National Library of Energy BETA

Sample records for aq batch id

  1. Aq Dryers Agricultural Drying Low Temperature Geothermal Facility...

    Open Energy Info (EERE)

    Aq Dryers Agricultural Drying Low Temperature Geothermal Facility Jump to: navigation, search Name Aq Dryers Agricultural Drying Low Temperature Geothermal Facility Facility Aq...

  2. Batch Jobs

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

    Batch Jobs Batch Jobs Overview Batch jobs are jobs that run non-interactively under the control of a "batch script," which is a text file containing a number of job directives and Linux commands or utilities. Batch scripts are submitted to the "batch system," where they are queued awaiting free resources. The batch scheduler/resource manager for Cori is SLURM. Bare-bones batch script A very simple SLURM batch script will look like this. #!/bin/bash -l #SBATCH -p regular

  3. Batch Jobs

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

    Batch Jobs Batch Jobs Overview Batch jobs are jobs that run non-interactively under the control of a "batch script," which is a text file containing a number of job directives and LINUX commands or utilities. Batch scripts are submitted to the "batch system," where they are queued awaiting free resources on Hopper. The batch system on Hopper is known as "Torque." Bare-Bones Batch Script The simplest Hopper batch script will look something like this. #PBS -q regular

  4. Batch Jobs

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

    that run non-interactively under the control of a "batch script," which is a text file (shell script) containing a number of job directives and LINUX commands. Batch scripts are...

  5. 4-ID beamline layout

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

    Sector 4 beamline layout Overview Sector 4 uses a canted undulator straight section to operate two beamlines The 4-ID-C beamline operates between 500 and 3000 eV while the 4-ID-D...

  6. NDA BATCH 2002-02

    SciTech Connect (OSTI)

    Lawrence Livermore National Laboratory

    2009-12-09

    QC sample results (daily background checks, 20-gram and 100-gram SGS drum checks) were within acceptable criteria established by WIPP's Quality Assurance Objectives for TRU Waste Characterization. Replicate runs were performed on 5 drums with IDs LL85101099TRU, LL85801147TRU, LL85801109TRU, LL85300999TRU and LL85500979TRU. All replicate measurement results are identical at the 95% confidence level as established by WIPP criteria. Note that the batch covered 5 weeks of SGS measurements from 23-Jan-2002 through 22-Feb-2002. Data packet for SGS Batch 2002-02 generated using gamma spectroscopy with the Pu Facility SGS unit is technically reasonable. All QC samples are in compliance with established control limits. The batch data packet has been reviewed for correctness, completeness, consistency and compliance with WIPP's Quality Assurance Objectives and determined to be acceptable. An Expert Review was performed on the data packet between 28-Feb-02 and 09-Jul-02 to check for potential U-235, Np-237 and Am-241 interferences and address drum cases where specific scan segments showed Se gamma ray transmissions for the 136-keV gamma to be below 0.1 %. Two drums in the batch showed Pu-238 at a relative mass ratio more than 2% of all the Pu isotopes.

  7. Badging, Real ID

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

    Office » Badging, Real ID Badging, Real ID Effective Nov. 3, 2014, the Lab will implement requirements of the REAL ID Act. Contact Badge Office (505) 667-6901 Email Badge requirements US citizen employees must present a photo ID and proof of US citizenship. See Security Smart on Proof of United States Citizenship for the Badge Office (pdf). Foreign national guests and employees must have an approved visit and present a valid passport and documentation of US legal status and work authorizations.

  8. Beamline 29-ID

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

    & Milestones IEX Advisory Committees FDR Beamline Information RSXS ARPES APS Ring Status Current APS Schedule Intermediate Energy X-Rays (29-ID): The Intermediate Energy...

  9. Transferring Data from Batch Jobs

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

    Transferring Data from Batch Jobs Transferring Data from Batch Jobs Examples Once you are set up for automatic authentication (see HPSS Passwords) you can access HPSS within batch...

  10. Submitting Batch Jobs

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

    Submitting Batch Jobs Submitting Batch Jobs Debug Jobs Short jobs requesting less than 30 minutes and requiring 512 nodes (2,048 cores) or fewer can run in the debug queue. From 5am-6pm Pacific Time, 256 nodes are reserved for debugging and interactive use. See also, running Interactive Jobs. Sample Batch Scripts The following batch script requests 8 cores on 2 nodes with a 10 minute wall clock limit in the debug queue. Torque directive lines tell the batch system how to run a job and begin with

  11. Example Hopper Batch Scripts

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

    batch system must wait for the desired big memory nodes to become available. Running Hybrid MPIOpenMP Applications Hybrid MPIOpenMP Example: New Recommendations (recommended)...

  12. Running Interactive Batch Jobs

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

    Interactive Batch Jobs Running Interactive Batch Jobs You cannot login to the PDSF batch nodes directly but you can run an interactive session on a batch node using either qlogin or qsh. This can be useful if you are doing something that is potentially disruptive or if the interactive nodes are overloaded. qlogin will give you an interactive session in the same window as your original session on PDSF, however, you must have your ssh keys in place. You can do this locally on PDSF by following

  13. Example Batch Scripts

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

    Example Batch Scripts Example Batch Scripts Sample Batch Scripts One of the most noted differences between the Hopper system and other NERSC systems is the number of cores per node is NOT a power of two. This means if you want to run a job on 32 cores, two nodes will be used and some cores will remain idle. Basic Batch Script This script uses the default 24 cores per node, (except on the remainder node when the number of cores requested is not a multiple of 24) #PBS -q debug #PBS -l

  14. EERE Program Management Guide - Appendices A-Q | Department of Energy

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

    Appendices A-Q EERE Program Management Guide - Appendices A-Q Appendices A-Q provide information on the EERE multi-year program plan template. PDF icon appendix_a-q.pdf More Documents & Publications EERE Program Management Guide - Appendix H EERE Program Management Guide - Appendix P EERE Program Management Guide - Appendix I

  15. Real ID Act in brief

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

    Visitors » Badging, Badge Office » Real ID Act in brief Real ID Act in brief Effective Nov. 3, 2014, the Lab will implement requirements of the REAL ID Act. Contact Badge Office (505) 667-6901 Email REAL ID Act in brief REAL ID is a coordinated effort by the states and the Federal Government to improve the reliability and accuracy of state-issued identification documents, which should inhibit terrorists' ability to evade detection by using fraudulent identification. REAL ID implements a 9/11

  16. 4-ID-D optics

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

    4-ID-D Beamline Optics A schetch of the major optical components for beam line 4-ID-D are shown above. All these components located in the B-station upstream from the D...

  17. Data ID Service

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

    ID Service First DOI for a DOE dataset was minted by OSTI and registered with DataCite on 8/10/2011 from the DOE Atmospheric Radiation Measurement (ARM) Climate Research Facility at Oak Ridge National Laboratory http://dx.doi.org/10.5439/1021460 Disseminate Our Results: "Our success should be measured not when a project is completed or an experiment concluded, but when scientifc and technical information is disseminated. Beyond broad availability of technical reports, e-prints and

  18. Blind Modal ID

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

    Research Projects » Blind Modal ID Blind separation of high-resolution vibration modes High-resolution video camera measurement of the structural vibration (the top video) could be separated into individual, monotone, vibration modes, which enable high-resolution visualization and analysis of structural dynamics. Contact Yongchao Yang (832) 335-3003 Email David Mascarenas dmascarenas@lanl.gov (505) 665-0881 Original video = Mode 1 - 6.34 Hz + Mode 2 - 17.96 Hz + Mode 3 - 25.89 Hz (higher

  19. T ID CODE I

    National Nuclear Security Administration (NNSA)

    T ID CODE I DE- , I AC52- AMENDMENT OF SOLICITATION/MODIFICATlON OF CONTRACT I. CONTRAC I 06NA25396 I Los Alamos National Security, LLC 4200 West Jernez Road Suite 400 Los Alamos, NM 87544 PAGE 1 OF 1 PAGES 2. AMENDMENTIMODIFICATION NO. A029 U.S. Department of Energy National Nuclear Security Administration Manager, Los Alamos Site Office 528 3sth Street Los Alamos, NM 87544 I 9B. DATED (SEE ITEM 11) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) 10A. MODIFICATION OF

  20. Example Batch Scripts

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

    Example Batch Scripts Example Batch Scripts Here are some sample job scripts that cover the most of the use cases on Edison. If you find anything that you need is missing, please let us know at consult at nersc dot gov. Note, Edison queue may still undergo configuration change as we gain more insight about how Slurm works with Edison workload. Basic Job Scripts #!/bin/bash -l #SBATCH -p regular #SBATCH -N 2 #SBATCH -t 04:00:00 #SBATCH -J my_job #SBATCH -o my_job.o%j #Edison has 24 cores per

  1. DHSIsotopeID

    Energy Science and Technology Software Center (OSTI)

    2007-12-18

    DHSIsotopeID is an application designed to read and analyze radiation measurement files taken by radiation measurement files taken by radiation portal monitors, and in particular, by the advanced spectroscopic portals. It requires that the data files be in the N42 file format, compliant with the interface control documents for DNDO radiation measurement files. It carries out an automated analysis to determine which isotopes are present in the spectra, and then presents the results in graphicalmore » form to the user. It also enables further post-processing and analysis, for example by performing further analysis on selected regions of interest of the spectrum, as designated by the user via the graphical interface.« less

  2. Using the PDSF Batch System

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

    System Using the PDSF Batch System Submitting PDSF Jobs An introduction to submitting jobs to the PDSF batch system. Read More IO Resources IO resources are an essential tool...

  3. Hydration of Kr(aq) in dilute and concentrated solutions

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

    Chaudhari, Mangesh I.; Sabo, Dubravko; Pratt, Lawrence R.; Rempe, Susan B.

    2014-10-13

    Molecular dynamics simulations of water with both multi-Kr and single Kr atomic solutes are carried out to implement quasi-chemical theory evaluation of the hydration free energy of Kr(aq). This approach obtains free energy differences reflecting Kr–Kr interactions at higher concentrations. Those differences are negative changes in hydration free energies with increasing concentrations at constant pressure. The changes are due to a slight reduction of packing contributions in the higher concentration case. The observed Kr–Kr distributions, analyzed with the extrapolation procedure of Krüger et al., yield a modestly attractive osmotic second virial coefficient, B2 ≈ -60 cm3/mol. Moreover, the thermodynamic analysismore » interconnecting these two approaches shows that they are closely consistent with each other, providing support for both approaches.« less

  4. APS Beamline 6-ID-B,C

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

    6-ID-B,C Home Recent Publications Beamline Info Optics Instrumentation Software User Info Beamline 6-ID-B,C Beamline 6-ID-B,C is operated by the Magnetic Materials Group in the...

  5. APS Beamline 6-ID-D

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

    MM-Group Home MMG Advisory Committees 6-ID-D Home Recent Publications Beamline Info Optics Instrumentation Software User Info Beamline 6-ID-D Beamline 6-ID-D is operated by the...

  6. DOEDataID_24X30poster112515

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

    home/doe-data-id-service

  7. DOE-ID Twitter Site

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

    what's going on at DOE-Idaho? Follow DOE-ID public affairs supervisor Brad Bugger on Twitter at doeidbug. https:twitter.comdoeidbug Editorial Date May 9, 2911 By Brad Bugger...

  8. Progressing batch hydrolysis process

    DOE Patents [OSTI]

    Wright, J.D.

    1985-01-10

    A progressive batch hydrolysis process is disclosed for producing sugar from a lignocellulosic feedstock. It comprises passing a stream of dilute acid serially through a plurality of percolation hydrolysis reactors charged with feed stock, at a flow rate, temperature and pressure sufficient to substantially convert all the cellulose component of the feed stock to glucose. The cooled dilute acid stream containing glucose, after exiting the last percolation hydrolysis reactor, serially fed through a plurality of pre-hydrolysis percolation reactors, charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the hemicellulose component of said feedstock to glucose. The dilute acid stream containing glucose is cooled after it exits the last prehydrolysis reactor.

  9. Progressing batch hydrolysis process

    DOE Patents [OSTI]

    Wright, John D.

    1986-01-01

    A progressive batch hydrolysis process for producing sugar from a lignocellulosic feedstock, comprising passing a stream of dilute acid serially through a plurality of percolation hydrolysis reactors charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the cellulose component of the feedstock to glucose; cooling said dilute acid stream containing glucose, after exiting the last percolation hydrolysis reactor, then feeding said dilute acid stream serially through a plurality of prehydrolysis percolation reactors, charged with said feedstock, at a flow rate, temperature and pressure sufficient to substantially convert all the hemicellulose component of said feedstock to glucose; and cooling the dilute acid stream containing glucose after it exits the last prehydrolysis reactor.

  10. Transferring Data from Batch Jobs

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

    Transferring Data from Batch Jobs Transferring Data from Batch Jobs Examples Once you are set up for automatic authentication (see HPSS Passwords) you can access HPSS within batch scripts. You can add the following lines at the end of your batch script. HSI will accept one-line commands on the HSI command line, e.g., hsi put filename HSI, ftp and pftp read from the standard input (stdin) and a list of commands can be placed in a text file (script) and redirected into the given utility, e.g., htp

  11. NDA BATCH 2009-7

    SciTech Connect (OSTI)

    Lawrence Livermore National Laboratory

    2009-10-30

    The testing facility is LLNL plutonium facility segmented gamma scanner. 100% of the radioassay data in the batch data report is reviewed.

  12. Supporting Multiple Workloads, Batch Systems,

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

    Multiple Workloads, Batch Systems, and Computing Environments on a Single Linux Cluster Larry Pezzaglia National Energy Research Scientific Computing Center Lawrence...

  13. U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus

    Office of Scientific and Technical Information (OSTI)

    improved observations from the Ozone Monitoring Instrument (OMI) (Journal Article) | SciTech Connect SciTech Connect Search Results Journal Article: U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI) Citation Details In-Document Search Title: U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI) Emissions of nitrogen oxides

  14. U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus

    Office of Scientific and Technical Information (OSTI)

    improved observations from the Ozone Monitoring Instrument (OMI) (Journal Article) | DOE PAGES Accepted Manuscript: U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI) Title: U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI) Emissions of nitrogen oxides (NOx) and, subsequently, atmospheric levels of nitrogen dioxide

  15. DOE-ID Operations Summary

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

    June 5, 2013 DOE-ID Operations Summary For the Period May 16, through May 30, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC - Shannon Brennan, DOE-ID, (208) 526-3993.

  16. DOE-ID Operations Summary

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

    24, 2013 DOE-ID Operations Summary For the Period May 30, 2013 through June 12, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC - Shannon Brennan, DOE-ID, (208) 526-3993.

  17. Thermal Analysis of Waste Glass Batches: Effect of Batch Makeup on

    Office of Scientific and Technical Information (OSTI)

    Gas-Evolving Reactions (Book) | SciTech Connect Book: Thermal Analysis of Waste Glass Batches: Effect of Batch Makeup on Gas-Evolving Reactions Citation Details In-Document Search Title: Thermal Analysis of Waste Glass Batches: Effect of Batch Makeup on Gas-Evolving Reactions Batches made with a variety of precursors were subjected to thermo-gravimetric analysis. The baseline modifications included all-nitrate batch with sucrose addition, all-carbonate batch, and batches with different

  18. Data ID Service | DOE Data Explorer

    Office of Scientific and Technical Information (OSTI)

    DOE Data ID Service DOE Data ID Service Note 1: This section pertains to datasets, dataset records, and Digital Object Identifiers (DOIs). It is not related to the collection...

  19. APS Beamline 6-ID-B,C

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

    B,C Home Recent Publications Beamline Info Optics Instrumentation Software User Info Beamline 6-ID-B,C Beamline 6-ID-B,C is operated by the Magnetic Materials Group in the X-ray...

  20. APS Beamline 6-ID-D

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

    D Home Recent Publications Beamline Info Optics Instrumentation Software User Info Beamline 6-ID-D Beamline 6-ID-D is operated by the Magnetic Materials Group in the X-ray Science...

  1. Batch compositions for cordierite ceramics

    DOE Patents [OSTI]

    Hickman, David L. (Big Flats, NY)

    1994-07-26

    Ceramic products consisting principally of cordierite and a method for making them are provided, the method employing batches comprising a mineral component and a chemical component, the mineral component comprising clay and talc and the chemical component consisting essentially of a combination of the powdered oxides, hydroxides, or hydrous oxides of magnesium, aluminum and silicon. Ceramics made by extrusion and firing of the batches can exhibit low porosity, high strength and low thermal expansion coefficients.

  2. DOE-ID Operations Summary

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

    07, 2013 DOE-ID Operations Summary For the Period July 8, 2013 through July 28, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced

  3. DOE-ID Operations Summary

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

    6, 2013 DOE-ID Operations Summary For the Period July 29, 2013 through August 12, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced

  4. DOE-ID Operations Summary

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

    10, 2013 DOE-ID Operations Summary For the Period August 12, 2013 through August 26, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709.

  5. DOE-ID Operations Summary

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

    8, 2013 DOE-ID Operations Summary For the Period September 30, 2013 through October 31, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709.

  6. DOE-ID Operations Summary

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

    6, 2014 DOE-ID Operations Summary For the Period November 01, 2013 through November 30, 2013 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709.

  7. DOE-ID Operations Summary

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

    23, 2015 Updated on April 28, 2015 DOE-ID Operations Summary For the Period September 30, 2014 through November 1, 2014 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle

  8. DOE-ID Operations Summary

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

    7, 2015 DOE-ID Operations Summary For the Period January 1, 2015 - January 31, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709.

  9. DOE-ID Operations Summary

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

    6, 2015 DOE-ID Operations Summary For the Period February 1, 2015 - February 28, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709.

  10. DOE-ID Operations Summary

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

    4, 2015 DOE-ID Operations Summary For the Period May 1, 2015 - May 31, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709. Advanced

  11. DOE-ID Operations Summary

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

    December 2, 2015 DOE-ID Operations Summary For the Period September 1, 2015 - September 30, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208)

  12. DOE-ID Operations Summary

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

    7, 2015 DOE-ID Operations Summary For the Period August 1, 2015 - August 31, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709.

  13. DOE-ID Operations Summary

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

    February 11, 2016 DOE-ID Operations Summary For the Period November 1, 2015 - November 30, 2015 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208)

  14. Document ID Number: RL-721

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

    ---------------------------------------------------------- Document ID Number: RL-721 REV 4 NEPA REVIEW SCREENING FORM DOE/CX-00066 I. Project Title: Nesting Bird Deterrent Study at the 241-C Tank Farm CX B3.8, "Outdoor Terrestrial Ecological and Environmental Research" II. Project Description and Location (including Time Period over which proposed action will occur and Project Dimensions - e.g., acres displaced/disturbed, excavation length/depth, area/location/number of buildings,

  15. II.CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    1 II.CONTRACT ID CODE ~AGE 1 of AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT PAGES AC 5. PROJECT NO. (If applicable) 3. EFFECTNE DATE 2. AMENDMENTfMODIFICA TION NO. 4. REQUISITIONIPURCHASE REQ. NO. See Block 16c. NOPR 7. ADMINISTERED BY (If other than Item 6) CODE 05008 6. ISSUED BY CODE 05008 U.S. Department of Energy National Nuclear Security Administration U.S. Department of Energy National Nuclear Security Administration P.O. Box 2050 Oak Ridge, TN 37831 P.O. Box 2050 Oak Ridge, TN

  16. IDS Climate Change and Development Centre Resources | Open Energy...

    Open Energy Info (EERE)

    IDS Climate Change and Development Centre Resources Jump to: navigation, search Tool Summary Name: IDS Climate Change and Development Centre Resources AgencyCompany Organization:...

  17. 1-ID Home Page | Advanced Photon Source

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

    1-ID Home Infrastructure Techniques Data Analysis Publications X-ray Resources Materials Physics and Engineering Group Useful Links Current APS status ESAF System GUP System X-Ray...

  18. Id-1 and Id-2 genes and products as markers of epithelial cancer

    DOE Patents [OSTI]

    Desprez, Pierre-Yves; Campisi, Judith

    2011-10-04

    A method for detection and prognosis of breast cancer and other types of cancer. The method comprises detecting expression, if any, for both an Id-1 and an Id-2 genes, or the ratio thereof, of gene products in samples of breast tissue obtained from a patient. When expressed, Id-1 gene is a prognostic indicator that breast cancer cells are invasive and metastatic, whereas Id-2 gene is a prognostic indicator that breast cancer cells are localized and noninvasive in the breast tissue.

  19. Id-1 and Id-2 genes and products as markers of epithelial cancer

    DOE Patents [OSTI]

    Desprez, Pierre-Yves; Campisi, Judith

    2008-09-30

    A method for detection and prognosis of breast cancer and other types of cancer. The method comprises detecting expression, if any, for both an Id-1 and an Id-2 genes, or the ratio thereof, of gene products in samples of breast tissue obtained from a patient. When expressed, Id-1 gene is a prognostic indicator that breast cancer cells are invasive and metastatic, whereas Id-2 gene is a prognostic indicator that breast cancer cells are localized and noninvasive in the breast tissue.

  20. 2011 Annual Planning Summary for Idaho Operations Office (ID) | Department

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

    of Energy Idaho Operations Office (ID) 2011 Annual Planning Summary for Idaho Operations Office (ID) The ongoing and projected Environmental Assessments and Environmental Impact Statements for 2011 and 2012 within the Idaho Operations Office (ID) (See Environmental Management). PDF icon 2011 Annual Planning Summary for Idaho Operations Office (ID) More Documents & Publications 2010 Annual Planning Summary for Idaho Operations Office (ID) 2012 Annual Planning Summary for SLAC Site Office

  1. Requesting a Digital ID | Department of Energy

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

    a Digital ID Requesting a Digital ID S puzzle1.jpg tep One - Registering with the DOE's Management Information System (MIS) Before you request a DOE Digital Identity, you must register in DOE's Management Information System (MIS). Please note that DOE Federal employees are already registered and do not need to complete this step. The may skip to step two. During the registration process, you will be required to select a DOE sponsor. Your sponsor is the DOE employee who certifies that you have a

  2. I.D I VI Figure

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

    ~press - ,~,.--;~ 3.1 ,,~-.::;:.--- ~ ( 3.1 ( ;-; t\ I.D I VI Figure 9-1. Location of the original Cypress Grove Set-Aside and the Stave Island and Georgia Power replacement Areas. Set-Aside 9: Cypress Grove, Stave Island, and Georgia Power

  3. Microsoft Word - DOE-ID-INL-12-015.doc

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

    15 SECTION A. Project Title: Materials and Fuels Complex Underground and Aboveground Storage Tank Replacement SECTION B. Project Description: The purpose of this project is to permanently close and remove the Materials and Fuels Complex (MFC) 4,000 gallon bio-diesel underground storage tank (UST) [Site ID# 7230/Facility ID # 6-120614/Tank ID # 99ANL00013] and remove the 1,000 gallon E-85 aboveground storage tank (AST) [Site ID# 7230/Facility ID# 6-120614/Tank ID# 05MFC00035] and replace the two

  4. Department of Energy Idaho - Inside DOE-ID

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

    Inside ID Inside Idaho Operations Office (DOE-ID) DOE-ID Mission and Vision Brief History of the Idaho National Laboratory (INL) DOE-ID Agreement in Principle Organization Chart Employment Opportunities New Employee Orientation EOD Checklist - 68 KB EOD Forms - 261 KB DOE/Tribal Agreement in Principle Strategic Partnership Projects (formerly WFO) Idaho Site Contractor Timeline - 3.7 MB ID@Work Introduces some of the DOE-ID employees and the jobs they perform. Last Updated: 05/21/2015

  5. Facility Representative Program Outstanding at ID

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

    June 19, 2007 Facility Representative Program Outstanding at ID Idaho's three DOE Complex-wide Facility Representative of the Year (FROTY) recipients at this year's conference pose for a photo shoot with Elvis. L to R: Dary Newbry 2005 FROTY, Bob Seal 2006 FROTY, Bob Knighten 2004 FROTY Facility representatives (FRs) are the eyes and ears of the federal government at the Idaho National Laboratory. They oversee the people, processes, facilities and systems that ensure safety at INL facilities.

  6. Facility Representative Program ID Selects FR of the Year

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

    Facility Representative Program ID Selects FR of the Year John Martin DOE-ID Facility Representative John Martin DOE-ID Facility Representative of the Year. John Martin was selected as DOE-ID's Facility Representative of the Year and the office's nominee for the 2007 DOE Facility Representative of the Year Award. John was selected from an exceptional field of candidates to represent DOE-ID at the Facility Representative Annual Workshop in Las Vegas this May. Each year the Department of Energy

  7. CHANGE IN ACCEPTABLE ID DOCUMENTS FOR JLAB ACCESS:

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

    CHANGE IN ACCEPTABLE ID DOCUMENTS FOR JLAB ACCESS: The REAL ID Act (Public Law 109-13) now determines which state driver's license can be presented and accepted as a valid ID document for access to Jefferson Lab. The following states/US territories have been determined by the U.S. Department of Homeland Security to have failed to comply with the REAL ID Act: American Samoa, Illinois, Minnesota, Missouri, and Washington. As of March 2, 2015, Jefferson Lab will begin using the REAL ID Act

  8. Mo Year Report Period: EIA ID NUMBER:

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

    Mo Year Report Period: EIA ID NUMBER: http://www.eia.gov/survey/form/eia_14/instructions.pdf Mailing Address: Secure File Transfer option available at: (e.g., PO Box, RR) https://signon.eia.doe.gov/upload/noticeoog.jsp Electronic Transmission: The PC Electronic Zip Code - Data Reporting Option (PEDRO) is available. If interested in software, call (202) 586-9659. Email form to: OOG.SURVEYS@eia.doe.gov - - - - Fax form to: (202) 586-9772 Mail form to: Oil & Gas Survey Email address: U.S.

  9. SLAC Dosimeter / ID Request Form A

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

    Feb 2009 (updated 13 May 2010) SLAC-I-760-0A07J-006-R010 1 of 2 SLAC Dosimeter / ID Request Form A (For applicants who have completed SLAC Environment, Safety, and Health Training) Sections 1-5 completed by applicant. Section 1: Contact Information Last name: First name: MI: Male Female Birth year (yyyy): Job title: Contact information/mailing address: City: State: Zip code: Country: Dept/Group: Phone number: Mail stop: Users or non-SLAC employees only: List employer, company, or university :

  10. Airless drying -- Developments since IDS'94

    SciTech Connect (OSTI)

    Stubbing, T.J.

    1999-09-01

    Since its introduction to IDS'94 delegates, significant progress has been made with the development of airless drying technology. The ceramic industry internationally is beginning to benefit from both the energy use and drying time reductions it achieves, while on the basis of further theoretical work carried out since 1993 other industries, including the bioenergy sector, should also soon begin to exploit its advantages. As global warming becomes a reality and oil reserves decline, superheated steam drying and gasification of biomass will contribute to the mitigation of those problems.

  11. Your Unanswered Questions…. Answered- Batch 2

    Broader source: Energy.gov [DOE]

    Secretary Chu hosted an online town hall to discuss President Obama's clean energy innovation agenda -- and while he was able to answer about 10 questions submitted online during the event, we received more than 200! Here is our second batch of questions and answers.

  12. Carry Emergency Contact Card with your Lab ID | Jefferson Lab

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

    Carry Emergency Contact Card with your Lab ID Jefferson Lab Emergency Manager, Tina Menefee, encourages all members of the Jefferson Lab community to carry their JLab emergency notification and reminder card with their lab ID. Put it on your ID lanyard or carry it in your wallet. The card (front and back pictured below) lists the primary numbers where emergencies, injuries, or any abnormal situation should be reported. The other side of the card provides guidance on reporting emergencies and

  13. RAPID/Roadmap/12-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Contact Us State Biological Resource Considerations (12-ID-a) The Idaho Department of Fish & Game preserves wildlife against any direct take, including wild animals, birds, and...

  14. RAPID/Roadmap/8-ID-e | Open Energy Information

    Open Energy Info (EERE)

    ID-e < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools...

  15. RAPID/Roadmap/3-ID-e | Open Energy Information

    Open Energy Info (EERE)

    ID-e < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools...

  16. RAPID/Roadmap/14-ID-b | Open Energy Information

    Open Energy Info (EERE)

    RAPIDRoadmap14-ID-b < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal...

  17. RAPID/Roadmap/8-ID-a | Open Energy Information

    Open Energy Info (EERE)

    RAPIDRoadmap8-ID-a < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower...

  18. RAPID/Roadmap/6-ID-b | Open Energy Information

    Open Energy Info (EERE)

    RAPIDRoadmap6-ID-b < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower...

  19. RAPID/Roadmap/17-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Contact Us Aesthetic Resource Assessment (17-ID-a) 17IDAAestheticResourceAssessment.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  20. RAPID/Roadmap/9-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Environmental Review Process (9-ID-a) Add overview. 09IDAStateEnvironmentalProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  1. RAPID/Roadmap/14-ID-c | Open Energy Information

    Open Energy Info (EERE)

    Geothermal Hydropower Solar Tools Contribute Contact Us Underground Injection Control Permit (14-ID-c) Rule 40 of the Idaho Department of Water Resources' Drilling for...

  2. RAPID/Roadmap/14-ID-d | Open Energy Information

    Open Energy Info (EERE)

    Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us 401 Water Quality Certification (14-ID-d) IDEQ is...

  3. RAPID/Roadmap/3-ID-b | Open Energy Information

    Open Energy Info (EERE)

    Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us State Land Access Overview (3-ID-b) If a project is...

  4. RAPID/Roadmap/14-ID-f | Open Energy Information

    Open Energy Info (EERE)

    Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us 401 NPDES Water Quality Certification (14-ID-f) Idaho...

  5. RAPID/Roadmap/4-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us State Exploration Process (4-ID-a) 04IDAStateExploration...

  6. RAPID/Roadmap/11-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us State Cultural Considerations (11-ID-a) Idaho has a statute that provides state...

  7. RAPID/Roadmap/15-ID-b | Open Energy Information

    Open Energy Info (EERE)

    BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us Air Quality Permit - Tier II Operating Permit (15-ID-b) Tier II Operating Permits are...

  8. RAPID/Roadmap/15-ID-a | Open Energy Information

    Open Energy Info (EERE)

    BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us Air Quality Permit - Permit to Construct (15-ID-a) The Idaho Department of Environmental...

  9. RAPID/Roadmap/5-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Geothermal Hydropower Solar Tools Contribute Contact Us Drilling and Well Development (5-ID-a) 05IDADrillingWellDevelopment.pdf Error creating thumbnail: Page number not in...

  10. DOE-ID FOIA Electronic Reading Room Documents

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

    Electronic Reading Room Documents Electronic Reading Room Documents The information contained here represents DOE-ID's responses to FOIA requests that have been or are likely to be...

  11. Temporary EPA ID Number Request | Open Energy Information

    Open Energy Info (EERE)

    Temporary EPA ID Number RequestLegal Abstract A developer that may "generate hazardous waste only from an episodic event" may instead apply for a temporary hazardous waste...

  12. DOE - Office of Legacy Management -- Lowman Mill Site - ID 01

    Office of Legacy Management (LM)

    Lowman Mill Site - ID 01 FUSRAP Considered Sites Site: Lowman Mill Site (ID.01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site Disposition: Radioactive Materials Handled: Primary Radioactive Materials Handled: Radiological Survey(s): Site Status: Also see Lowman, Idaho, Disposal Site Documents Related to Lowman Mill Site

  13. Id-1 and Id-2 genes and products as therapeutic targets for treatment of breast cancer and other types of carcinoma

    DOE Patents [OSTI]

    Desprez, Pierre-Yves; Campisi, Judith

    2014-09-30

    A method for treatment and amelioration of breast, cervical, ovarian, endometrial, squamous cells, prostate cancer and melanoma in a patient comprising targeting Id-1 or Id-2 gene expression with a delivery vehicle comprising a product which modulates Id-1 or Id-2 expression.

  14. JLab Registration/International Services - Researcher/Visitor ID

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

    Requirements Researcher/Visitor ID Requirements CHANGE IN ACCEPTABLE ID DOCUMENTS FOR JLAB ACCESS U.S. Citizens must bring a valid Government issued ID card that contains a photo such as a passport or valid driver's license. Non-driver photo identification cards issued by the Department of Motor Vehicles can be used as proof of identification. Lawful Permanent Resident of the United States must bring their Green Card or passport with valid I-551 stamp AND a valid government issued

  15. Poster - DOE Data ID Service | OSTI, US Dept of Energy, Office...

    Office of Scientific and Technical Information (OSTI)

    ID Service Document Files and References Available Downloads for this Document: applicationpdf icon Poster DOE Data ID Service Last updated on Tuesday 22 December...

  16. TANK 50 BATCH 0 SALTSTONE FORMULATION CONFIRMATION

    SciTech Connect (OSTI)

    Langton, C.

    2006-06-05

    Savannah River National Laboratory (SRNL) personnel were requested to confirm the Tank 50 Batch 0 grout formulation per Technical Task Request, SSF-TTR-2006-0001 (task 1 of 2) [1]. Earlier Batch 0 formulation testing used a Tank 50 sample collected in September 2005 and is described elsewhere [2]. The current testing was performed using a sample of Tank 50 waste collected in May 2006. This work was performed according to the Technical Task and Quality Assurance Plan (TT/QAP), WSRC-RP-2006-00594 [3]. The salt solution collected from Tank 50 in May 2006 contained approximately 3 weight percent more solids than the sample collected in September 2005. The insoluble solids took longer to settle in the new sample which was interpreted as indicating finer particles in the current sample. The saltstone formulation developed for the September 2005 Tank 50 Batch 0 sample was confirmed for the May 2006 sample with one minor exception. Saltstone prepared with the Tank 50 sample collected in May 2006 required 1.5 times more Daratard 17 set retarding admixture than the saltstone prepared with the September In addition, a sample prepared with lower shear mixing (stirring with a spatula) had a higher plastic viscosity (57 cP) than samples made with higher shear mixing in a blender (23cP). The static gel times of the saltstone slurries made with low shear mixing were also shorter ({approx}32 minutes) than those for comparable samples made in the blender ({approx}47 minutes). The addition of the various waste streams (ETP, HEU-HCAN, and GPE-HCAN) to Tank 50 from September 2005 to May 2006 has increased the amount of set retarder, Daratard 17, required for processing saltstone slurries through the Saltstone facility. If these streams are continued to be added to Tank 50, the quantity of admixtures required to maintain the same processing conditions for the Saltstone facility will probably change and additional testing is recommended to reconfirm the Tank 50 Saltstone formulation.

  17. RAPID/Roadmap/18-ID-b | Open Energy Information

    Open Energy Info (EERE)

    demonstrate insurance coverage that would protect the community from incurring clean-up costs in the event of the developer's insolvency. 18-ID-b.5 - Facility siting license...

  18. RAPID/Roadmap/6-ID-c | Open Energy Information

    Open Energy Info (EERE)

    Tools Contribute Contact Us Drinking Water Permit (6-ID-c) 06IDCDrinkingWaterPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  19. RAPID/Roadmap/7-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Contact Us Power Plant Siting Process (7-ID-a) 07IDAPowerPlantSitingConstruction.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  20. RAPID/Roadmap/13-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Contribute Contact Us State Land Use Assessment (13-ID-a) 13IDALandUseAssessment.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  1. RAPID/Roadmap/6-ID-a | Open Energy Information

    Open Energy Info (EERE)

    load A load is overlegal if the load is: width over 8'6"; Over 14' tall; Truck and trailer combined are over 75' long; or The load weighs over 80,000 pounds. 6-ID-a.2 - Meet...

  2. RAPID/Roadmap/19-ID-a | Open Energy Information

    Open Energy Info (EERE)

    to 19-ID-a.5 - Is a Change in Point of Diversion, Place of Use, Period of Use, or Nature of Use Needed for an Existing Water Right If the proposed activity will require a...

  3. RAPID/Roadmap/3-ID-a | Open Energy Information

    Open Energy Info (EERE)

    the IDL becomes involved only if they are notified and the Land Board requests their involvement. 3-ID-a.3 - Consultation (optional) IDL may meet with any other state agency to...

  4. Beamline 4-ID-C | Advanced Photon Source

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

    C 4-ID-C Home Recent Publications XSD-MM Home MM Advisory Committees FAQs Beamline Info Instrumentation Magnet Materials Internal Useful Links Current APS status ESAF System GUP...

  5. Employee Assistance Self-ID Form | Department of Energy

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

    Form-HQ PDF icon Employee Assistance Self-ID Form More Documents & Publications DOE HQ Special Needs Assistance in an Emergency DOE Emergency Special Needs Self-Identification...

  6. RAPID/Roadmap/3-ID-d | Open Energy Information

    Open Energy Info (EERE)

    Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us Land Use Permit (3-ID-d) The Idaho Department of Lands issues Land Use Permits for...

  7. T-642: RSA SecurID update to Customers

    Broader source: Energy.gov [DOE]

    RSA investigation has revealed that the attack resulted in certain information being extracted from RSA's systems. Some of that information is related to RSA's SecurID two-factor authentication products

  8. Microsoft Word - DOE-ID-INL-15-070.docx

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

    DOE-ID-INL-15-070 excluded petroleum and natural gas products that pre-exist in the environment such that there would be uncontrolled or unpermitted releases; (4) have the...

  9. Vermont Hazardous Waste Handler Site ID Form | Open Energy Information

    Open Energy Info (EERE)

    to library Legal Document- Permit ApplicationPermit Application: Vermont Hazardous Waste Handler Site ID FormLegal Abstract This form is used to notify the Vermont Agency of...

  10. NERSC Helps Physicists ID New Molecules With Unique Features

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

    NERSC Helps Physicists ID New Molecules With Unique Features NERSC Helps Physicists ID New Molecules With Unique Features Hollow magnetic cage molecules may have applications in technology, healthcare August 10, 2013 NERSC supercomputing resources helped Virginia Commonwealth University (VCU) researchers determine it may be possible to create large, hollow magnetic cage molecules that could be used in medicine as a drug delivery system to noninvasively treat tumors and in other emerging

  11. Microsoft Word - DOE-ID-INL-11-011.doc

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

    1 SECTION A. Project Title: MFC-752 Analytical Laboratory Seismic Upgrade SECTION B. Project Description: The Department of Energy, Idaho Operations Office (DOE-ID) conducted a review of the nuclear safety practices on the Materials and Fuels Complex (MFC) documented safety analyses (DSAs) in 2005 during transition of operating contractors. The DOE-ID assessment concluded that the MFC DSAs had potential inadequacies in following the safe harbor methodology of the nuclear safety rule. That review

  12. Microsoft Word - DOE-ID-INL-13-001.doc

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

    NEPA-CX DETERMINATION Idaho National Laboratory Page 1 of 1 CX Posting No.: DOE-ID-INL-13-001 SECTION A. Project Title: INL Research (Technical) Library Lease Termination SECTION B. Project Description: The proposed activity will terminate the current lease of the INLTechnical Library (IF-618, University Place) at 1776 Science Center Drive in Idaho Falls, ID on or about February 28, 2013 for cost savings and footprint reduction purposes. A facility walkthrough by BEA personnel will occur on or

  13. Microsoft Word - DOE-ID-INL-13-007.doc

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

    8 EC Document No.: DOE-ID-INL-13-007 SECTION A. Project Title: Seismic Monitoring for Seismic Hazards Analyses SECTION B. Project Description: The Idaho National Laboratory (INL) Probabilistic Seismic Hazards Analysis (PSHA) Phase I - Data Collection and Evaluation project is being conducted by Battelle Energy Alliance (BEA) at the request of the U.S. Department of Energy Idaho Operations office (DOE-ID) and INL Management. The project is being conducted from FY-2013 to FY-2017. Earthquake data

  14. Physicists ID Mechanism that Stabilizes Plasma in Tokamaks

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

    Physicists ID Mechanism that Stabilizes Plasma in Tokamaks Physicists ID Mechanism that Stabilizes Plasma in Tokamaks Calculations Run at NERSC Create 3D Simulations of Fusion Plasmas January 4, 2016 Contact: Kathy Kincade, kkincade@lbl.gov, +1 510 495 2124 jardinfusion A cross-section of the virtual plasma showing where the magnetic field lines intersect the plane. The central section has field lines that rotate exactly once. Image: Stephen Jardin A team of physicists led by Stephen Jardin of

  15. Uranium and Strontium Batch Sorption and Diffusion Kinetics into...

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

    Uranium and Strontium Batch Sorption and Diffusion Kinetics into Mesoporous Silica Friday, February 27, 2015 Figure 1 Figure 1. Transmission electron microscopy images of (A)...

  16. DOE Data ID Service | OSTI, US Dept of Energy, Office of Scientific and

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

    Technical Information DOE Data ID Service DataCite | Contact DOE Data ID Service DOE Data ID Service DOE Data ID Service The DOE Office of Scientific and Technical Information (OSTI) offers a service for registering datasets to help increase access to digital data from DOE-funded scientific research. Through the DOE Data ID Service, OSTI assigns persistent identifiers, known as Digital Object Identifiers (DOIs), to datasets submitted by DOE and its contractor and grantee researchers and

  17. Microsoft Word - DOE-ID-INL-12-018.doc

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

    8 SECTION A. Project Title: Rexburg Bus Lot (B60-1789-D-NE) Lease Termination SECTION B. Project Description: The proposed activity will terminate the lease of approximately four bus spaces at the Rexburg Parking Lot (B60-1789-D-NE) at South 5 th West in Rexburg, ID on or about July 31, 2012 for cost savings and consolidation to the existing lot at Rigby, ID. A facility walkthrough by BEA personnel will be performed in order to ensure the facility is ready for turnover back to the owner.

  18. Microsoft Word - DOE-ID-INL-14-046.docx

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

    DOE0ID NEPA CX DETERMINATION Idaho National Laboratory Page 1 of 2 CX Posting No.: DOE-ID-INL-14-046 SECTION A. Project Title: Materials and Fuel Complex (MFC)-752 Analytical Laboratory (AL) Fire Suppression System SECTION B. Project Description: The project scope consists of adding fire water suppression capability to MFC-752AL maintenance cells RM-A116, and to the basement clean room located by room B-30. In addition to the enhanced fire suppression capability, appropriate fire detection will

  19. Analyzing source apportioned methane in northern California during Discover-AQ-CA using airborne measurements and model simulations

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

    Johnson, Matthew S.; Yates, Emma L.; Iraci, Laura T.; Loewenstein, Max; Tadić, Jovan M.; Wecht, Kevin J.; Jeong, Seongeun; Fischer, Marc L.

    2014-12-01

    This study analyzes source apportioned methane (CH4) emissions and atmospheric mixing ratios in northern California during the Discover-AQ-CA field campaign using airborne measurement data and model simulations. Source apportioned CH4 emissions from the Emissions Database for Global Atmospheric Research (EDGAR) version 4.2 were applied in the 3-D chemical transport model GEOS-Chem and analyzed using airborne measurements taken as part of the Alpha Jet Atmospheric eXperiment over the San Francisco Bay Area (SFBA) and northern San Joaquin Valley (SJV). During the time period of the Discover-AQ-CA field campaign EDGAR inventory CH4 emissions were ~5.30 Gg day –1 (Gg = 1.0 ×more » 109 g) (equating to ~1.90 × 103 Gg yr–1) for all of California. According to EDGAR, the SFBA and northern SJV region contributes ~30% of total CH4 emissions from California. Source apportionment analysis during this study shows that CH4 mixing ratios over this area of northern California are largely influenced by global emissions from wetlands and local/global emissions from gas and oil production and distribution, waste treatment processes, and livestock management. Model simulations, using EDGAR emissions, suggest that the model under-estimates CH4 mixing ratios in northern California (average normalized mean bias (NMB) = –5.2% and linear regression slope = 0.20). The largest negative biases in the model were calculated on days when large amounts of CH4 were measured over local emission sources and atmospheric CH4 mixing ratios reached values >2.5 parts per million. Sensitivity emission studies conducted during this research suggest that local emissions of CH4 from livestock management processes are likely the primary source of the negative model bias. These results indicate that a variety, and larger quantity, of measurement data needs to be obtained and additional research is necessary to better quantify source apportioned CH4 emissions in California.« less

  20. Analyzing source apportioned methane in northern California during Discover-AQ-CA using airborne measurements and model simulations

    SciTech Connect (OSTI)

    Johnson, Matthew S.; Yates, Emma L.; Iraci, Laura T.; Loewenstein, Max; Tadić, Jovan M.; Wecht, Kevin J.; Jeong, Seongeun; Fischer, Marc L.

    2014-12-01

    This study analyzes source apportioned methane (CH4) emissions and atmospheric mixing ratios in northern California during the Discover-AQ-CA field campaign using airborne measurement data and model simulations. Source apportioned CH4 emissions from the Emissions Database for Global Atmospheric Research (EDGAR) version 4.2 were applied in the 3-D chemical transport model GEOS-Chem and analyzed using airborne measurements taken as part of the Alpha Jet Atmospheric eXperiment over the San Francisco Bay Area (SFBA) and northern San Joaquin Valley (SJV). During the time period of the Discover-AQ-CA field campaign EDGAR inventory CH4 emissions were ~5.30 Gg day –1 (Gg = 1.0 × 109 g) (equating to ~1.90 × 103 Gg yr–1) for all of California. According to EDGAR, the SFBA and northern SJV region contributes ~30% of total CH4 emissions from California. Source apportionment analysis during this study shows that CH4 mixing ratios over this area of northern California are largely influenced by global emissions from wetlands and local/global emissions from gas and oil production and distribution, waste treatment processes, and livestock management. Model simulations, using EDGAR emissions, suggest that the model under-estimates CH4 mixing ratios in northern California (average normalized mean bias (NMB) = –5.2% and linear regression slope = 0.20). The largest negative biases in the model were calculated on days when large amounts of CH4 were measured over local emission sources and atmospheric CH4 mixing ratios reached values >2.5 parts per million. Sensitivity emission studies conducted during this research suggest that local emissions of CH4 from livestock management processes are likely the primary source of the negative model bias. These results indicate that a variety, and larger quantity, of measurement data needs to be obtained and additional research is necessary to better quantify source apportioned CH4 emissions in California.

  1. GALEX AND PAN-STARRS1 DISCOVERY OF SN IIP 2010aq: THE FIRST FEW DAYS AFTER SHOCK BREAKOUT IN A RED SUPERGIANT STAR

    SciTech Connect (OSTI)

    Gezari, S.; Huber, M. E.; Grav, T.; Rest, A.; Narayan, G.; Forster, K.; Neill, J. D.; Martin, D. C.; Valenti, S.; Smartt, S. J.; Chornock, R.; Berger, E.; Soderberg, A. M.; Mattila, S.; Kankare, E.; Burgett, W. S.; Chambers, K. C.; Dombeck, T.; Heasley, J. N.; Hodapp, K. W.

    2010-09-01

    We present the early UV and optical light curve of Type IIP supernova (SN) 2010aq at z = 0.0862, and compare it to analytical models for thermal emission following SN shock breakout in a red supergiant star. SN 2010aq was discovered in joint monitoring between the Galaxy Evolution Explorer (GALEX) Time Domain Survey (TDS) in the NUV and the Pan-STARRS1 Medium Deep Survey (PS1 MDS) in the g, r, i, and z bands. The GALEX and Pan-STARRS1 observations detect the SN less than 1 day after the shock breakout, measure a diluted blackbody temperature of 31, 000 {+-} 6000 K 1 day later, and follow the rise in the UV/optical light curve over the next 2 days caused by the expansion and cooling of the SN ejecta. The high signal-to-noise ratio of the simultaneous UV and optical photometry allows us to fit for a progenitor star radius of 700 {+-} 200R {sub sun}, the size of a red supergiant star. An excess in UV emission two weeks after shock breakout compared with SNe well fitted by model atmosphere-code synthetic spectra with solar metallicity is best explained by suppressed line blanketing due to a lower metallicity progenitor star in SN 2010aq. Continued monitoring of PS1 MDS fields by the GALEX TDS will increase the sample of early UV detections of Type II SNe by an order of magnitude and probe the diversity of SN progenitor star properties.

  2. SLUDGE BATCH VARIABILITY STUDY WITH FRIT 418

    SciTech Connect (OSTI)

    Johnson, F.; Edwards, T.

    2010-11-29

    The Defense Waste Processing Facility (DWPF) initiated processing Sludge Batch 6 (SB6) in the summer of 2010. In support of processing, the Savannah River National Laboratory (SRNL) provided a recommendation to utilize Frit 418 to process SB6. This recommendation was based on assessments of the compositional projections for SB6 available at the time from the Liquid Waste Organization (LWO) and SRNL (using a model-based approach). To support qualification of SB6, SRNL executed a variability study to assess the applicability of the current durability models for SB6. The durability models were assessed over the expected Frit 418-SB6 composition range. Seventeen glasses were selected for the variability study based on the sludge projections used in the frit recommendation. Five of the glasses are based on the centroid of the compositional region, spanning a waste loading (WL) range of 32 to 40%. The remaining twelve glasses are extreme vertices (EVs) of the sludge region of interest for SB6 combined with Frit 418 and are all at 36% WL. These glasses were fabricated and characterized using chemical composition analysis, X-ray diffraction (XRD) and the Product Consistency Test (PCT). After initiating the SB6 variability study, the measured composition of the SB6 Tank 51 qualification glass produced at the SRNL Shielded Cells Facility indicated that thorium was present in the glass at an appreciable concentration (1.03 wt%), which made it a reportable element for SB6. This concentration of ThO{sub 2} resulted in a second phase of experimental studies. Five glasses were formulated that were based on the centroid of the new sludge compositional region combined with Frit 418, spanning a WL range of 32 to 40%. These glasses were fabricated and characterized using chemical composition analysis and the PCT. Based on the measured PCT response, all of the glasses (with and without thorium) were acceptable with respect to the Environmental Assessment (EA) reference glass regardless of thermal history. All of the normalized boron releases were less than 1 g/L. While all of the targeted glass compositions were predictable with respect to the Product Composition Control System (PCCS) models for durability, a small number of the measured glass compositions were located outside of the lower prediction limit indicating poorer durability than what was actually measured. These unpredictable glasses were in the same lithium metaborate (LM) preparation block during the chemical analyses, which resulted in measured compositions that were not representative of the target compositions. A review of the data did not indicate a clear cause for the problem. Re-digestion and re-measurement of three glasses from this preparation block yielded glass compositions closer to the target values and predicted PCT responses within the PCCS model uncertainty. Therefore, it is believed that the glasses were correctly fabricated and the targeted compositions are closer representations of the true compositions. Per the requirements of the DWPF Glass Product Control Program, the PCCS durability models have been shown to be applicable for the SB6/Frit 418 glass system. PCT results from the glasses fabricated as part of the variability study were shown to be predictable and/or acceptable with respect to the DWPF PCCS models. In addition, the inclusion of ThO{sub 2} was shown to have minimal impact on the acceptability and predictability of the variability study glasses.

  3. DOI-BLM-ID-T020-2012-0003-CX | Open Energy Information

    Open Energy Info (EERE)

    ID-T020-2012-0003-CX Jump to: navigation, search NEPA Document Collection for: DOI-BLM-ID-T020-2012-0003-CX CX for GeothermalExploration CX for Seismic Survey at ?? Geothermal...

  4. Finding Utility Companies Under a Given Utility ID | OpenEI Community

    Open Energy Info (EERE)

    utility company pages under a given utility id. From the Special Ask page, in the query box enter the following: Category:Utility CompaniesEiaUtilityId::15248 substituting...

  5. EIS-0471: Areva Eagle Rock Enrichment Facility in Bonneville County, ID |

    Office of Environmental Management (EM)

    Department of Energy 1: Areva Eagle Rock Enrichment Facility in Bonneville County, ID EIS-0471: Areva Eagle Rock Enrichment Facility in Bonneville County, ID May 20, 2011 delete me old download page duplicate

  6. Microsoft Word - DOE-ID-10-003.doc

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

    3 SECTION A. Project Title: Agreement in Principle, INL Oversight, Idaho DEQ SECTION B. Project Description The state of Idaho receives funding from the Department of Energy to conduct independent oversight and monitoring of DOE-ID operations. Oversight activities and monitoring actions that will be conducted by the state of Idaho include general project management and administrative actions, data management, providing information to the public, emergency response coordination, and environmental

  7. Microsoft Word - DOE-ID-INL-10-020.doc

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

    DOE-ID-INL-10-020 SECTION A. Project Title: Idaho National Laboratory (INL) Routine Maintenance Activities (Overarching) SECTION B. Project Description: The purpose of this overarching Environmental Checklist (EC) is to address activities that would meet the intent of the categorical exclusion (CX) B1.3 as described in 10 CFR 1021, Appendix B to Subpart D. These activities would consist of typical and non-typical types of actions, such as routine maintenance, minor modifications, and custodial

  8. Microsoft Word - DOE-ID-INL-11-009.doc

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

    CS Posting No.: DOE-ID-INL-11-009 SECTION A. Project Title: International Way Building (IWB) Relocation SECTION B. Project Description: The International Way Building (IWB) is currently leased and near the end of the lease term. Relocating the programs and equipment currently housed in the IWB to underutilized facilties is needed to provide efficient operation of these programs in the National and Homeland Security (N&HS) directorate. Relocating the programs and equipment would also result

  9. Microsoft Word - DOE-ID-INL-12-003.docx

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

    EC Document No.: DOE-ID-INL-12-003 SECTION A. Project Title: Auxiliary Canal Fill Project at Test Reactor Area (TRA)-670 SECTION B. Project Description: Although the ATR canal meets all design basis criteria, lessons learned following the earthquake and tsunami events at the Fukushima- Daiichi Nuclear Power Plant in March of 2011 indicate that an auxiliary water supply to the fuel storage canal with a fill connection located outside of the facility would have been valuable following the beyond

  10. Microsoft Word - DOE-ID-INL-12-006.doc

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    6 SECTION A. Project Title: International Way Office Building Lease Termination SECTION B. Project Description: The proposed activity will terminate the current lease of the International Way Office Building (IF-674, IWB) at 1690 International Way in Idaho Falls, ID on or about March 28, 2012 for cost savings and footprint reduction purposes. A facility walkthrough by BEA personnel will occur on or about March 26 to ensure the building is ready for turnover back to the owner. Approximate cost

  11. Microsoft Word - DOE-ID-INL-12-022.docx

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

    IDAHO NATIONAL LABORATORY Page 1 of 3 CX Posting No.: DOE-ID-INL-12-022 SECTION A. Project Title: Radiological Dispersal Device (RDD)/Improvised Nuclear Device (IND) Material Training Activities and Evaluations Using Radiation Emitting Sources/Material/Devices - Overarching SECTION B. Project Description This Environmental Checklist (EC) will be an overarching EC for future training as described in this EC. Work Description The purpose of this overarching EC is to plan, prepare, coordinate,

  12. Microsoft Word - DOE-ID-INL-13-006.docx

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

    3 EC Document No.: DOE-ID-INL-13-006 SECTION A. Project Title: Power Line Configuration 2013-1 SECTION B. Project Description: This project will install temporary distribution-level power lines between Materials and Fuels Complex (MFC) and Critical Infrastructure Test Range Complex (CITRC) to support research and development and testing using electric power infrastructure. Two circuits of three-phase distribution lines will be installed from Power Burst Facility (PBF)-613 to the MFC test pad.

  13. Microsoft Word - DOE-ID-INL-13-025.doc

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

    4 EC Document No.: DOE-ID-INL-13-025 SECTION A. Project Title: Willow Creek Building Pedestrian Bridge Replacement SECTION B. Project Description: The purpose and need for the proposed action is to address safety concerns related to the pedestrian bridge across Willow Creek east of the main entrance to the Willow Creek Building (IF-616). The proposed action would remove the current pedestrian bridge and associated steel railing and would remove the existing concrete approaches on either side of

  14. Microsoft Word - DOE-ID-INL-13-026.docx

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

    EC Document No.: DOE-ID-INL-13-026 SECTION A. Project Title: Relief Valve Test Stand Relocation SECTION B. Project Description: The scope of this modification is to relocate the existing relief valve test stand (RVTS) and associated high pressure air supply (skid mounted compressor and bottle rack dedicated to the RVTS) from the laydown area in Test Reactor Area (TRA)-670 to TRA-605. This modification will also include disconnecting the existing utilities from the RVTS in Advanced Test Reactor

  15. Microsoft Word - DOE-ID-INL-14-029.docx

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

    DETERMINATIONS Idaho National Laboratory Page 1 of 2 CX Posting No.: DOE-ID-INL-14-029 SECTION A. Project Title: High-Efficiency Particulate Air (HEPA) Filter Installation in the Dry Transfer Cubicle Ventilation System SECTION B. Project Description: In order to minimize the risk of contamination from the Advanced Test Reactor (ATR) Dry Transfer Cubicle (DTC), a filtration system needs to be added to the ATR DTC ventilation system in the ductwork between the installed roughing filters and DTC

  16. Microsoft Word - DOE-ID-INL-14-043.docx

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

    DETERMNATION Idaho National Laboratory Page 1 of 1 CX Posting No.: DOE-ID-INL-14-043 SECTION A. Project Title: Idaho Falls (IF)-685 (Energy Systems Laboratory [ESL]) Battery Laboratory Panel Installation Project SECTION B. Project Description: . The IF-685 Battery Laboratory (Lab) researchers require the following actions: 1. Relocate existing 75 KVA transformer on top of new 150 KVA transformer Unistrut frame. 2. Provide and install a new 150 kilovolt-amp (kVA) transformer (XFMR-42) and

  17. Microsoft Word - DOE-ID-INL-14-044.docx

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

    DETERMINATIO Idaho National Laboratory Page 1 of 2 CX Posting No.: DOE-ID-INL-14-044 SECTION A. Project Title: Materials and Fuels Complex (MFC)-752 Analytical Laboratory Water System Upgrade Project SECTION B. Project Description: The proposed project will remove and replace the current demineralized water system and backflow preventers with an air-gap system. The purpose of the project is to comply with Environmental Support and Services Technical Interpretation (ES&S-TI)-027, Idaho

  18. Microsoft Word - DOE-ID-INL-15-045.docx

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

    7 CX Posting No.: DOE-ID-INL-15-045 SECTION A. Project Title: Army Medical Department (AMEDD) Radiological Dispersal Device/Improvised Nuclear Device (RDD/IND) Material Training Activities and Evaluations SECTION B. Project Description and Purpose: Rev 5 This Environmental Checklist (EC) incorporates and supercedes EC INL-12-087 (Overarching [OA] 17) and its revisions. The training exercises described in the original EC and Revisions 1 and 3 will be repeated during August 2015, including the use

  19. Microsoft Word - DOE-ID-INL-15-053.docx

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

    53 SECTION A. Project Title: Idaho National Laboratory (INL) Engineering Demonstration Facility (IEDF) Safety Shower Installation SECTION B. Project Description and Purpose: The proposed activity would install a safety shower on the northwest second floor of the Idaho National Laboratory (INL) Engineering Demonstration Facility (IEDF, Idaho Falls [IF]-657) in Idaho Falls, ID, for the purpose of supporting research and development activities in the area. In the event of use, the shower would

  20. Microsoft Word - DOE-ID-INL-16-001.docx

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

    CX Posting No.: DOE-ID-INL-16-001 SECTION A. Project Title: Testing for Hot Fuel Examination Facility (HFEF) Gas Sample Assay and Recharge (GASR) Upgrade at Idaho National Laboratory Research Center (IRC). SECTION B. Project Description and Purpose: An upgrade of the GASR is necessary to ensure system reliability for future fuel examination campaigns. Work in IRC would include setup and completion of the out of cell testing of the redesigned GASR which is necessary prior to installation of the

  1. Microsoft Word - DOE-ID_INL-13-010.doc

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

    0 SECTION A. Project Title: North Boulevard Annex Lease Termination SECTION B. Project Description: The proposed activity would terminate the current lease of the North Boulevard Annex (IF-613) at 2095 North Boulevard in Idaho Falls, ID on or about July 31, 2013 for cost savings and footprint reduction purposes. A facility walkthrough by BEA personnel will occur prior to the lease termination to ensure the facility is ready for turnover back to the owner. Approximate cost associated with these

  2. Microsoft Word - 140602DOE-ID_OperationsSummary.docx

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

    , 2014 DOE-ID Operations Summary For the Period April 8, 2014 through May 15, 2014 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory, managed by DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC -Danielle Miller, (208) 526-5709. Advanced

  3. Effect of furnace operating conditions on alkali vaporization, batch

    Office of Scientific and Technical Information (OSTI)

    carryover, and the formation of SO2 and NO in an oxy-fuel fired container glass furnace. (Journal Article) | SciTech Connect furnace operating conditions on alkali vaporization, batch carryover, and the formation of SO2 and NO in an oxy-fuel fired container glass furnace. Citation Details In-Document Search Title: Effect of furnace operating conditions on alkali vaporization, batch carryover, and the formation of SO2 and NO in an oxy-fuel fired container glass furnace. No abstract prepared.

  4. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 7A QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Billings, A.; Click, D.

    2011-07-08

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry (Sludge Batch 7a*) be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). Sludge Batch 7a (SB7a) is composed of portions of Tanks 4, 7, and 12; the Sludge Batch 6 heel in Tank 51; and a plutonium stream from H Canyon. SRNL received the Tank 51 qualification sample (sample ID HTF-51-10-125) following sludge additions to Tank 51. This report documents: (1) The washing (addition of water to dilute the sludge supernate) and concentration (decanting of supernate) of the SB7a - Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the washed Tank 51 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a non-radioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7a related data together in a single permanent record and to discuss the overall aspects of SB7a processing.

  5. Microsoft Word - DOE-ID-INL-10-017.doc

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

    DOE-ID-INL-10-017 SECTION A. Project Title: ATR Complex Dial Room. SECTION B. Project Description: The proposed project is to construct and operate a new dial room at the Advanced Test Reactor Complex (ATR Complex) (formerly known as the Test Reactor Area [TRA]) in order to meet the U.S. Department of Energy Office of Nuclear Energy programmatic needs and to provide ongoing critical support at the Idaho National Laboratory (INL). The existing telecommunication and data systems located at the

  6. Microsoft Word - DOE-ID-INL-12-012.docx

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

    ECX Posting No.: DOE-ID-INL-12-012 SECTION A. Project Title: Film Processing Project at Test Reactor Area (TRA)-678 SECTION B. Project Description The proposed action is to install a silver recovery unit to the film processor in the film processing area at TRA-678 for the purpose of minimizing waste generation and implementing pollution prevention. The proposed film processor (Kodak M-35A) generates approximately 90 ml of developer and 140 ml of fixer effluents per 17 inch film and approximately

  7. Microsoft Word - DOE-ID-INL-12-016.doc

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

    No.: DOE-ID-INL-12-016 SECTION A. Project Title: Reverse Osmosis System Removal SECTION B. Project Description: The project will remove a reverse osmosis water treatment system (FU-HA-101) from TAN 681 room 182. The system is out-of-service, with no intent of future use. Work will involve removal of the reverse osmosis system, and associated plumbing/piping and electrical lines and conduit. The project will clear the area of obstacles and tripping hazards associated with unused/unnecessary

  8. Microsoft Word - DOE-ID-INL-12-023.doc

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

    Page 1 of 1 CX Posting No.: DOE-ID-INL-12-023 SECTION A. Project Title: Idaho Falls Power - Willow Creek Building (WCB) Conduit Installation SECTION B. Project Description: The purpose of this project is to provide the Idaho National Laboratory (INL) a communications pathway from the Willow Creek Building (WCB) northeast parking lot handhole to the handhole north of Research and Education Campus (REC)-617. INL and the City of Idaho Falls have an existing easement agreement that allows INL to

  9. Microsoft Word - DOE-ID-INL-12-024..doc

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

    PostingNo.: DOE-ID-INL-12-024 SECTION A. Project Title: Rigby Bus Lot Northwest Entrance SECTION B. Project Description: The purpose of the proposed action is to provide an additional bus entrance to the Rigby Park and Ride Bus Lot. A portion of chain link fencing (running east to west) on the northwest corner of the Rigby Park and Ride Bus Lot would be relocated to allow an opening off of the City of Rigby dirt access road so that buses may enter the Rigby Park and Ride Lot from the northwest.

  10. Microsoft Word - DOE-ID-INL-13-008.doc

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

    DOEID NEPA CX DETERMINATION Idaho National Laboratory Page 1 of 2 EC Document No.: DOE-ID-INL-13-008 SECTION A. Project Title: Materials and Fuels Complex (MFC) Diversion Dam SECTION B. Project Description: There is a flood control dam about 2000 ft south of MFC. The dam is at risk of failure during a large runoff event. This project will reinforce the flood control dam with additional earthen material and a concrete headwall around the culvert inlet. The workscope consists of 1) Removing riprap

  11. Microsoft Word - DOE-ID-INL-13-019.doc

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

    9 SECTION A. Project Title: University Boulevard Water Meter Installation SECTION B. Project Description: This project would install water meters for the purpose of measuring water use at each of four University Boulevard (UB) buildings at 535, 655, 625, and 595 University Boulevard (IF-680 (UB1), IF-681 (UB2), IF-682 (UB3), and IF-684 (UB4)) in Idaho Falls, ID during the projected time period of August and September, 2013 at an approximate cost of $20 K - $95 K depending upon whether the work

  12. Microsoft Word - DOE-ID-INL-14-015.doc

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

    5 CX Posting No.: DOE-ID-INL-14-015 SECTION A. Project Title: United States Geological Survey (USGS) Geotechnical Drilling for USGS-142 and USGS-143 SECTION B. Project Description: The U.S. Geological Survey (USGS) proposes to continuously core geotechnical boreholes USGS-142 and USGS-143 to a depth of 1,000 and 2,000 ft below land surface, respectively. Boreholes USGS-142 and USGS-143 would be constructed as monitoring wells and used to measure and collect aquifer data. Borehole USGS-142 (see

  13. Microsoft Word - DOE-ID-INL-15-009.docx

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

    CS Posting No.: DOE-ID-INL-15-009 SECTION A. Project Title: Bond Strength Laser Shock Testing SECTION B. Project Description: The proposed action is to install a laser shock system in the hot cell at the Hot Fuels Examination Facility (HFEF) at Idaho National Laboratory's (INL's) Materials and Fuels Complex (MFC). The system is needed to study bond strength of cladding on nuclear fuel associated with the Reduced Enrichment Research and Test Reactor (RERTR). The Laser Shock System delivers a high

  14. Microsoft Word - DOE-ID-INL-15-069.docx

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

    DETERMIANTION Idaho National Laboratory Page 1 of 2 CX Posting No.: DOE-ID-INL-15-069 SECTION A. Project Title: Test Reactor Area (TRA)-653 Men's Shower Remodel SECTION B. Project Description and Purpose: The TRA-653 men's shower is in need of remodeling due to the age, loose or missing ceramic tile and the difficulty in cleaning it. The proposed project will remove the shower materials including ceramic tile (approximately 385 square feet), grout, and grout base and replace with a new non-slip

  15. DOE-ID Procurement Services � the action team

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

    DOE-ID Procurement Services � the action team Passage of the American Recovery and Reinvestment Act of 2009 included billions of dollars in additional funding for energy efficiency improvements to U.S. homes and businesses. By early July, the U.S. Department of Energy was hard pressed to get that funding to the communities who needed it to reduce their power bills. That�s when DOE�s Office of Energy Efficiency asked the department�s Idaho Operations Office for support from DOE-ID�s

  16. AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT I '. CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    SOLICITATIONIMODIFICATION OF CONTRACT I '. CONTRACT ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, VA 24506 PAGE I OF 12 PAGES Albuquerque, NM 871 85-5400 I Amarillo, TX 79120 I I 90. DATED (SEE ITEM 1 1 ) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) I 10A. MODIFICATION OF CONTRACTIORDER NO. 2. AMENDMENT/MODIFICATION NO. MI67 9A. AMENDMENT OF SOLICITATION NO. I 1 DE-AC04-00AL66620 100. DATED (SEE ITEM 13) 3. EFFECTIVE DATE See Block 16C Offers must

  17. Material Safety Data Sheet MSDS ID NO.: 0137SPE012

    Alternative Fuels and Advanced Vehicles Data Center [Office of Energy Efficiency and Renewable Energy (EERE)]

    Material Safety Data Sheet MSDS ID NO.: 0137SPE012 Revision date: 05/25/2011 1. CHEMICAL PRODUCT AND COMPANY INFORMATION Product name: Speedway E85 Synonym: Speedway ED75/ED85; E-75; E75; E-85; E85; Ethanol/Gasoline Fuel Blend; Fuel Ethanol ED75/ED85 Chemical Family: Gasoline/Ethanol Formula: Mixture Manufacturer: Speedway LLC P.O. Box 1500 Enon, OH 45501 Other information: 419-421-3070 Emergency telephone number: 877-627-5463 2. COMPOSITION/INFORMATION ON INGREDIENTS E85 is a mixture of ethyl

  18. U.S. NO2 trends (2005-2013): EPA Air Quality System (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI)

    Office of Scientific and Technical Information (OSTI)

    Atmospheric Environment 110 (2015) 130-143 Contents lists available at ScienceDirect Atmospheric Environment journal homepage: www.elsevier.com/locate/atmosenv U.S. NO2 trends (2005-2013): EPA Air Quality System (AQS) data versus improved observations from the Ozone Monitoring Instrument (OMI) CrossMark Lok N. Lamsal a b *, Bryan N. Duncan b, Yasuko Yoshida c'b, Nickolay A. Krotkov b, Kenneth E. Pickering b, David G. Streets d, Zifeng Lu d a Goddard Earth Sciences Technology and Research,

  19. HIGH LEVEL WASTE SLUDGE BATCH 4 VARIABILITY STUDY

    SciTech Connect (OSTI)

    Fox, K; Tommy Edwards, T; David Peeler, D; David Best, D; Irene Reamer, I; Phyllis Workman, P

    2006-10-02

    The Defense Waste Processing Facility (DWPF) is preparing for vitrification of High Level Waste (HLW) Sludge Batch 4 (SB4) in early FY2007. To support this process, the Savannah River National Laboratory (SRNL) has provided a recommendation to utilize Frit 503 for vitrifying this sludge batch, based on the composition projection provided by the Liquid Waste Organization on June 22, 2006. Frit 418 was also recommended for possible use during the transition from SB3 to SB4. A critical step in the SB4 qualification process is to demonstrate the applicability of the durability models, which are used as part of the DWPF's process control strategy, to the glass system of interest via a variability study. A variability study is an experimentally-driven assessment of the predictability and acceptability of the quality of the vitrified waste product that is anticipated from the processing of a sludge batch. At the DWPF, the durability of the vitrified waste product is not directly measured. Instead, the durability is predicted using a set of models that relate the Product Consistency Test (PCT) response of a glass to the chemical composition of that glass. In addition, a glass sample is taken during the processing of that sludge batch, the sample is transmitted to SRNL, and the durability is measured to confirm acceptance. The objective of a variability study is to demonstrate that these models are applicable to the glass composition region anticipated during the processing of the sludge batch - in this case the Frit 503 - SB4 compositional region. The success of this demonstration allows the DWPF to confidently rely on the predictions of the durability/composition models as they are used in the control of the DWPF process.

  20. Influences of emission sources and meteorology on aerosol chemistry in a polluted urban environment: results from DISCOVER-AQ California

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

    Young, D. E.; Kim, H.; Parworth, C.; Zhou, S.; Zhang, X.; Cappa, C. D.; Seco, R.; Kim, S.; Zhang, Q.

    2015-12-15

    The San Joaquin Valley (SJV) in California experiences persistent air quality problems associated with elevated particulate matter (PM) concentrations due to anthropogenic emissions, topography, and meteorological conditions. Thus it is important to unravel the various sources and processes that affect the physico-chemical properties of PM in order to better inform pollution abatement strategies and improve parameterizations in air quality models. moreAerosol Mass Spectrometer (HR-ToF-AMS) and an Ionicon Proton Transfer Reaction Time-of-Flight Mass Spectrometer (PTR-TOF-MS) as part of the NASA Deriving Information on Surface Conditions from Column and Vertically Resolved Observations Relevant to Air Quality (DISCOVER-AQ) campaign. The average submicron aerosol (PM1) concentration was 31.0 ?g m?3 and the total mass was dominated by organic aerosols (OA, 55 %), followed by ammonium nitrate (35 %). High PM pollution events were commonly associated with elevated OA concentrations, mostly from primary sources. Organic aerosols had average atomic oxygen-to-carbon (O / C), hydrogen-to-carbon (H / C), and nitrogen-to-carbon (N / C) ratios of 0.42, 1.70, and 0.017, respectively. Six distinct sources of organic aerosol were identified from positive matrix factorization (PMF) analysis of the AMS data: hydrocarbon-like OA (HOA; 9 % of total OA; O / C = 0.09) associated with local traffic, cooking OA (COA; 28 % of total OA; O / C = 0.19) associated with food cooking activities, two biomass burning OAs (BBOA1; 13 % of total OA; O / C = 0.33 and BBOA2; 20 % of total OA; O / C = 0.60) most likely associated with residential space heating from wood combustion, and semi-volatile oxygenated OA (SV-OOA; 16 % of total OA; O / C = 0.63) and low volatility oxygenated OA (LV-OOA; 24 % of total OA; O / C = 0.90) formed via chemical reactions in the atmosphere. Large differences in aerosol chemistry at Fresno were observed between the current campaign (winter 2013) and a~previous wintertime campaign (winter 2010), most notably that PM1 concentrations were nearly three times higher in 2013 than in 2010. These variations were attributed to differences in the meteorological conditions, which influenced primary emissions and secondary aerosol formation. In particular, COA and BBOA concentrations were greater in 2013 than 2010, where colder temperatures in 2013 likely resulted in increased biomass burning activities. The influence from a nighttime formed residual layer that mixed down in the morning was found to be much more intense in 2013 than 2010, leading to sharp increases in ground-level concentrations of secondary aerosol species including nitrate, sulfate, and OOA, in the morning between 08:00 to 12:00 PST. This is an indication that nighttime chemistry might also be higher in 2013. As solar radiation was stronger in 2013 the higher nitrate and OOA concentrations in 2013 could also be partly due to greater photochemical production of secondary aerosol species. The greater solar radiation and larger range in temperature in 2013 also likely led to both SV-OOA and LV-OOA being observed in 2013 whereas only a single OOA factor was identified in 2010.less

  1. Batch drilling program cuts time, costs for Liuhua development

    SciTech Connect (OSTI)

    Gray, G.E.; Hall, K.H.; Mu, H.C.

    1996-08-12

    The efficiency of batch drilling operations and the appropriate use of technology, teamwork, and thorough planning helped cut several days off the time to drill each of 10 subsea wells for the Liuhua 11-1 development project in the South China Sea. The overall development program calls for drilling and completing 20 subsea horizontal wells. The rig-of-opportunity phase was the initial phase of this development and used a contract rig to establish the subsea wellhead array and initiate drilling of the development wells. The wellhead array was the first critical step. It was the foundation for the building block construction process used to create Liuhua`s subsea production system on the seabed. The paper discusses conductor operations, batch drilling operations, surface hole section, intermediate and production hole sections, the ten wells, application of technology, and overall results.

  2. IDS-NF Impact of Neutrino Cross Section Impact of Neutrino Cross Section

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

    IDS-NF Impact of Neutrino Cross Section Impact of Neutrino Cross Section Knowledge on Oscillation Knowledge on Oscillation Measurements Measurements M. Sorel, IFIC (CSIC and U. of Valencia) IDS-NF, RAL, Jan 16-17 2008 M. Sorel - IFIC (Valencia U. & CSIC) 2 IDS-NF Neutrino Cross Sections: At What Energies Needed? Superbeams: Solid: T2K Dashed: NovA M. Sorel - IFIC (Valencia U. & CSIC) 3 IDS-NF Neutrino Cross Sections: At What Energies Needed? Superbeams: Solid: T2K Dashed: NovA Beta

  3. Implementation of the REAL ID Act | Y-12 National Security Complex

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

    recommendations of the 911 Commission, passed the REAL ID Act in an effort to reduce fraud and deter acts of terrorism using fraudulent identification. This Act sets minimum...

  4. Underground Storage Tank Integrated Demonstration (UST-ID). Technology summary

    SciTech Connect (OSTI)

    Not Available

    1994-02-01

    The DOE complex currently has 332 underground storage tanks (USTs) that have been used to process and store radioactive and chemical mixed waste generated from weapon materials production. Very little of the over 100 million gallons of high-level and low-level radioactive liquid waste has been treated and disposed of in final form. Two waste storage tank design types are prevalent across the DOE complex: single-shell wall and double-shell wall designs. They are made of stainless steel, concrete, and concrete with carbon steel liners, and their capacities vary from 5000 gallons (19 m{sup 3}) to 10{sup 6} gallons (3785 m{sup 3}). The tanks have an overburden layer of soil ranging from a few feet to tens of feet. Responding to the need for remediation of tank waste, driven by Federal Facility Compliance Agreements (FFCAs) at all participating sites, the Underground Storage Tank Integrated Demonstration (UST-ID) Program was created by the US DOE Office of Technology Development in February 1991. Its mission is to focus the development, testing, and evaluation of remediation technologies within a system architecture to characterize, retrieve, treat to concentrate, and dispose of radioactive waste stored in USTs at DOE facilities. The ultimate goal is to provide safe and cost-effective solutions that are acceptable to the public and the regulators. The UST-ID has focused on five DOE locations: the Hanford Site, which is the host site, in Richland, Washington; the Fernald Site in Fernald, Ohio; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; the Oak Ridge Reservation in Oak Ridge, Tennessee, and the Savannah River Site in Savannah River, South Carolina.

  5. Femtosecond dark-field imaging with an X-ray free electron laser (CXIDB ID 19)

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

    Martin, A. V.

    This data was collected as part of the same experiment as the data deposited in [ID16](id-16.html). Experiment details are given in [Loh, N.D. et al.](http://dx.doi.org/10.1038/nature11222)

  6. Femtosecond dark-field imaging with an X-ray free electron laser (CXIDB ID 19)

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

    Martin, A. V.

    2012-08-25

    This data was collected as part of the same experiment as the data deposited in [ID16](id-16.html). Experiment details are given in [Loh, N.D. et al.](http://dx.doi.org/10.1038/nature11222)

  7. Uranium and Strontium Batch Sorption and Diffusion Kinetics into Mesoporous

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

    Silica | Stanford Synchrotron Radiation Lightsource Uranium and Strontium Batch Sorption and Diffusion Kinetics into Mesoporous Silica Friday, February 27, 2015 Figure 1 Figure 1. Transmission electron microscopy images of (A) washed, unreacted mesoporous silica (insert: cross section of a particle exhibiting the regular channel array structure), and mesoporous silica reacted with (B) 10 µM Sr, (C) 10 µM U at pH 4.0 with no carbonate and no calcium present, and (D) 10 µM U at pH 9.8 with

  8. Microsoft Word - FINAL Rocky Flats LBNL report Batch #1.docx

    Office of Legacy Management (LM)

    the First Batch of Rocky Flats Water Samples Submitted to LBNL John N. Christensen Report date 9/16/13 Thirteen samples were submitted by SM Stoller to Lawrence Berkeley National Laboratory for uranium isotopic and concentration analysis- 12 surface water samples from two sites (WALPOC and GS10) covering the period Sept. 2011 to April 2013, and one groundwater sample taken on 5/14/12 from well 79102 (Table 1). Uranium isotopic compositions of the samples were determined at LBNL by MC- ICPMS

  9. A short Id2 protein fragment containing the nuclear export signal forms amyloid-like fibrils

    SciTech Connect (OSTI)

    Colombo, Noemi [Fakultaet fuer Chemie und Pharmazie, Universitaet Regensburg, Universitaetsstrasse 31, 93053 Regensburg (Germany); Schroeder, Josef [Institut fuer Pathologie, Zentrales EM-Labor, Fakultaet fuer Medizin, Universitaet Regensburg, Franz-Josef-Strauss-Allee 11, 93053 Regensburg (Germany); Cabrele, Chiara [Fakultaet fuer Chemie und Pharmazie, Universitaet Regensburg, Universitaetsstrasse 31, 93053 Regensburg (Germany)]. E-mail: chiara.cabrele@chemie.uni-regensburg.de

    2006-07-21

    The negative regulator of DNA-binding/cell-differentiation Id2 is a small protein containing a central helix-loop-helix (HLH) motif and a C-terminal nuclear export signal (NES). Whereas the former is essential for Id2 dimerization and nuclear localization, the latter is responsible for the transport of Id2 from the nucleus to the cytoplasm. Whereas the isolated Id2 HLH motif is highly helical, large C-terminal Id2 fragments including the NES sequence are either unordered or aggregation-prone. To study the conformational properties of the isolated NES region, we synthesized the Id2 segment 103-124. The latter was insoluble in water and only temporarily soluble in water/alcohol mixtures, where it formed quickly precipitating {beta}-sheets. Introduction of a positively charged N-terminal tail prevented aggressive precipitation and led to aggregates consisting of long fibrils that bound thioflavin T. These results show an interesting structural aspect of the Id2 NES region, which might be of significance for both protein folding and function.

  10. Id-1 gene and gene products as therapeutic targets for treatment of breast cancer and other types of carcinoma

    DOE Patents [OSTI]

    Desprez, Pierre-Yves; Campisi, Judith

    2014-08-19

    A method for treatment of breast cancer and other types of cancer. The method comprises targeting and modulating Id-1 gene expression, if any, for the Id-1 gene, or gene products in breast or other epithelial cancers in a patient by delivering products that modulate Id-1 gene expression. When expressed, Id-1 gene is a prognostic indicator that cancer cells are invasive and metastatic.

  11. Microsoft Word - cg0915 Alum Carbothermic Tech DE-FC36-00ID139000.doc

    Office of Scientific and Technical Information (OSTI)

    2004 December 31 Cooperative Agreement No. DE-FC36-00ID13900 Aluminum Carbothermic Technology Final Technical Progress Report for the Period 2000 July through 2004 December Submitted to: U. S. Department of Energy Golden Field Office 1617 Cole Boulevard Golden, CO 80401 DOE/ID/13900 Aluminum Carbothermic Technology Submitted to: U. S. Department of Energy Cooperative Agreement Number DE-FC36-00ID13900 Submitted by: M. J. Bruno Alcoa Inc. 100 Technical Drive Alcoa Center, PA 15069-0001 Email:

  12. FLOWSHEET FOR ALUMINUM REMOVAL FROM SLUDGE BATCH 6

    SciTech Connect (OSTI)

    Pike, J; Jeffrey Gillam, J

    2008-12-17

    Samples of Tank 12 sludge slurry show a substantially larger fraction of aluminum than originally identified in sludge batch planning. The Liquid Waste Organization (LWO) plans to formulate Sludge Batch 6 (SB6) with about one half of the sludge slurry in Tank 12 and one half of the sludge slurry in Tank 4. LWO identified aluminum dissolution as a method to mitigate the effect of having about 50% more solids in High Level Waste (HLW) sludge than previously planned. Previous aluminum dissolution performed in a HLW tank in 1982 was performed at approximately 85 C for 5 days and dissolved nearly 80% of the aluminum in the sludge slurry. In 2008, LWO successfully dissolved 64% of the aluminum at approximately 60 C in 46 days with minimal tank modifications and using only slurry pumps as a heat source. This report establishes the technical basis and flowsheet for performing an aluminum removal process in Tank 51 for SB6 that incorporates the lessons learned from previous aluminum dissolution evolutions. For SB6, aluminum dissolution process temperature will be held at a minimum of 65 C for at least 24 days, but as long as practical or until as much as 80% of the aluminum is dissolved. As planned, an aluminum removal process can reduce the aluminum in SB6 from about 84,500 kg to as little as 17,900 kg with a corresponding reduction of total insoluble solids in the batch from 246,000 kg to 131,000 kg. The extent of the reduction may be limited by the time available to maintain Tank 51 at dissolution temperature. The range of dissolution in four weeks based on the known variability in dissolution kinetics can range from 44 to more than 80%. At 44% of the aluminum dissolved, the mass reduction is approximately 1/2 of the mass noted above, i.e., 33,300 kg of aluminum instead of 66,600 kg. Planning to reach 80% of the aluminum dissolved should allow a maximum of 81 days for dissolution and reduce the allowance if test data shows faster kinetics. 47,800 kg of the dissolved aluminum will be stored in Tank 8 and 21,000 kg will be stored in saltcake via evaporation. Up to 77% of the total aluminum planned for SB6 may be removed via aluminum dissolution. Storage of the aluminum-laden supernate in Tank 8 will require routine evaluation of the free hydroxide concentration in order to maintain aluminum in solution. Periodic evaluation will be established on concurrent frequency with corrosion program samples as previously established for aluminum-laden supernate from SB5 that is stored in Tank 11.

  13. YEAR","UTILITY_ID","UTILITY_NAME","PLANT_ID","PLANT_NAME","SCHEDULE","LINENO","A

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

    UTILITY_ID","UTILITY_NAME","PLANT_ID","PLANT_NAME","SCHEDULE","LINENO","AMOUNTS","DESCRIPTION" 2001,298,"Alexandria City of",6558,"DG Hunter",9,"Line 1","STEAM","Kind of Plant" 2001,298,"Alexandria City of",6558,"DG Hunter",9,"Line 2",1956,"Year Originally Constructed" 2001,298,"Alexandria City of",6558,"DG

  14. Hydrothermal liquefaction of biomass: Developments from batch to continuous process

    SciTech Connect (OSTI)

    Elliott, Douglas C.; Biller, Patrick; Ross, Andrew; Schmidt, Andrew J.; Jones, Susanne B.

    2015-02-01

    This review describes the recent results in hydrothermal liquefaction (HTL) of biomass in continuous-flow processing systems. Although much has been published about batch reactor tests of biomass HTL, there is only limited information yet available on continuous-flow tests, which can provide a more reasonable basis for process design and scale-up for commercialization. High-moisture biomass feedstocks are the most likely to be used in HTL. These materials are described and results of their processing are discussed. Engineered systems for HTL are described however they are of limited size and do not yet approach a demonstration scale of operation. With the results available process models have been developed and mass and energy balances determined. From these models process costs have been calculated and provide some optimism as to the commercial likelihood of the technology.

  15. Uranium Adsorption on Granular Activated Carbon Batch Testing

    SciTech Connect (OSTI)

    Parker, Kent E.; Golovich, Elizabeth C.; Wellman, Dawn M.

    2013-09-26

    The uranium adsorption performance of two activated carbon samples (Tusaar Lot B-64, Tusaar ER2-189A) was tested using unadjusted source water from well 299-W19-36. These batch tests support ongoing performance optimization efforts to use the best material for uranium treatment in the Hanford Site 200 West Area groundwater pump-and-treat system. A linear response of uranium loading as a function of the solution-to-solid ratio was observed for both materials. Kd values ranged from ~380,000 to >1,900,000 ml/g for the B-64 material and ~200,000 to >1,900,000 ml/g for the ER2-189A material. Uranium loading values ranged from 10.4 to 41.6 ?g/g for the two Tusaar materials.

  16. Increased CPC batch size study for Tank 42 sludge in the Defense Waste Processing Facility

    SciTech Connect (OSTI)

    Daniel, W.E.

    2000-01-06

    A series of experiments have been completed at TNX for the sludge-only REDOX adjusted flowsheet using Tank 42 sludge simulant in response to the Technical Task Request HLW/DWPT/TTR-980013 to increase CPC batch sizes. By increasing the initial SRAT batch size, a melter feed batch at greater waste solids concentration can be prepared and thus increase melter output per batch by about one canister. The increased throughput would allow DWPF to dispose of more waste in a given time period thus shortening the overall campaign.

  17. File:08-ID-c - Certificate of Public Convenience and Necessity...

    Open Energy Info (EERE)

    modified from its original state, some details may not fully reflect the modified file. Image title Lucidchart Author None Short title 08-ID-c - Certificate of Public Convenience...

  18. File:USDA-CE-Production-GIFmaps-ID.pdf | Open Energy Information

    Open Energy Info (EERE)

    ID.pdf Jump to: navigation, search File File history File usage Idaho Ethanol Plant Locations Size of this preview: 776 600 pixels. Full resolution (1,650 1,275 pixels,...

  19. DOI-BLM-ID-B010-2010-0083-CX | Open Energy Information

    Open Energy Info (EERE)

    0083-CX Jump to: navigation, search NEPA Document Collection for: DOI-BLM-ID-B010-2010-0083-CX CX for GeothermalExploration, CX for Thermal Gradient Holes for Geothermal...

  20. DOI-BLM-ID-I020-2012-0017-CX | Open Energy Information

    Open Energy Info (EERE)

    I020-2012-0017-CX Jump to: navigation, search NEPA Document Collection for: DOI-BLM-ID-I020-2012-0017-CX CX at Bingham-Caribou Geothermal Area for GeothermalExploration CX for...

  1. DOI-BLM-ID-B010-2010-??-CX | Open Energy Information

    Open Energy Info (EERE)

    ??-CX Jump to: navigation, search NEPA Document Collection for: DOI-BLM-ID-B010-2010-??-CX CX at Weiser Geothermal Area for GeothermalExploration CX at Weiser Geothermal Area for...

  2. DOI-BLM-ID-110-2009-3825-CE | Open Energy Information

    Open Energy Info (EERE)

    110-2009-3825-CE Jump to: navigation, search NEPA Document Collection for: DOI-BLM-ID-110-2009-3825-CE CX at Crane Creek Geothermal Area for GeothermalExploration Crane Creek...

  3. High-resolution x-ray diffraction microscopy of specifically labeled yeast cells (CXIDB ID 6)

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

    Nelson, Johanna

    2011-07-22

    This is the third of five exposures of the same sample at different tilts. This one is at +30 degrees tilt. Check CXI IDs 4 to 8 for the complete set.

  4. High-resolution x-ray diffraction microscopy of specifically labeled yeast cells (CXIDB ID 5)

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

    Nelson, Johanna

    2011-07-22

    This is the second of five exposures of the same sample at different tilts. This one is at +15 degrees tilt. Check CXI IDs 4 to 8 for the complete set.

  5. High-resolution x-ray diffraction microscopy of specifically labeled yeast cells (CXIDB ID 8)

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

    Nelson, Johanna

    2011-07-22

    This is the fifth of five exposures of the same sample at different tilts. This one is at -30 degrees tilt. Check CXI IDs 4 to 8 for the complete set.

  6. High-resolution x-ray diffraction microscopy of specifically labeled yeast cells (CXIDB ID 4)

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

    Nelson, Johanna

    2011-07-22

    This is the first of five exposures of the same sample at different tilts. This one is at +0 degrees tilt. Check CXI IDs 4 to 8 for the complete set.

  7. High-resolution x-ray diffraction microscopy of specifically labeled yeast cells (CXIDB ID 7)

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

    Nelson, Johanna

    2011-07-22

    This is the fourth of five exposures of the same sample at different tilts. This one is at -15 degrees tilt. Check CXI IDs 4 to 8 for the complete set.

  8. Microsoft Word - DOE-ID-12-011 RESL XRF EC.doc

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

    1 SECTION A. Project Title: DOE-ID/RESL Wavelength-Dispersive X-Ray Spectrometer for Chemistry Research & Development SECTION B. Project Description The DOE-ID Radiological & Environmental Sciences Laboratory (RESL) has a need for a complete state-of-the-art fully automated sequential wavelength-dispersive X-ray fluorescence (WD-XRF) spectrometer system. The WD-XRF spectrometer system will be primarily used for elemental analyses of soil, liquids (waters), air filters, unknown

  9. Microsoft Word - DOE-ID-INL-12-028-1.doc

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

    EC Document No.: DOE-ID-INL-12-028 SECTION A. Project Title: National Oceanic and Atmospheric Administration (NOAA) Birch Creek Canyon Wind Study SECTION B. Project Description: The National Oceanic and Atmospheric Administration (NOAA) Birch Creek Valley Wind Study would be conducted under the umbrella of the NOAA/Idaho National Laboratory (INL) Meteorological Research Partnership Memorandum of Agreement between NOAA and the Idaho Office of the U.S. Department of Energy (DOE-ID). The project

  10. How the DOE Data ID Service Works | OSTI, US Dept of Energy, Office of

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

    Scientific and Technical Information the DOE Data ID Service Works DataCite | Contact DOE Data ID Service A DOE researcher, organization, or grantee determines that important datasets exist which need to be announced in DOE's scientific and technical databases and assigned DOIs. DOE Order 241.1B instructs that bibliographic information for these datasets be submitted to OSTI. First time submitters may contact OSTI at 865-576-6784 for help in deciding what submittal method will be used,

  11. SULFATE SOLUBILITY LIMIT VERIFICATION FOR DWPF SLUDGE BATCH 7A

    SciTech Connect (OSTI)

    Billings, A.

    2011-04-19

    During processing at the Defense Waste Processing Facility (DWPF), high sulfate concentrations in the feed are a concern to DWPF as it can lead to the formation of a detrimental, sulfate-rich, molten salt phase on the surface of the glass melt pool. To avoid these issues, a sulfate concentration limit was implemented into the Product Composition Control System (PCCS). Related to SB7a frit development efforts, the Savannah River National Laboratory (SRNL) assessed the viability of using the current 0.6 wt % SO{sub 4}{sup 2-} limit set for SB6 (in glass) and the possibility of increasing the SO{sub 4}{sup 2-} solubility limit in PCCS to account for anticipated sulfur concentrations, targeted waste loadings, and inclusion of secondary streams (e.g., Actinide Removal Process (ARP)) with two recommended frits (Frit 418 and Frit 702) for SB7a processing. For a nominal SB7a blend with a 63 inch SB6 heel remaining in Tank 40 (projection SB7a-63), a 0.60 wt% SO{sub 4}{sup 2-} in glass limit was determined for waste loadings of 34 wt% up to 40 wt% with Frit 418 based on crucible melts with batched chemicals. SRNL also examined the inclusion of ARP for the same blending scenario (SB7a-63-ARP) with Frit 418 and at least a 0.6 wt% SO{sub 4}{sup 2-} level, and waste loadings of 34 wt% to 40 wt% were also acceptable. When a visible yellow and/or white sulfate salt layer was visible on the surface of any cooled glass, it was assumed to have surpassed the solubility limit of SO{sub 4}{sup 2-} for that particular composition. All of the glasses fabricated at these concentrations did not exhibit a sulfate rich salt layer on the surface of the glass melt and retained the majority of the batched SO{sub 4}{sup 2-}. At higher levels of SO{sub 4}{sup 2-} 'spiked' into the projected sludge compositions over the aforementioned interval of waste loadings, with Frit 418, low viscosity sulfur layers were observed on the surface of glass melts which confirm exceeding the solubility limit. The same sludge scenarios were also tested with Frit 702 and all glasses did not exhibit sulfur layers on the surfaces of the glass melts at spiking levels up to 0.80 wt% SO{sub 4}{sup 2-}. An ultimate SO{sub 4}{sup 2-} limit was not defined with Frit 702, but if projected SO{sub 4}{sup 2-} concentrations are expected to increase with the onset of SB7a processing, a higher limit is achievable with Frit 702 than is achievable with Frit 418. Given the anticipated concentration of SO{sub 4}{sup 2-} for SB7a, a SO{sub 4}{sup 2-} limit of 0.6 wt % SO{sub 4}{sup 2-} is recommended for processing using Frit 418. Once the confirmed SB7a composition is known and should a higher limit be needed, SRNL can re-evaluate the limit based on the actual composition and provide an updated recommendation. It has been observed that higher levels of SO{sub 4}{sup 2-} in glass can be retained with compositional changes to the frit, as was demonstrated by the glasses fabricated using Frit 702. SRNL also recommends the continuation of studies to define a more 'global' sulfate concentration limit to account for future sludge batch composition uncertainties.

  12. REPORTABLE RADIONUCLIDES IN DWPF SLUDGE BATCH 7A (MACROBATCH 8)

    SciTech Connect (OSTI)

    Reboul, S.; Diprete, D.; Click, D.; Bannochie, C.

    2011-12-20

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that the waste producer 'shall report the curie inventory of radionuclides that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115.' As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type all radionuclides that have half-lives longer than 10 years and contribute greater than 0.01 percent of the total curie inventory from the time of production through the 1100 year period from 2015 through 3115. The initial list of radionuclides to be reported is based on the design-basis glass identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report. However, it is required that the list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the 'greater than 0.01% of the curie inventory' criterion. Specification 1.6 of the WAPS, International Atomic Energy Agency Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, and U-238; and Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete list of reportable radionuclides must also include these sets of U and Pu isotopes - and the U and Pu isotopic mass distributions must be identified. The DWPF receives HLW sludge slurry from Savannah River Site (SRS) Tank 40. For Sludge Batch 7a (SB7a), the waste in Tank 40 contained a blend of the heel from Sludge Batch 6 (SB6) and the Sludge Batch 7 (SB7) material transferred to Tank 40 from Tank 51. This sludge blend is also referred to as Macrobatch 8. Laboratory analyses of a Tank 40 sludge sample were performed to quantify the concentrations of pertinent radionuclides in the SB7a waste. Subsequently, radiological decay and in-growth were calculated over the time period from 2015 to 3115. This provided a basis for characterizing the radionuclide content of SB7a over time and for identifying the 'reportable radionuclides.' Details of the characterization methodology and the analytical results are the focus of this report. This work was performed at the request of the Waste Solidification Engineering Department of Savannah River Remediation, initiated via Technical Task Request (TTR) HLW-DWPF-TTR-2010-0031. A minor revision in the reporting requirements was requested via a subsequent email communication. The work was conducted in accordance with the protocols identified in Task Technical and Quality Assurance Plan SRNL-RP-2010-01218 and Analytical Study Plan SRNL-RP-2010-01219. All of the raw data related to this scope have been recorded in laboratory notebook SRNL-NB-2011-00061. The overall goal of this task was to characterize the radionuclide content of the SB7a waste sufficiently to meet the WAPS and DWPF reporting requirements. The specific objectives were: (1) Quantify the current concentrations of all radionuclides impacting (or potentially-impacting) the total curie content between calendar years 2011 and 3115. Also quantify the current concentrations of other radionuclides specifically requested in the TTR or required by the WAPS. (2) Calculate future concentrations of decayed and in-grown radionuclides impacting the total curie content between calendar years 2015 and 3115; (3) Identify as 'reportable' all radionuclides contributing {ge} 0.01% of the total curie content from 2015 to 3115 and having half-lives {ge} 10 years.

  13. SLUDGE BATCH 7 PREPARATION TANK 4 AND 12 CHARACTERIZATION

    SciTech Connect (OSTI)

    Bannochie, C.; Click, D.; Pareizs, J.

    2010-05-21

    Samples of PUREX sludge from Tank 4 and HM sludge from Tank 12 were characterized in preparation for Sludge Batch 7 (SB7) formulation in Tank 51. SRNL analyses on Tank 4 and Tank 12 were requested in separate Technical Assistance Requests (TAR). The Tank 4 samples were pulled on January 19, 2010 following slurry operations by F-Tank Farm. The Tank 12 samples were pulled on February 9, 2010 following slurry operations by H-Tank Farm. At the Savannah River National Laboratory (SRNL), two 200 mL dip samples of Tank 4 and two 200 mL dip samples of Tank 12 were received in the SRNL Shielded Cells. Each tank's samples were composited into clean 500 mL polyethylene storage bottles and weighed. The composited Tank 4 sample was 428.27 g and the composited Tank 12 sample was 502.15 g. As expected there are distinct compositional differences between Tank 4 and Tank 12 sludges. The Tank 12 slurry is much higher in Al, Hg, Mn, and Th, and much lower in Fe, Ni, S, and U than the Tank 4 slurry. The Tank 4 sludge definitely makes the more significant contribution of S to any sludge batch blend. This S, like that observed during SB6 washing, is best monitored by looking at the total S measured by digesting the sample and analyzing by inductively coupled plasma - atomic emission spectroscopy (ICPAES). Alternatively, one can measure the soluble S by ICP-AES and adjust the value upward by approximately 15% to have a pretty good estimate of the total S in the slurry. Soluble sulfate measurements by ion chromatography (IC) will be biased considerably lower than the actual total S, the difference being due to the non-sulfate soluble S and the undissolved S. Tank 12 sludge is enriched in U-235, and hence samples transferred into SRNL from the Tank Farm will need to be placed on the reportable special nuclear material inventory and tracked for total U per SRNL procedure requirements.

  14. Sample Results from Routine Salt Batch 7 Samples

    SciTech Connect (OSTI)

    Peters, T.

    2015-05-13

    Strip Effluent Hold Tank (SEHT) and Decontaminated Salt Solution Hold Tank (DSSHT) samples from several of the microbatches of Integrated Salt Disposition Project (ISDP) Salt Batch (Macrobatch) 7B have been analyzed for 238Pu, 90Sr, 137Cs, Inductively Coupled Plasma Emission Spectroscopy (ICPES), and Ion Chromatography Anions (IC-A). The results from the current microbatch samples are similar to those from earlier samples from this and previous macrobatches. The Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU) continue to show more than adequate Pu and Sr removal, and there is a distinct positive trend in Cs removal, due to the use of the Next Generation Solvent (NGS). The Savannah River National Laboratory (SRNL) notes that historically, most measured Concentration Factor (CF) values during salt processing have been in the 12-14 range. However, recent processing gives CF values closer to 11. This observation does not indicate that the solvent performance is suffering, as the Decontamination Factor (DF) has still maintained consistently high values. Nevertheless, SRNL will continue to monitor for indications of process upsets. The bulk chemistry of the DSSHT and SEHT samples do not show any signs of unusual behavior.

  15. Methods for batch fabrication of cold cathode vacuum switch tubes

    DOE Patents [OSTI]

    Walker, Charles A. (Albuquerque, NM); Trowbridge, Frank R. (Albuquerque, NM)

    2011-05-10

    Methods are disclosed for batch fabrication of vacuum switch tubes that reduce manufacturing costs and improve tube to tube uniformity. The disclosed methods comprise creating a stacked assembly of layers containing a plurality of adjacently spaced switch tube sub-assemblies aligned and registered through common layers. The layers include trigger electrode layer, cathode layer including a metallic support/contact with graphite cathode inserts, trigger probe sub-assembly layer, ceramic (e.g. tube body) insulator layer, and metallic anode sub-assembly layer. Braze alloy layers are incorporated into the stacked assembly of layers, and can include active metal braze alloys or direct braze alloys, to eliminate costs associated with traditional metallization of the ceramic insulator layers. The entire stacked assembly is then heated to braze/join/bond the stack-up into a cohesive body, after which individual switch tubes are singulated by methods such as sawing. The inventive methods provide for simultaneously fabricating a plurality of devices as opposed to traditional methods that rely on skilled craftsman to essentially hand build individual devices.

  16. Tc-99 Adsorption on Selected Activated Carbons - Batch Testing Results

    SciTech Connect (OSTI)

    Mattigod, Shas V.; Wellman, Dawn M.; Golovich, Elizabeth C.; Cordova, Elsa A.; Smith, Ronald M.

    2010-12-01

    CH2M HILL Plateau Remediation Company (CHPRC) is currently developing a 200-West Area groundwater pump-and-treat system as the remedial action selected under the Comprehensive Environmental Response, Compensation, and Liability Act Record of Decision for Operable Unit (OU) 200-ZP-1. This report documents the results of treatability tests Pacific Northwest National Laboratory researchers conducted to quantify the ability of selected activated carbon products (or carbons) to adsorb technetium-99 (Tc-99) from 200-West Area groundwater. The Tc-99 adsorption performance of seven activated carbons (J177601 Calgon Fitrasorb 400, J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, J177612 Norit GAC830, J177613 Norit GAC830, and J177617 Nucon LW1230) were evaluated using water from well 299-W19-36. Four of the best performing carbons (J177606 Siemens AC1230AWC, J177609 Carbon Resources CR-1240-AW, J177611 General Carbon GC20X50, and J177613 Norit GAC830) were selected for batch isotherm testing. The batch isotherm tests on four of the selected carbons indicated that under lower nitrate concentration conditions (382 mg/L), Kd values ranged from 6,000 to 20,000 mL/g. In comparison. Under higher nitrate (750 mg/L) conditions, there was a measureable decrease in Tc-99 adsorption with Kd values ranging from 3,000 to 7,000 mL/g. The adsorption data fit both the Langmuir and the Freundlich equations. Supplemental tests were conducted using the two carbons that demonstrated the highest adsorption capacity to resolve the issue of the best fit isotherm. These tests indicated that Langmuir isotherms provided the best fit for Tc-99 adsorption under low nitrate concentration conditions. At the design basis concentration of Tc 0.865 g/L(14,700 pCi/L), the predicted Kd values from using Langmuir isotherm constants were 5,980 mL/g and 6,870 mL/g for for the two carbons. These Kd values did not meet the target Kd value of 9,000 mL/g. Tests conducted to ascertain the effects of changing pH showed that at pH values of 6.5 and 7.5, no significant differences existed in Tc-adsorption performance for three of the carbons, but the fourth carbon performed better at pH 7.5. When the pH was increased to 8.5, a slight decline in performance was observed for all carbons. Tests conducted to ascertain the temperature effect on Tc-99 adsorption indicated that at 21 C, 27 C, and 32 C there were no significant differences in Tc-99 adsorption for three of the carbons. The fourth carbon showed a noticeable decline in Tc-99 adsorption performance with increasing temperature. The presence of volatile organic compounds (VOCs) in the source water did not significantly affect Tc-99 adsorption on either of two carbons tested. Technetium-99 adsorption differed by less than 15% with or without VOCs present in the test water, indicating that Tc-99 adsorption would not be significantly affected if VOCs were removed from the water prior to contact with carbon.

  17. SLUDGE BATCH 6/TANK 51 SIMULANT CHEMICAL PROCESS CELL SIMULATIONS

    SciTech Connect (OSTI)

    Koopman, David; Best, David

    2010-04-28

    Qualification simulant testing was completed to determine appropriate processing conditions and assumptions for the Sludge Batch 6 (SB6) Shielded Cells demonstration of the DWPF flowsheet using the qualification sample from Tank 51 for SB6 after SRNL washing. It was found that an acid addition window of 105-139% of the DWPF acid equation (100-133% of the Koopman minimum acid equation) gave acceptable Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator (SME) results for nitrite destruction and hydrogen generation. Hydrogen generation occurred continuously after acid addition in three of the four tests. The three runs at 117%, 133%, and 150% stoichiometry (Koopman) were all still producing around 0.1 lb hydrogen/hr at DWPF scale after 42 hours of boiling in the SRAT. The 150% acid run reached 110% of the DWPF SRAT limit of 0.65 lb H{sub 2}/hr, and the 133% acid run reached 75% of the DWPF SME limit of 0.223 lb H{sub 2}/hr. Conversely, nitrous oxide generation was subdued compared to previous sludge batches, staying below 25 lb/hr in all four tests or about a fourth as much as in comparable SB4 testing. Two other processing issues were noted. First, incomplete mercury suspension impacted mercury stripping from the SRAT slurry. This led to higher SRAT product mercury concentrations than targeted (>0.45 wt% in the total solids). Associated with this issue was a general difficulty in quantifying the mass of mercury in the SRAT vessel as a function of time, especially as acid stoichiometry increased. About ten times more mercury was found after drying the 150% acid SME product to powder than was indicated by the SME product sample results. Significantly more mercury was also found in the 133% acid SME product samples than was found during the SRAT cycle sampling. It appears that mercury is segregating from the bulk slurry in the SRAT vessel, as mercury amalgam deposits for example, and is not being resuspended by the agitators. The second processing issue was significant ammonium ion formation as the acid stoichiometry was increased due to the high noble metal-high mercury feed conditions. Ammonium ion was found partitioned between the SRAT product slurry and the condensate from the lab-scale off-gas chiller downstream of the SRAT condenser. The ammonium ion was produced from nitrate ion by formic acid. Formate losses increased with increasing acid stoichiometry reaching 40% at the highest stoichiometry tested. About a third of the formate loss at higher acid stoichiometries appeared to be due to ammonia formation. The full extent of ammonia formation was not determined in these tests, since uncondensed ammonia vapor was not quantified; but total formation was bounded by the combined loss of nitrite and nitrate. Nitrate losses during ammonia formation led to nitrite-to-nitrate conversion values that were negative in three of the four tests. The negative results were an artifact of the calculation that assumes negligible SRAT nitrate losses. The sample data after acid addition indicated that some of the initial nitrite was converted to nitrate, so the amount of nitrate destroyed included nitrite converted to nitrate plus some of the added nitrate from the sludge and nitric acid. It is recommended that DWPF investigate the impact of SME product ammonium salts on melter performance (hydrogen, redox). It was recommended that the SB6 Shielded Cells qualification run be performed at 115% acid stoichiometry and allow about 35 hours of boiling for mercury stripping at the equivalent of a 5,000 lb/hr boil-up rate.

  18. MELT RATE FURNACE TESTING FOR SLUDGE BATCH 5 FRIT OPTIMIZATION

    SciTech Connect (OSTI)

    Miller, D; Fox, K; Pickenheim, B; Stone, M

    2008-10-03

    Savannah River National Laboratory (SRNL) was requested to provide the Defense Waste Processing Facility (DWPF) with a frit composition for Sludge Batch 5 (SB5) to optimize processing. A series of experiments were designed for testing in the Melt Rate Furnace (MRF). This dry fed tool can be used to quickly determine relative melt rates for a large number of candidate frit compositions and lead to a selection for further testing. Simulated Sludge Receipt and Adjustment Tank (SRAT) product was made according to the most recent SB5 sludge projections and a series of tests were conducted with frits that covered a range of boron and alkali ratios. Several frits with relatively large projected operating windows indicated melt rates that would not severely impact production. As seen with previous MRF testing, increasing the boron concentration had positive impacts on melt rate on the SB5 system. However, there appears to be maximum values for both boron and sodium above which the there is a negative effect on melt rate. Based on these data and compositional trends, Frit 418 and a specially designed frit (Frit 550) have been selected for additional melt rate testing. Frit 418 and Frit 550 will be run in the Slurry Fed Melt Rate Furnace (SMRF), which is capable of distinguishing rheological properties not detected by the MRF. Frit 418 will be used initially for SB5 processing in DWPF (given its robustness to compositional uncertainty). The Frit 418-SB5 system will provide a baseline from which potential melt rate advantages of Frit 550 can be gauged. The data from SMRF testing will be used to determine whether Frit 550 should be recommended for implementation in DWPF.

  19. Please use "gres" settings in your batch scripts

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

    Please use "gres" settings in your batch scripts Please use "gres" settings in your batch scripts September 4, 2012 by Helen He We would like to encourage you to use the generic resources ("gres") setting for various file systems that your batch jobs use. This feature is currently available on Hopper and Carver. The advantage of this setting is that your jobs won't start (thus won't fail) during a scheduled file system maintenance. The syntax for the

  20. A Better Way to ID Extreme Weather Events in Climate Models

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

    A Better Way to ID Extreme Weather Events in Climate Models A Better Way to ID Extreme Weather Events in Climate Models Berkeley Lab scientists help automate the search for hurricanes and other storms in huge datasets December 7, 2011 Dan Krotz, dakrotz@lbl.gov, +1 510-486-4019 You'd think that spotting a category 5 hurricane would never be difficult. But when the hurricane is in a global climate model that spans several decades, it becomes a fleeting wisp among mountains of data. That's a

  1. Comments on Docket ID: DOE-HQ-2011-0014 | Department of Energy

    Energy Savers [EERE]

    on Docket ID: DOE-HQ-2011-0014 Comments on Docket ID: DOE-HQ-2011-0014 This letter comprises the comments of the Pacific Gas and Electric Company (PG&E), Southern California Gas Company (SCGC), San Diego Gas and Electric (SDG&E), and Southern California Edison (SCE) in response to the U.S. Department of Energy's (DOE) Request for Information on Regulatory Burden. The signatories of this letter, collectively referred to herein as the California Investor Owned Utilities (CA IOUs) represent

  2. How to Use the DOE Data ID Service: For Data Centers and High Volume/High

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

    Frequency Submitters | OSTI, US Dept of Energy, Office of Scientific and Technical Information Data Centers and High Volume/High Frequency Submitters DataCite | Contact DOE Data ID Service Call or email your organization's Scientific and Technical Information (STI) Manager. Your STI Manager will refer you to the correct contact at OSTI. Or, if someone else has suggested you contact OSTI directly, you may do so through the DOE Data ID Service email. OSTI will work with you to discover your

  3. DOE Data ID Service Benefits | OSTI, US Dept of Energy, Office of

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

    Scientific and Technical Information Benefits DataCite | Contact DOE Data ID Service When you submit metadata to OSTI about a dataset, you are basically "announcing" that it exists and you are describing it. That's why you will see the name of the basic submittal tool for data referred to as "Announcement Notice 241.6." Note that the DOE Data ID Service does not accept the dataset itself; only the metadata is submitted. The metadata loads into the OSTI processing system

  4. Tank 40 Final Sludge Batch 8 Chemical Characterization Results

    SciTech Connect (OSTI)

    Bannochie, Christopher J.

    2013-09-19

    A sample of Sludge Batch 8 (SB8) was pulled from Tank 40 in order to obtain radionuclide inventory analyses necessary for compliance with the Waste Acceptance Product Specifications (WAPS). The SB8 WAPS sample was also analyzed for chemical composition, including noble metals, and fissile constituents, and these results are reported here. These analyses along with the WAPS radionuclide analyses will help define the composition of the sludge in Tank 40 that is currently being fed to the Defense Waste Processing Facility (DWPF) as SB8. At SRNL, the 3-L Tank 40 SB8 sample was transferred from the shipping container into a 4-L high density polyethylene bottle and solids were allowed to settle. Supernate was then siphoned off and circulated through the shipping container to complete the transfer of the sample. Following thorough mixing of the 3-L sample, a 553 g sub-sample was removed. This sub-sample was then utilized for all subsequent slurry sample preparations. Eight separate aliquots of the slurry were digested, four with HNO{sub 3}/HCl (aqua regia) in sealed Teflon(r) vessels and four with NaOH/Na{sub 2}O{sub 2} (alkali or peroxide fusion) using Zr crucibles. Two Analytical Reference Glass - 1 (ARG-1) standards were digested along with a blank for each preparation. Each aqua regia digestion and blank was diluted to 1:100 mL with deionized water and submitted to Analytical Development (AD) for inductively coupled plasma - atomic emission spectroscopy (ICP-AES) analysis, inductively coupled plasma - mass spectrometry (ICP-MS) analysis, atomic absorption spectroscopy (AA) for As and Se, and cold vapor atomic absorption spectroscopy (CV-AA) for Hg. Equivalent dilutions of the alkali fusion digestions and blank were submitted to AD for ICP-AES analysis. Tank 40 SB8 supernate was collected from a mixed slurry sample in the SRNL Shielded Cells and submitted to AD for ICP-AES, ion chromatography (IC), total base/free OH-/other base, total inorganic carbon/total organic carbon (TIC/TOC) analyses. Weighted dilutions of slurry were submitted for IC, TIC/TOC, and total base/free OH-/other base analyses. Activities for U-233, U-235, and Pu-239 were determined from the ICP-MS data for the aqua regia digestions of the Tank 40 WAPS slurry using the specific activity of each isotope. The Pu-241 value was determined from a Pu-238/-241 method developed by SRNL AD and previously described.

  5. Uranium Adsorption on Ion-Exchange Resins - Batch Testing

    SciTech Connect (OSTI)

    Mattigod, Shas V.; Golovich, Elizabeth C.; Wellman, Dawn M.; Cordova, Elsa A.; Smith, Ronald M.

    2010-12-01

    The uranium adsorption performance of five resins (Dowex 1, Dowex 21K 16-30 [fresh], Dowex 21K 16-30 [regenerated], Purofine PFA600/4740, and ResinTech SIR-1200) were tested using unspiked, nitrate-spiked, and nitrate-spiked/pH adjusted source water from well 299-W19-36. These batch tests were conducted in support of a resin selection process in which the best resin to use for uranium treatment in the 200-West Area groundwater pump-and-treat system will be identified. The results from these tests are as follows: The data from the high-nitrate (1331 mg/L) tests indicated that Dowex 1, Dowex 21K 16-30 (fresh), Purofine PFA600/4740, and ResinTech SIR-1200 all adsorbed uranium similarly well with Kd values ranging from ~15,000 to 95,000 ml/g. All four resins would be considered suitable for use in the treatment system based on uranium adsorption characteristics. Lowering the pH of the high nitrate test conditions from 8.2 to 7.5 did not significantly change the uranium adsorption isotherms for the four tested resins. The Kd values for these four resins under high nitrate (1338 mg/L), lower pH (7.5) ranged from ~15,000 to 80,000 ml/g. Higher nitrate concentrations greatly reduced the uranium adsorption on all four resins. Tests conducted with unspiked (no amendments; nitrate at 337 mg/L and pH at 8.2) source water yielded Kd values for Dowex 1, Dowex 21K 16-30 (fresh), Purofine PFA600/4740, and ResinTech SIR-1200 resins ranging from ~800,000 to >3,000,000 ml/g. These values are about two orders of magnitude higher than the Kd values noted from tests conducted using amended source water. Compared to the fresh resin, the regenerated Dowex 21K 16-30 resin exhibited significantly lower uranium-adsorption performance under all test conditions. The calculated Kd values for the regenerated resin were typically an order of magnitude lower than the values calculated for the fresh resin. Additional testing using laboratory columns is recommended to better resolve differences between the adsorption abilities of the resins and to develop estimates of uranium loading on the resins. By determining the quantity of uranium that each resin can adsorb and the time required to reach various levels of loading, resin lifetime in the treatment system can be estimated.

  6. Progress in Multi-Batch Slip Stacking in the Fermilab Main Injector and Future Plans

    SciTech Connect (OSTI)

    Seiya, K.; Chase, B.; Dey, J.; Joireman, P.; Kourbanis, I.; Reid, J.; /Fermilab

    2008-04-01

    The multi-batch slip stacking has been used for operations since January, 2008 and effectively increased proton intensity to the NuMI target by 50% in a Main Injector (MI) cycle. The MI accepts 11 batches at injection energy from the Booster, and sends two batches to antiproton production and nine to the NuMI beam line. The total beam power in a cycle was increased to 340 kW on average. We have been doing beam studies in order to increase the beam power to 400 kW and to control the beam loss. We will also discuss 12 batch slip stacking scheme which is going to be used for future neutrino experiments.

  7. Site Selection for Concrete Batch Plant to Support Plutonium Disposition Facilities at the Savannah River Site

    SciTech Connect (OSTI)

    Wike, L.D.

    2001-06-15

    WSRC conducted a site selection study to identify, assess, and rank candidate sites for an onsite concrete batch plant at the Savannah River Site in the vicinity of F-Area.

  8. Single mimivirus particles intercepted and imaged with an X-ray laser (CXIDB ID 2)

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

    Seibert, M. Marvin; Ekeberg, Tomas

    2011-02-02

    These are the files used to reconstruct the images in the paper "Single Mimivirus particles intercepted and imaged with an X-ray laser". Besides the diffracted intensities, the Hawk configuration files used for the reconstructions are also provided. The files from CXIDB ID 2 are the pattern and configuration files for the pattern showed in Figure 2b in the paper.

  9. Single mimivirus particles intercepted and imaged with an X-ray laser (CXIDB ID 1)

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

    Seibert, M. Marvin; Ekeberg, Tomas; Maia, Filipe R.N.C.

    2011-02-02

    These are the files used to reconstruct the images in the paper "Single Mimivirus particles intercepted and imaged with an X-ray laser". Besides the diffracted intensities, the Hawk configuration files used for the reconstructions are also provided. The files from CXIDB ID 1 are the pattern and configuration files for the pattern showed in Figure 2a in the paper.

  10. Last Revision Date: 8/16/2010 Last Merged Filing ID:

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

    Revision Date: 8/16/2010 Last Merged Filing ID: Tariffs, Rate Schedules, and Other Tariff Documents Southwestern Power Administration Tariffs, Rate Schedules, and Other Tariff Documents Document Generated On: 10/1/2010 Contents TABLE OF CONTENTS ....................................................................................................................................1 PREAMBLE: AUTHORITIES AND OBLIGATIONS

  11. Single mimivirus particles intercepted and imaged with an X-ray laser (CXIDB ID 1)

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

    Seibert, M. Marvin; Ekeberg, Tomas; Maia, Filipe R.N.C.

    These are the files used to reconstruct the images in the paper "Single Mimivirus particles intercepted and imaged with an X-ray laser". Besides the diffracted intensities, the Hawk configuration files used for the reconstructions are also provided. The files from CXIDB ID 1 are the pattern and configuration files for the pattern showed in Figure 2a in the paper.

  12. Production of branched-chain alcohols by recombinant Ralstonia eutropha in fed-batch cultivation

    SciTech Connect (OSTI)

    Fei, Q; Brigham, CJ; Lu, JN; Fu, RZ; Sinskey, AJ

    2013-09-01

    Branched-chain alcohols are considered promising green energy sources due to their compatibility with existing infrastructure and their high energy density. We utilized a strain of Ralstonia eutropha capable of producing branched-chain alcohols and examined its production in flask cultures. In order to increase isobutanol and 3-methyl-1-butanol (isoamyl alcohol) productivity in the engineered strain, batch, fed-batch, and two-stage fed-batch cultures were carried out in this work. The effects of nitrogen source concentration on branched-chain alcohol production were investigated under four different initial concentrations in fermenters. A maximum 380 g m(-3) of branched-chain alcohol production was observed with 2 kg m(-3) initial NH4Cl concentration in batch cultures. A pH-stat control strategy was utilized to investigate the optimum carbon source amount fed during fed-batch cultures for higher cell density. In cultures of R. eutropha strains that did not produce polyhydroxyalkanoate or branched-chain alcohols, a maximum cell dry weight of 36 kg m(-3) was observed using a fed-batch strategy, when 10 kg m(-3) carbon source was fed into culture medium. Finally, a total branched-chain alcohol titer of 790 g m(-3), the highest branched-chain alcohol yield of 0.03 g g(-1), and the maximum branched-chain alcohol productivity of 8.23 g m(-3) h(-1) were obtained from the engineered strain Re2410/pJL26 in a two-stage fed-batch culture system with pH-stat control. Isobutanol made up over 95% (mass fraction) of the total branched-chain alcohols titer produced in this study. (C) 2013 Published by Elsevier Ltd.

  13. DOE Data ID Service Background | OSTI, US Dept of Energy, Office of

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

    Scientific and Technical Information Background DataCite | Contact DOE Data ID Service In 2011, the DOE Office of Scientific and Technical Information (OSTI) joined DataCite to facilitate citing, accessing, and reusing publicly available scientific research datasets produced by DOE-funded researchers. DataCite is an international organization that supports data visibility, ease of data citation in scholarly publications, data preservation and future re-use, and data access and

  14. Meeting Summary Docket ID No. EERE-2014-BT-STD-0036-0023

    Office of Environmental Management (EM)

    Meeting Summary Docket ID No. EERE-2014-BT-STD-0036-0023 RIN 1904-AD35 Tuesday, December 22, 2015 On December 15, 2015, representatives of the Hearth Patio & Barbecue Association (HPBA) met with Department of Energy (DOE) officials to discuss issues related to DOE's proposed energy conservation standard for "hearth products" published at 80 Fed. Reg. 7082 (February 9, 2015). The meeting was attended by the following individuals: Jack Goldman, President & CEO of HPBA Ryan

  15. Microsoft PowerPoint - ID 876 TourBooklet_revb_Geology [Compatibility Mode]

    Office of Environmental Management (EM)

    Energy, National Nuclear Security Administration Nevada Field Office Bob Andrews Navarro-Intera December 10, 2014 Nevada National Security Site Underground Test Area (UGTA) Tour Page 2 Page 2Title ID 876 Tour Booklet 12/10/2014 - Page 2 Log No. 2014-xxx Nevada National Security Site (NNSS) * NNSS has many diverse roles to support the U.S. nuclear weapons stockpile stewardship missions and also supports other U.S. Department of Energy (DOE), Department of Defense, and Department of Homeland

  16. Microsoft Word - DOE-ID-13-044 Idaho EC B3-6.doc

    Office of Environmental Management (EM)

    Page 1 of 1 CX Posting No.: DOE-ID-13-044 SECTION A. Project Title: Off-gas Treatment: Evaluation of Nano-structured Sorbents for Selective Removal of Contaminants - University of Idaho SECTION B. Project Description The University of Idaho proposes to evaluate nanostructured sorbent materials for their effectiveness in removing and immobilizing contaminants for the off-gas treatment from the used nuclear fuel recycling operations. Specific objectives of the project are: 1. To synthesize and

  17. Results Of Initial Analyses Of The Salt (Macro) Batch 9 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T.

    2015-10-08

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics. Further results on the chemistry and other tests will be issued in the future.

  18. Results of initial analyses of the salt (macro) batch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-10-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Interim Salt Disposition Project (ISDP) Salt (Macro) Batch 9 for processing through the Actinide Removal Process (ARP) and the Modular Caustic-Side Solvent Extraction Unit (MCU). This document reports the initial results of the analyses of samples of Tank 21H. Analysis of the Tank 21H Salt (Macro) Batch 9 composite sample indicates that the material does not display any unusual characteristics or observations, such as floating solids, the presence of large amount of solids, or unusual colors. Further results on the chemistry and other tests will be issued in the future.

  19. MELTING OF GLASS BATCH: MODEL FOR MULTIPLE OVERLAPPING GAS-EVOLVING

    Office of Scientific and Technical Information (OSTI)

    REACTIONS (Journal Article) | SciTech Connect MELTING OF GLASS BATCH: MODEL FOR MULTIPLE OVERLAPPING GAS-EVOLVING REACTIONS Citation Details In-Document Search Title: MELTING OF GLASS BATCH: MODEL FOR MULTIPLE OVERLAPPING GAS-EVOLVING REACTIONS In this study, we present a model for the kinetics of multiple overlapping reactions. Mathematical representation of the kinetics of gas-evolving reactions is crucial for the modeling of the feed-to-glass conversion in a waste-glass melter. The model

  20. Batch crystallization of rhodopsin for structural dynamics using an X-ray free-electron laser

    SciTech Connect (OSTI)

    Wu, Wenting; Nogly, Przemyslaw; Rheinberger, Jan; Kick, Leonhard M.; Gati, Cornelius; Nelson, Garrett; Deupi, Xavier; Standfuss, Jrg; Schertler, Gebhard; Panneels, Valrie

    2015-06-27

    A new batch preparation method is presented for high-density micrometre-sized crystals of the G protein-coupled receptor rhodopsin for use in time-resolved serial femtosecond crystallography at an X-ray free-electron laser using a liquid jet. Rhodopsin is a membrane protein from the G protein-coupled receptor family. Together with its ligand retinal, it forms the visual pigment responsible for night vision. In order to perform ultrafast dynamics studies, a time-resolved serial femtosecond crystallography method is required owing to the nonreversible activation of rhodopsin. In such an approach, microcrystals in suspension are delivered into the X-ray pulses of an X-ray free-electron laser (XFEL) after a precise photoactivation delay. Here, a millilitre batch production of high-density microcrystals was developed by four methodical conversion steps starting from known vapour-diffusion crystallization protocols: (i) screening the low-salt crystallization conditions preferred for serial crystallography by vapour diffusion, (ii) optimization of batch crystallization, (iii) testing the crystal size and quality using second-harmonic generation (SHG) imaging and X-ray powder diffraction and (iv) production of millilitres of rhodopsin crystal suspension in batches for serial crystallography tests; these crystals diffracted at an XFEL at the Linac Coherent Light Source using a liquid-jet setup.

  1. AMEN DMENT OF SOLICITATION/MODIFICATION OF CONTRACT r* CONTRACT ID CODE

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

    AMEN DMENT OF SOLICITATION/MODIFICATION OF CONTRACT r* CONTRACT ID CODE I PAGE OF PAGES 1 I 1 2. AMENDMENT/MODIFICATION NO. 3. EFFECTIVE DATE 4. REQUISITION/PURCHASE REQ. NO. ,5. PROJECT NO. (If applicable) 0234 10/08/2013 6.1SSUED BY CODE 00603 7. ADMINISTERED BY (If other than Item 6) CODE I00603 Office of River Protection u.s. Department of Energy Office of River Protection P.O. Box 450 Richland WA 99352 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state and ZIP Code) ASHINGTON

  2. AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT 1.CONTRACT ID CODE PAGE OF PAGES

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

    CONTRACT ID CODE PAGE OF PAGES T 1 1 13 2 AMENDIMENT/MODIFICATION NO 3. EFFECTIVE DATE 4 -REGUISITION/PURCHASE RED. NO 5. PROJECT NO. (If epplicable) 032 04/14/2011 11EM002244 6 ISSUED BY CODE 00603 7 ADMINISTERED BY (Iftherthan temrt6) CODE J00603 Office of River Protection Office of River Protection U.S. Department of Energy U.S. Department of Energy Office of River Protection office of River Protection P.O. Box 450 P.O. Box 450 Richland WA 99352 Richland WA 99352 8 NAME AND ADDRESS OF

  3. AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT \1. CONTRACT ID CODE

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

    ID CODE I PAGE OF PAGES 1 I 2 2. AMENDMENTIMODIFICATION NO. 3. EFFECTIVE DATE 4. REOUISITIONIPURCHASE REO. NO. r' PROJECT NO. (If applicable) 356 See Block 16C 12SC001876 Item 7 6. ISSUED BY CODE 00518 7. ADMINISTERED BY (If other than Item 6) CODE \00518 Oak Ridge Oak Ridge U.S. Department of Energy U.S. Department of Energy P.O. Box 2001 P.O. Box 2001 Oak Ridge TN 37831 Oak Ridge TN 37831 8. NAME AND ADDRESS OF CONTRACTOR (No., stroot, county, State and ZIP Code) J1 SA. AMENDMENT OF

  4. AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT 1. CONTRACT ID CODE P AE

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

    OF CONTRACT 1. CONTRACT ID CODE P AE 2. AMEN DMENT/MODIF ICATION NO. 3. EFFECTIVE DATE 4. REQUISITION/PURCHASE RED. NO. 5. PROJECT NO. (If applicable) 073 See Block 16C 12EM002951/12EM003004 6. ISSUED BY CODE 100603 7. ADMINISTERED BY (If other than Item 6) CODE 100603 Office of River Protection Office of River Protection U.S. Department of Energy U.S. Department of Energy Office of River Protection Office of River Protection P.O. Box 450 P.O. Box 450 Richland WA 99352 Richland WA 99352 8. NAME

  5. AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT I CONTRACT ID CODE PAGE OF PAGES

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

    I CONTRACT ID CODE PAGE OF PAGES 1 14 2. AMENDMENT/MODIFICATION NO. 3 EFFECTIVE DATE 4. REQUISITION/PURCHASE RED. NO 5. PRtOJECT NO. (if pplicable) 186 See Block 16CL 6. ISSUED BY CODE j 0603 7. ADMINISTERED BY (If other than Item 6) CODE 00603 office of River Protection Office of River Protection U.S. Department of Energy U.S. Department of Energy office of River Protection office of River Protection P.O. Box 450 P.O. Box 450 Richland WA 99352 MS: H6-60 Richland WA 99352 6. NAME AND ADDRESS OF

  6. AMENDMENT OF SOUCITATIONIMODIFICATION OF CONTRACT 1. CONTRACT ID CODE PAGE OF PAGES

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

    1. CONTRACT ID CODE PAGE OF PAGES II 11 9 2. AMEN DMENTIMODIFICATION NO. 3. EFFECTIVE DATE 4. REOUISITIONIPURCHASE REQ. NO. 5. PROJECT NO. (If elpicable) 169 See Block 16C 12EM0020631 6. ISSUED BY CODE 00603 7. ADMINISTERED BY (If otherthan Item 6) CODE 100603 Office of River Protection Office of River Protection U.S. Department of Energy U.S. Department of Energy Office of River Protection Office of River Protection P.O. Box 450 P.O. Box 450 Richland WA 99352 MS: H6-60

  7. Here�s What�s Going on with DOE-ID

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

    Here�s What�s Going on with DOE-ID As you know, we initiated a survey under �Voice of the People� last month, in order to get your input on how we can make this website more useful to you. In response to your feedback, one thing we did is develop a monthly article that attempts to capsulize the activities and opportunities for public input, all in one place. This is the first of those articles. Public Involvement Opportunities You have until close of business on June 21 to provide input

  8. How to Use the DOE Data ID Service: For Individual Lab Researchers | OSTI,

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

    US Dept of Energy, Office of Scientific and Technical Information Individual Lab Researchers DataCite | Contact DOE Data ID Service Call or email your organization's Scientific and Technical Information (STI) Manager. Explain your need to submit a dataset to support a publication and/or to receive a DOI. Ask if your lab has been assigned a unique DOI prefix. The answer should be "yes." If it is not, the STI Manager will need to contact OSTI to obtain a prefix and then get back to

  9. Report Period: EIA ID NUMBER: Appendix A: Mailing Address: Appendix B:

    Gasoline and Diesel Fuel Update (EIA)

    Report Period: EIA ID NUMBER: Appendix A: Mailing Address: Appendix B: Zip Code - Secure File Transfer option available at: - - - - Email form to: OOG.SURVEYS@eia.doe.gov Fax form to: (202) 586-9772 Email address: Oil & Gas Survey U.S. Department of Energy Ben Franklin Station PO Box 279 Washington, DC 20044-0279 Questions? Call toll free: 1-800-638-8812 1. Total Acquisitions (Enter the total volume of foreign crude oil acquired during the report month for importation into the United States.

  10. Report Period: EIA ID NUMBER: Instructions: (e.g., Street Address, Bldg, Floor, Suite)

    Gasoline and Diesel Fuel Update (EIA)

    Report Period: EIA ID NUMBER: Instructions: (e.g., Street Address, Bldg, Floor, Suite) Secure File Transfer option available at: (e.g., PO Box, RR) Electronic Transmission: The PC Electronic Data Reporting Option (PEDRO) is available. Zip Code: - If interested in software, call (202) 586-9659. Email form to: Fax form to: (202) 586-9772 - - Mail form to: Oil & Gas Survey - - U.S. Department of Energy Ben Franklin Station PO Box 279 Washington, DC 20044-0279 Questions? Call toll free:

  11. 11. CONTRACT ID CODE PAGE OF PAGES I AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT

    National Nuclear Security Administration (NNSA)

    11. CONTRACT ID CODE PAGE OF PAGES I AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT 1 I 2. AMENDMENTIMODIFICATION NO. 258 6. ISSUED BY CODE 3. EFFECTIVE DATE See Block 16C 05008 4. REQUISITION/PURCHASE REQ. NO. 7. ADMINISTERED BY (If other than Item 6) 15. PROJECT NO. (If applicable) CODE 1 0 5 0 0 8 NNSA/Oakridge Site Office NNSA/Oakridge Site Office U.S. Department of Energy U. S. Department of Energy NNSA/Y-12 Site Office NNSA/Y-12 Site Office P.O. Box 2050 P.O. Box 2050 Building 9704-2

  12. AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT 11. CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    -------------------------------------------------------- AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT 11. CONTRACT ID CODE I PAGE OF PAGES 1 I 2 2. AMENDMENT/MODIFICATION NO. 3. EFFECTIVE DATE 4. REQUISITION/PURCHASE REQ. NO. 15. PROJECT NO. (If applicable) 0246 See Block 16C 6. ISSUED BY CODE 05003 7. ADMINISTERED BY (If other than Item 6) CODE 105003 NNSA/Los Alamos Site Office NNSA/Los Alamos Site Office U.S. Department of Energy U.S. Department of Energy NNSA/Los Alamos Site Office Los

  13. AMENDMENT OF SOLICITATIONIMODIFICATlON OF CONTRACT ( I- CONTRACT ID CODE PAGE I OF 2

    National Nuclear Security Administration (NNSA)

    ( I- CONTRACT ID CODE PAGE I OF 2 PAGES I . . Babcock & Wilcox Technical Services Pantex, LLC PO Box 30020 Amarillo, TX 79120 2. AMENDMENTIMODIFICATION NO. M I 51 Albuquerque, NM 87185-5400 I Amarillo, TX 79120 90. DATED (SEE ITEM 11) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) 3. EFFECTIVE DATE See Block 16C 9A. AMENDMENT OF SOLICITATION NO. extended. 6 . ISSUED BY CODE U.S. Department of Energy National Nuclear Security Administration Service Center Property

  14. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT ( I. ID CODE

    National Nuclear Security Administration (NNSA)

    ( I. ID CODE / DE-ACO4-OOAL6662O ' 10s. DATED (SEE ITEM 13) PAGE I OF 2 PAGES Babcock & W ~ ~ C O X Technical Services Pantex, LLC 800 Main Street Lynchburg, VA 24505 9B. DATED (SEE ITEM 11) 10A. MODIFICATION OF CONTRACTIORDER NO. Offers must acknowledge receipt of this amendment prior to the hour and date specified in the solicitation as amended, by one of the following methods: (a) By completing Items 8 and 15, and returning - copies of the amendment; (b) By acknowledging receipt of this

  15. AMENDMENT OF SOlLICITATION/MODIFICATlON OF CONTRACT I I. CONTRACr ID CODE

    National Nuclear Security Administration (NNSA)

    SOlLICITATION/MODIFICATlON OF CONTRACT I I. CONTRACr ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, VA 24506 PAGE I OF 2 PAGES Albuquerque, NM 871 85-5400 I Amarillo, TX 79120 9B. DATED (SEE ITEM 1 1 ) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) DE-AC04-00AL66620 I I IOB. DATED (SEE ITEM 13) 2. AMENDMENTIMODIFICATION NO. MI41 9A. AMENDMENT OF Sol-ICITATION NO. CODE I ~ H L I L I I Y L U U ~ I I - 11. THlS ITEM ONLY APPLIES TO AMENDMENTS OF

  16. Header Sheet Doc ID Z OAK RIDGE NATIONAL LABORATORY M. E. Murray

    Office of Legacy Management (LM)

    Dames & Moore Header Sheet Doc ID Z OAK RIDGE NATIONAL LABORATORY M. E. Murray MANAGED BY LOCKHEED MARTIN rNERGY RESEARCH CORPORATION PHONE: (423) 574-5838 FOR THE U.S. DEPARTMENT OF ENERGY FAX: (423) POST OFFICE Box 2 INTERNET: r'0 March 31, 1997 Mr. Andrew Meloy DuPont Environmental Remediation Services DuPont Chambers Works Route 130, Anti-Knocks Building G Deepwater, New Jersey 08023 Dear Mr. Meloy: Radiological Sampling Requirements for the B Ditch Remediation Project, DuPont Chamber

  17. An interactive version of PropID for the aerodynamic design of horizontal axis wind turbines

    SciTech Connect (OSTI)

    Ninham, C.P.; Selig, M.S.

    1997-12-31

    The original PROP code developed by AeroVironment, Inc. and its various versions have been in use for wind turbine performance predictions for over ten years. Due to its simplicity, rapid execution times and relatively accurate predictions, it has become an industry standard in the US. The Europeans have similar blade-element/momentum methods in use for design. Over the years, PROP has continued to be improved (in its accuracy and capability), e.g., PROPSH, PROPPC, PROP93, and PropID. The latter version incorporates a unique inverse design capability that allows the user to specify the desired aerodynamic characteristics from which the corresponding blade geometry is determined. Through this approach, tedious efforts related to manually adjusting the chord, twist, pitch and rpm to achieve desired aerodynamic/performance characteristics can be avoided, thereby making it possible to perform more extensive trade studies in an effort to optimize performance. Past versions of PropID did not have supporting graphics software. The more current version to be discussed includes a Matlab-based graphical user interface (GUI) and additional features that will be discussed in this paper.

  18. Characterization Of The As-Received Sludge Batch 9 Qualification Sample (Htf-51-15-81)

    SciTech Connect (OSTI)

    Pareizs, J.

    2015-09-30

    Savannah River National Laboratory (SRNL) personnel have been requested to qualify the next sludge batch (Sludge Batch 9 SB9) for processing at the Defense Waste Processing Facility (DWPF). To accomplish this task, Savannah River Remediation (SRR) has sent SRNL a 3-L slurried sample of Tank 51H (HTF-51-15-81) to be characterized, washed, and then used in a lab-scale demonstration of the DWPF flowsheet (potentially after combining with Tank 40H sludge). This report documents the first steps of the qualification process characterization of the as-received Tank 51H qualification sample. These results will be used to support a reprojection of SB9 by SRR from which final Tank 51H washing, frit development, and Chemical Processing Cell (CPC) activities will be based.

  19. SRS SLUDGE BATCH QUALIFICATION AND PROCESSING; HISTORICAL PERSPECTIVE AND LESSONS LEARNED

    SciTech Connect (OSTI)

    Cercy, M.; Peeler, D.; Stone, M.

    2013-09-25

    This report provides a historical overview and lessons learned associated with the SRS sludge batch (SB) qualification and processing programs. The report covers the framework of the requirements for waste form acceptance, the DWPF Glass Product Control Program (GPCP), waste feed acceptance, examples of how the program complies with the specifications, an overview of the Startup Program, and a summary of continuous improvements and lessons learned. The report includes a bibliography of previous reports and briefings on the topic.

  20. Removal of aqueous rinsable flux residues in a batch spray dishwater

    SciTech Connect (OSTI)

    Slanina, J.T.

    1992-02-01

    An alkaline detergent solution used in an industrial dishwasher was evaluated to remove aqueous rinsable flux residues on printed wiring boards (PWBs) after hot air solder leveling and hot oil solder dip and leveling. The dishwasher, a batch cleaning process, was compared to an existing conveyorized aqueous cleaning process. The aqueous soluble flux residues from both soldering processes were removed with a solution of a mild alkaline detergent dissolved in hot deionized (DI) water.

  1. MODELING CST ION EXCHANGE FOR CESIUM REMOVAL FROM SCIX BATCHES 1 - 4

    SciTech Connect (OSTI)

    Smith, F.

    2011-04-25

    The objective of this work is, through modeling, to predict the performance of Crystalline Silicotitinate (CST) for the removal of cesium from Small Column Ion Exchange (SCIX) Batches 1-4 (as proposed in Revision 16 of the Liquid Waste System Plan). The scope of this task is specified in Technical Task Request (TTR) 'SCIX Feed Modeling', HLE-TTR-2011-003, which specified using the Zheng, Anthony, Miller (ZAM) code to predict CST isotherms for six given SCIX feed compositions and the VErsatile Reaction and SEparation simulator for Liquid Chromatography (VERSE-LC) code to predict ion-exchange column behavior. The six SCIX feed compositions provided in the TTR represent SCIX Batches 1-4 and Batches 1 and 2 without caustic addition. The study also investigated the sensitivity in column performance to: (1) Flow rates of 5, 10, and 20 gpm with 10 gpm as the nominal flow; and (2) Temperatures of 25, 35, and 45 C with 35 C as the nominal temperature. The isotherms and column predictions presented in this report reflect the expected performance of engineered CST IE-911. This form of CST was used in experiments conducted at the Savannah River National Laboratory (SRNL) that formed the basis for estimating model parameters (Hamm et al., 2002). As has been done previously, the engineered resin capacity is estimated to be 68% of the capacity of particulate CST without binder.

  2. Analysis Of DWPF Sludge Batch 7a (Macrobatch 8) Pour Stream Samples

    SciTech Connect (OSTI)

    Johnson, F. C.; Pareizs, J. M.

    2012-10-24

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7a (SB7a), also referred to as Macrobatch 8 (MB8), in June 2011. SB7a is a blend of the heel of Tank 40 from Sludge Batch 6 (SB6) and the SB7a material that was transferred to Tank 40 from Tank 51. SB7a was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Three pour stream glass samples and two Melter Feed Tank (MFT) slurry samples were collected while processing SB7a. These additional samples were taken during SB7a to understand the impact of antifoam and the melter bubblers on glass redox chemistry. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed.

  3. Proof of concept and performance optimization of high gravity batch type centrifuge for dewatering fine coal

    SciTech Connect (OSTI)

    Smith, L.B.; Durney, T.E. Jr.

    1991-04-23

    Coal Technology Corporation (CTC) believes that the new CTC high gravity, high production, batch type centrifugal dryer technology can play a significant role in improving the product quality as well as costs of operation in coal processing plants. It is further believed that the new centrifugal dryer technology can form an important part in systems used to clean up millions of tons of coal fines in refuse piles and ponds. It is anticipated that the new centrifuge can become an important ancillary to the advanced deep cleaning processes for coal. Because of these convictions, CTC has been engaged in a pioneering research effort into the new art of drying fine clean coal in high gravity, high production, batch type of centrifuge, since 1981. This work has progressed to the point where the new centrifugal dryer technology is nearly ready for commercialization. It promises to provide needed fine coal drying capability at somewhat lower capital costs and at substantially lower operating costs than competitive systems. It also promises to do so with no detrimental effects on either the coal quality or the environment. The primary objective of this project is to prove the concept of a high gravity batch centrifuge for drying coal fines in a commercial coal processing plant environment. The proof of concept tests also include testing with a variety of coals from different regions. A further objective is to optimize the efficiency and the cost effectiveness of the new centrifugal dryer technology. 2 figs., 3 tabs.

  4. Small Scale Mixing Demonstration Batch Transfer and Sampling Performance of Simulated HLW - 12307

    SciTech Connect (OSTI)

    Jensen, Jesse; Townson, Paul; Vanatta, Matt

    2012-07-01

    The ability to effectively mix, sample, certify, and deliver consistent batches of High Level Waste (HLW) feed from the Hanford Double Shell Tanks (DST) to the Waste treatment Plant (WTP) has been recognized as a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. At the end of 2009 DOE's Tank Operations Contractor, Washington River Protection Solutions (WRPS), awarded a contract to EnergySolutions to design, fabricate and operate a demonstration platform called the Small Scale Mixing Demonstration (SSMD) to establish pre-transfer sampling capacity, and batch transfer performance data at two different scales. This data will be used to examine the baseline capacity for a tank mixed via rotational jet mixers to transfer consistent or bounding batches, and provide scale up information to predict full scale operational performance. This information will then in turn be used to define the baseline capacity of such a system to transfer and sample batches sent to WTP. The Small Scale Mixing Demonstration (SSMD) platform consists of 43'' and 120'' diameter clear acrylic test vessels, each equipped with two scaled jet mixer pump assemblies, and all supporting vessels, controls, services, and simulant make up facilities. All tank internals have been modeled including the air lift circulators (ALCs), the steam heating coil, and the radius between the wall and floor. The test vessels are set up to simulate the transfer of HLW out of a mixed tank, and collect a pre-transfer sample in a manner similar to the proposed baseline configuration. The collected material is submitted to an NQA-1 laboratory for chemical analysis. Previous work has been done to assess tank mixing performance at both scales. This work involved a combination of unique instruments to understand the three dimensional distribution of solids using a combination of Coriolis meter measurements, in situ chord length distribution measurements, and electro-resistive tomography. This current work utilized the same instruments to monitor simulated waste transfers. This paper will discuss some of the scaling compromises when it came to the scaled sampling system design, handling of large quantities of material for sampling, and present data for the discuss of likely behavior of the full scale DST based on scaling correlations using a scale ratio exponent (SRE) from 0.25 to 0.45 and the behavior observed in the SSMD platform. This does not establish a scaling factor for DST mixing using paired jet mixers but is an attempt to envelope the likely performance ranges in terms of certification sampling bias, certification sample root-mean-square-deviation, and bath to batch relative standard deviation. (authors)

  5. STATISTICAL EVALUATION OF SMALL SCALE MIXING DEMONSTRATION SAMPLING AND BATCH TRANSFER PERFORMANCE - 12093

    SciTech Connect (OSTI)

    GREER DA; THIEN MG

    2012-01-12

    The ability to effectively mix, sample, certify, and deliver consistent batches of High Level Waste (HLW) feed from the Hanford Double Shell Tanks (DST) to the Waste Treatment and Immobilization Plant (WTP) presents a significant mission risk with potential to impact mission length and the quantity of HLW glass produced. DOE's Tank Operations Contractor, Washington River Protection Solutions (WRPS) has previously presented the results of mixing performance in two different sizes of small scale DSTs to support scale up estimates of full scale DST mixing performance. Currently, sufficient sampling of DSTs is one of the largest programmatic risks that could prevent timely delivery of high level waste to the WTP. WRPS has performed small scale mixing and sampling demonstrations to study the ability to sufficiently sample the tanks. The statistical evaluation of the demonstration results which lead to the conclusion that the two scales of small DST are behaving similarly and that full scale performance is predictable will be presented. This work is essential to reduce the risk of requiring a new dedicated feed sampling facility and will guide future optimization work to ensure the waste feed delivery mission will be accomplished successfully. This paper will focus on the analytical data collected from mixing, sampling, and batch transfer testing from the small scale mixing demonstration tanks and how those data are being interpreted to begin to understand the relationship between samples taken prior to transfer and samples from the subsequent batches transferred. An overview of the types of data collected and examples of typical raw data will be provided. The paper will then discuss the processing and manipulation of the data which is necessary to begin evaluating sampling and batch transfer performance. This discussion will also include the evaluation of the analytical measurement capability with regard to the simulant material used in the demonstration tests. The paper will conclude with a discussion of the analysis results illustrating the relationship between the pre-transfer samples and the batch transfers, which support the recommendation regarding the need for a dedicated feed sampling facility.

  6. SLUDGE BATCH 7B QUALIFICATION ACTIVITIES WITH SRS TANK FARM SLUDGE

    SciTech Connect (OSTI)

    Pareizs, J.; Click, D.; Lambert, D.; Reboul, S.

    2011-11-16

    Waste Solidification Engineering (WSE) has requested that characterization and a radioactive demonstration of the next batch of sludge slurry - Sludge Batch 7b (SB7b) - be completed in the Shielded Cells Facility of the Savannah River National Laboratory (SRNL) via a Technical Task Request (TTR). This characterization and demonstration, or sludge batch qualification process, is required prior to transfer of the sludge from Tank 51 to the Defense Waste Processing Facility (DWPF) feed tank (Tank 40). The current WSE practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks. Discharges of nuclear materials from H Canyon are often added to Tank 51 during sludge batch preparation. The sludge is washed and transferred to Tank 40, the current DWPF feed tank. Prior to transfer of Tank 51 to Tank 40, SRNL typically simulates the Tank Farm and DWPF processes with a Tank 51 sample (referred to as the qualification sample). With the tight schedule constraints for SB7b and the potential need for caustic addition to allow for an acceptable glass processing window, the qualification for SB7b was approached differently than past batches. For SB7b, SRNL prepared a Tank 51 and a Tank 40 sample for qualification. SRNL did not receive the qualification sample from Tank 51 nor did it simulate all of the Tank Farm washing and decanting operations. Instead, SRNL prepared a Tank 51 SB7b sample from samples of Tank 7 and Tank 51, along with a wash solution to adjust the supernatant composition to the final SB7b Tank 51 Tank Farm projections. SRNL then prepared a sample to represent SB7b in Tank 40 by combining portions of the SRNL-prepared Tank 51 SB7b sample and a Tank 40 Sludge Batch 7a (SB7a) sample. The blended sample was 71% Tank 40 (SB7a) and 29% Tank 7/Tank 51 on an insoluble solids basis. This sample is referred to as the SB7b Qualification Sample. The blend represented the highest projected Tank 40 heel (as of May 25, 2011), and thus, the highest projected noble metals content for SB7b. Characterization was performed on the Tank 51 SB7b samples and SRNL performed DWPF simulations using the Tank 40 SB7b material. This report documents: (1) The preparation and characterization of the Tank 51 SB7b and Tank 40 SB7b samples. (2) The performance of a DWPF Chemical Process Cell (CPC) simulation using the SB7b Tank 40 sample. The simulation included a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid was added to the sludge to destroy nitrite and reduce mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit was added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters were based on work with a nonradioactive simulant. (3) Vitrification of a portion of the SME product and characterization and durability testing (as measured by the Product Consistency Test (PCT)) of the resulting glass. (4) Rheology measurements of the SRAT receipt, SRAT product, and SME product. This program was controlled by a Task Technical and Quality Assurance Plan (TTQAP), and analyses were guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF. It should be noted that much of the data in this document has been published in interoffice memoranda. The intent of this technical report is bring all of the SB7b related data together in a single permanent record and to discuss the overall aspects of SB7b processing.

  7. North Portal Fuel Storage System Fire Hazard Analysis-ESF Surface Design Package ID

    SciTech Connect (OSTI)

    N.M. Ruonavaara

    1995-01-18

    The purpose of the fire hazard analysis is to comprehensively assess the risk from fire within the individual fire areas. This document will only assess the fire hazard analysis within the Exploratory Studies Facility (ESF) Design Package ID, which includes the fuel storage system area of the North Portal facility, and evaluate whether the following objectives are met: 1.1.1--This analysis, performed in accordance with the requirements of this document, will satisfy the requirements for a fire hazard analysis in accordance with U.S. Department of Energy (DOE) Order 5480.7A. 1.1.2--Ensure that property damage from fire and related perils does not exceed an acceptable level. 1.1.3--Provide input to the ESF Basis For Design (BFD) Document. 1.1.4 Provide input to the facility Safety Analysis Report (SAR) (Paragraph 3.8).

  8. Yucca Mountain Project Integrated Data System (IDS); Final report, October 1, 1989--December 31, 1990

    SciTech Connect (OSTI)

    1991-05-23

    This final report for LANL Subcontract 9-XS8-2604-1 includes copies of all formal letters, memorandums, and reports provided by CAG to support the IDS effort in the LANL Test Managers Office, Las Vegas, Nevada from October 1, 1989 through the end of the contract on December 31, 1990. The material is divided into two sections; the Functional Requirements Document (FRD) and other reports, letters, and memorandums. All documents are arranged in chronological order with most recent last. Numerous draft copies of the FRD were prepared and cover sheets for all drafts are included. The complete text of only the last version supplied (July 27, 1990) is included in this document.

  9. Evaluation of ISDP Batch 2 Qualification Compliance to 512-S, DWPF, Tank Farm, and Saltstone Waste Acceptance Criteria

    SciTech Connect (OSTI)

    Shafer, A.

    2010-05-05

    The purpose of this report is to document the acceptability of the second macrobatch (Salt Batch 2) of Tank 49H waste to H Tank Farm, DWPF, and Saltstone for operation of the Interim Salt Disposition Project (ISDP). Tank 49 feed meets the Waste Acceptance Criteria (WAC) requirements specified by References 11, 12, and 13. Salt Batch 2 material is qualified and ready to be processed through ARP/MCU to the final disposal facilities.

  10. Batch methods for enriching trace impurities in hydrogen gas for their further analysis

    DOE Patents [OSTI]

    Ahmed, Shabbir; Lee, Sheldon H.D.; Kumar, Romesh; Papdias, Dionissios D.

    2014-07-15

    Provided herein are batch methods and devices for enriching trace quantities of impurities in gaseous mixtures, such as hydrogen fuel. The methods and devices rely on concentrating impurities using hydrogen transport membranes wherein the time period for concentrating the sample is calculated on the basis of optimized membrane characteristics, comprising its thickness and permeance, with optimization of temperature, and wherein the enrichment of trace impurities is proportional to the pressure ratio P.sub.hi/P.sub.lo and the volume ratio V.sub.1/V.sub.2, with following detection of the impurities using commonly-available detection methods.

  11. Status of the first batch of niobium resonator production for the New Delhi booster linac.

    SciTech Connect (OSTI)

    Potukuchi, P. N.

    1999-03-16

    This paper reports the status and details of the costs of construction of niobium superconducting resonant cavities for a linear accelerator, presently being built as a booster for the 15 UD tandem Pelletron accelerator at the Nuclear Science Centre, New Delhi. The linear accelerator will have three cryostat modules, each holding eight quarter-wave resonators. Construction of a batch of ten resonators for the linac started at Argonne National Laboratory in May 1997. For production, all fabrication and all electron beam welding is being done through commercial vendors. Details of construction and present status of the project are presented.

  12. A 12-MW-scale pilot study of in-duct scrubbing (IDS) using a rotary atomizer

    SciTech Connect (OSTI)

    Samuel, E.A.; Murphy, K.R.; Demian, A.

    1989-11-01

    A low-cost, moderate-removal efficiency, flue gas desulfurization (FGD) technology was selected by the US Department of Energy for pilot demonstration in its Acid Rain Precursor Control Technology Initiative. The process, identified as In-Duct Scrubbing (IDS), applies rotary atomizer techniques developed for lime-based spray dryer FGD while utilizing existing flue gas ductwork and particulate collectors. IDS technology is anticipated to result in a dry desulfurization process with a moderate removal efficiency (50% or greater) for high-sulfur coal-fired boilers. The critical elements for successful application are: (1) adequate mixing of sorbent droplets with flue gas for efficient reaction contact, (2) sufficient residence time to produce a non-wetting product, and (3) appropriate ductwork cross-sectional area to prevent deposition of wet reaction products before particle drying is comple. The ductwork in many older plants, previously modified to meet 1970 Clean Air Act requirements for particulate control, usually meet these criteria. A 12 MW-scale IDS pilot plant was constructed at the Muskingum River Plant of the American Electric Power System. The pilot plant, which operates from a slipstrem attached to the air-preheater outlet duct from the Unit 5 boiler at the Muskingum River Plant (which burns about 4% sulfur coal), is equipped with three atomizer stations to test the IDS concept in vertical and horizontal configurations. In addition, the pilot plant is equipped to test the effect of injecting IDS off- product upstream of the atomizer, on SO{sub 2}and NO{sub x} removals.

  13. Proof of concept and performance optimization of high gravity batch type centrifuge for dewatering fine coal

    SciTech Connect (OSTI)

    Smith, L.B.; Durney, T.E. Jr.

    1990-07-24

    Coal Technology Corporation (CTC) believes that the new CTC high gravity, high production, batch type centrifugal dryer technology can play a significant role in improving the product quality as well as costs of operation in coal processing plants. It is further believed that the new centrifugal dryer technology can form an important part in systems used to clean up the millions of tons of coal fines in refuse piles and ponds. It is anticipated that the new centrifuge can become an important ancillary to the advanced deep cleaning processes for coal. Because of these convictions, CTC has been engaged in a pioneering research effort into the new art of drying fine clean coal in high gravity, high production, batch type centrifuges, since 1981. This work has progressed to the point where the new centrifugal dryer technology is nearly ready for commercialization. It promises to provide needed fine coal drying capability at somewhat lower capital costs and at substantially lower operating costs than competitive systems. It also promises to do so with no detrimental effects on either the coal quality or the evironment. The primary objective of this project is to prove the concept in a commercial coal processing plant environment. The proof of concept tests will also include testing with a variety of coals from different regions. A further objective will be to optimize the efficiency and the cost effectiveness of the new centrifugal dryer technology.

  14. Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Wu, Weimin; Criddle, Craig S.

    2015-11-16

    We (the Stanford research team) were invited as external collaborators to contribute expertise in environmental engineering and field research at the ORNL IFRC, Oak Ridge, TN, for projects carried out at the Argonne National Laboratory and funded by US DOE. Specifically, we assisted in the design of batch and column reactors using ORNL IFRC materials to ensure the experiments were relevant to field conditions. During the funded research period, we characterized ORNL IFRC groundwater and sediments in batch microcosm and column experiments conducted at ANL, and we communicated with ANL team members through email and conference calls and face-to-face meetings at the annual ERSP PI meeting and national meetings. Microcosm test results demonstrated that U(VI) in sediments was reduced to U(IV) when amended with ethanol. The reduced products were not uraninite but unknown U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. Due to budget reductions at ANL, Stanford contributions ended in 2011.

  15. Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

    SciTech Connect (OSTI)

    Crawford, C. L.; Diprete, D. P.

    2012-12-17

    The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. Twenty-seven radionuclides have been identified as reportable for DWPF SB7b. Each of these radionuclides has a half-life greater than ten years and contributes more than 0.01% of the radioactivity on a Curie basis at some point from production through the 1100 year period between 2015 and 3115. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. The radionuclide measurements made for SB7b are the most extensive conducted to date. Some method development/refinement occurred during the conduct of these measurements, leading to lower detection limits and more accurate measurement of some isotopes than was previously possible.

  16. INTERPRETATION OF AT-LINE SPECTRA FROM AFS-2 BATCH #3 FERROUS SULFAMATE TREATMENT

    SciTech Connect (OSTI)

    Kyser, E.; O'Rourke, P.

    2013-12-10

    Spectra from the at-line spectrometer were obtained during the ferrous sulfamate (FS) valence adjustment step of AFS-2 Batch #3 on 9/18/2013. These spectra were analyzed by mathematical principal component regression (PCR) techniques to evaluate the effectiveness of this treatment. Despite the complications from Pu(IV), we conclude that all Pu(VI) was consumed during the FS treatment, and that by the end of the treatment, about 85% was as Pu(IV) and about 15% was as Pu(III). Due to the concerns about the odd shape of the Pu(IV) peak and the possibility of this behavior being observed in the future, a follow-up sample was sent to SRNL to investigate this further. Analysis of this sample confirmed the previous results and concluded that it odd shape was due to an intermediate acid concentration. Since the spectral evidence shows complete reduction of Pu(VI) we conclude that it is appropriate to proceed with processing of this the batch of feed solution for HB-Line including the complexation of the fluoride with aluminum nitrate.

  17. Determination of Reportable Radionuclides for DWPF Sludge Batch 3 (Macrobatch 4)

    SciTech Connect (OSTI)

    Bannochie, C

    2005-05-01

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that ''The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115''. As part of the strategy to meet WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, IAEA Safeguards Reporting for HLW, requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The Defense Waste Processing Facility (DWPF) is receiving radioactive sludge slurry from High Level Waste Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the previous contents of Tank 40 (Sludge Batch 2) and the sludge that was transferred to Tank 40 from Tank 51. The blend of sludge from Tank 51 and Tank 40 defines Macrobatch 4 (also referred to as Sludge Batch 3). This report develops the list of reportable radionuclides and associated activities and determines the radionuclide activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Task Technical Request HLW/DWPF/TTR-03-0005, Revision 1 entitled Sludge Batch 3 SRTC Shielded Cells Testing. Specifically, this report details results from performing, in part, Subtask 3 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Technical Task and Quality Assurance Plan (TTQAP), WSRC-RP-2003-00249, Rev. 1 and Analytical Study Plan (ASP), WSRC-RP-2004-00262. In order to determine the reportable radionuclides for Sludge Batch 3 (Macro Batch 4), a list of radioisotopes that may meet the criteria as specified by the Department of Energy's (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes excluded from the projection calculations.

  18. ANALYSIS OF DWPF SLUDGE BATCH 7A (MACROBATCH 8) POUR STREAM SAMPLES

    SciTech Connect (OSTI)

    Johnson, F.

    2012-05-01

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7a (SB7a), also referred to as Macrobatch 8 (MB8), in June 2011. SB7a is a blend of the heel of Tank 40 from Sludge Batch 6 (SB6) and the SB7a material that was transferred to Tank 40 from Tank 51. SB7a was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Three pour stream glass samples and two Melter Feed Tank (MFT) slurry samples were collected while processing SB7a. These additional samples were taken during SB7a to understand the impact of antifoam and the melter bubblers on glass redox chemistry. The samples were transferred to the Savannah River National Laboratory (SRNL) where they were analyzed. The following conclusions were drawn from the analytical results provided in this report: (1) The sum of oxides for the official SB7a pour stream glass is within the Product Composition Control System (PCCS) limits (95-105 wt%). (2) The average calculated Waste Dilution Factor (WDF) for SB7a is 2.3. In general, the measured radionuclide content of the official SB7a pour stream glass is in good agreement with the calculated values from the Tank 40 dried sludge results from the SB7a Waste Acceptance Program Specification (WAPS) sample. (3) As in previous pour stream samples, ruthenium and rhodium inclusions were detected by Scanning Electron Microscopy-Electron Dispersive Spectroscopy (SEM-EDS) in the official SB7a pour stream sample. (4) The Product Consistency Test (PCT) results indicate that the official SB7a pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.64 g/L, which is an order of magnitude less than the Environmental Assessment (EA) glass. (5) The measured density of the SB7a pour stream glass was 2.7 g/cm{sup 3}. (6) The Fe{sup 2+}/{Sigma}Fe ratios of the SB7a pour stream samples were in the range of 0.04-0.13, while the MFT sample glasses prepared by SRNL were in the range of 0.02-0.04.

  19. ANALYSIS OF DWPF SLUDGE BATCH 6 (MACROBATCH 7) POUR STREAM GLASS SAMPLES

    SciTech Connect (OSTI)

    Johnson, F.

    2012-01-20

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 6 (SB6), also referred to as Macrobatch 7 (MB7), in June 2010. SB6 is a blend of the heel of Tank 40 from Sludge Batch 5 (SB5), H-Canyon Np transfers and SB6 that was transferred to Tank 40 from Tank 51.1 SB6 was processed using Frit 418. Sludge is received into the DWPF Chemical Processing Cell (CPC) and is processed through the Sludge Receipt and Adjustment Tank (SRAT) and Slurry Mix Evaporator Tank (SME). The treated sludge slurry is then transferred to the Melter Feed Tank (MFT) and fed to the melter. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP) and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. The DWPF requested various analyses of radioactive glass samples obtained from the melter pour stream during processing of SB6 as well as reduction/oxidation (REDOX) analysis of MFT samples to determine the impact of Argon bubbling. Sample analysis followed the Task Technical and Quality Assurance Plan (TTQAP) and an Analytical Study Plan (ASP). Four Pour Stream (PS) glass samples and two MFT slurry samples were delivered to the Savannah River National Laboratory (SRNL) from the DWPF. Table 1-1 lists the sample information for each pour stream glass sample. SB6 PS3 (S03472) was selected as the official pour stream sample for SB6 and full analysis was requested. This report details the visual observations of the as-received SB6 PS No.3 glass sample as well as results for the chemical composition, Product Consistency Test (PCT), radionuclide content, noble metals, and glass density. REDOX results will be provided for all four pour stream samples and vitrified samples of MFT-558 and MFT-568A. Where appropriate, data from other pour stream samples will be provided.

  20. Analysis Of The Sludge Batch 7b (Macrobatch 9) DWPF Pour Stream Glass Sample

    SciTech Connect (OSTI)

    Johnson, F. C.; Crawford, C. L.; Pareizs, J. M.

    2013-11-18

    The Defense Waste Processing Facility (DWPF) began processing Sludge Batch 7b (SB7b), also referred to as Macrobatch 9 (MB9), in January 2012. SB7b is a blend of the heel of Tank 40 from Sludge Batch 7a (SB7a) and the SB7b material that was transferred to Tank 40 from Tank 51. SB7b was processed using Frit 418. During processing of each sludge batch, the DWPF is required to take at least one glass sample to meet the objectives of the Glass Product Control Program (GPCP), which is governed by the DWPF Waste Form Compliance Plan, and to complete the necessary Production Records so that the final glass product may be disposed of at a Federal Repository. Two pour stream glass samples were collected while processing SB7b. The samples were transferred to the Savannah River National Laboratory (SRNL) where one was analyzed and the other was archived. The following conclusions were drawn from the analytical results provided in this report: The sum of oxides for the official SB7b pour stream glass is within the Product Composition Control System (PCCS) limits (95-105 wt%); The average calculated Waste Dilution Factor (WDF) for SB7b is 2.3. In general, the measured radionuclide content of the official SB7b pour stream glass is in good agreement with the calculated values from the Tank 40 dried sludge results from the SB7b Waste Acceptance Program Specification (WAPS) sample; As in previous pour stream samples, ruthenium and rhodium inclusions were detected by Scanning Electron Microscopy-Electron Dispersive Spectroscopy (SEM-EDS) in the SB7b pour stream sample; The Product Consistency Test (PCT) results indicate that the official SB7b pour stream glass meets the waste acceptance criteria for durability with a normalized boron release of 0.8 g/L, which is an order of magnitude less than the Environmental Assessment (EA) glass; The measured density of the SB7b pour stream glass was 2.70 g/cm{sup 3}; The Fe{sup 2+}/?Fe ratio of the SB7b pour stream samples was 0.07.

  1. Verification Of The Defense Waste Processing Facility's (DWPF) Process Digestion Methods For The Sludge Batch 8 Qualification Sample

    SciTech Connect (OSTI)

    Click, D. R.; Edwards, T. B.; Wiedenman, B. J.; Brown, L. W.

    2013-03-18

    This report contains the results and comparison of data generated from inductively coupled plasma atomic emission spectroscopy (ICP-AES) analysis of Aqua Regia (AR), Sodium Peroxide/Sodium Hydroxide Fusion Dissolution (PF) and Cold Chem (CC) method digestions and Cold Vapor Atomic Absorption analysis of Hg digestions from the DWPF Hg digestion method of Sludge Batch 8 (SB8) Sludge Receipt and Adjustment Tank (SRAT) Receipt and SB8 SRAT Product samples. The SB8 SRAT Receipt and SB8 SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constitutes the SB8 Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 7b (SB7b), to form the SB8 Blend composition.

  2. Analysis of Tank 35H Samples in Support of Salt Batch Planning

    SciTech Connect (OSTI)

    Hay, M. S.; Coleman, C. J.; Diprete, D. P.

    2015-04-30

    Savannah River Remediation obtained three samples from different heights within Tank 35H. The samples were analyzed by Savannah River National Laboratory to support Salt Batch planning. The results from the analysis indicate the compositions of the three samples show increasing concentrations for most analytes going from HTF-35-15-17 through HTF-35-15-19 corresponding to successively deeper sampling locations. The data indicate some stratification within the tank. The plutonium and Sr-90 concentrations measured in the filtered samples were slightly lower than in the decanted (unfiltered) samples. The difference in the results for the filtered and unfiltered samples likely lies within the expected uncertainty for the measurement, but may indicate that filtration removed a small amount of suspended material from the samples.

  3. Analysis of tank 23H samples in support of salt batch planning

    SciTech Connect (OSTI)

    Hay, M. S.; Coleman, C. J.; Diprete, D. P.

    2015-08-14

    Savannah River Remediation obtained three samples from different heights within Tank 23H. The samples were analyzed by Savannah River National Laboratory to support salt batch planning. The results from the analysis indicate the top two samples from the tank appear similar in composition. The lowest sample from the tank contained significantly more solids and a more concentrated salt solution. The filtered supernate from the bottom sample showed ~60% lower Sr-90 and Pu-238 concentrations than the decanted (unfiltered) supernate results which may indicate the presence of some small amount of entrained solid particles in the decanted sample. The mercury concentrations measured in the filtered supernate were fairly low for all three samples ranging from 11.2 to 42.3 mg/L.

  4. Numerical model for the vacuum pyrolysis of scrap tires in batch reactors

    SciTech Connect (OSTI)

    Yang, J.; Tanguy, P.A.; Roy, C.

    1995-06-01

    A quantitative model for scrap tire pyrolysis in a batch scale reactor developed comprises the following basic phenomena: conduction inside tire particles; conduction, convection, and radiation between the feedstock particles or between the fluids and the particles; tire pyrolysis reaction; exothermicity and endothermicity caused by tire decomposition and volatilization; and the variation of the composition and the thermal properties of tire particles. This model was used to predict the transient temperature and density distributions in the bed of particles, the volatile product evolution rate, the mass change, the energy consumption during the pyrolysis process, and the pressure history in a tire pyrolysis reactor with a load of 1 kg. The model predictions agree well with independent experimental data.

  5. DWPF coupled feed flowsheet material balance with batch one sludge and copper nitrate catalyst

    SciTech Connect (OSTI)

    Choi, A.S.

    1993-09-28

    The SRTC has formally transmitted a recommendation to DWPF to replace copper formate with copper nitrate as the catalyst form during precipitate hydrolysis [1]. The SRTC was subsequently requested to formally document the technical bases for the recommendation. A memorandum was issued on August 23, 1993 detailing the activities (and responsible individuals) necessary to address the impact of this change in catalyst form on process compatibility, safety, processibility environmental impact and product glass quality [2]. One of the activities identified was the preparation of a material balance in which copper nitrate is substituted for copper formate and the identification of key comparisons between this material balance and the current Batch 1 sludge -- Late Wash material balance [3].

  6. Experiences with a compost biofilter for VOC control from batch chemical manufacturing operations

    SciTech Connect (OSTI)

    Gilmore, G.L.; Briggs, T.G.

    1997-12-31

    The Synthetic Chemicals Division of Eastman Kodak Company makes a large number of complex organic chemicals using batch reactor syntheses. Exhaust gas, resulting from batch reactor operations, typically contains many different volatile organic chemicals with dynamic concentration profiles. Exhaust streams of this type have been considered difficult to treat effectively by biofiltration. Eastman Kodak Company was interested in exploring the applicability of biofiltration to treat these types of off-gas streams as an alternative to more costly control technologies. To this end, a 20,000 cfm capacity BIOTON{reg_sign} biofilter was installed in December 1995 in Kodak Park, Rochester, New York. A study was initiated to determine the overall efficiency of the biofilter, as well as the chemical specific efficiencies for a number of organic compounds. Flame ionization detectors operated continuously on the inlet and outlet of the biofilter to measure total hydrocarbon concentrations. A process mass spectrometer was installed to simultaneously monitor the concentrations of seven organics in the inlet and outlet of the biofilter. In addition, the process control software for the biofilter continuously recorded pressure drop, temperature, and moisture content of the bed. This paper presents operating and performance data for the BIOTON biofilter from start-up through about eleven months of continuous operation. Included are data collected over a wide range of loading conditions, during initial start-up, and during start-up after shutdown periods. Data for total hydrocarbons, methanol, acetone, and heptane are presented. The relationship between organic loading and removal efficiency is discussed in the biofilter, which typically operates significantly below its design loading specification. The overall control efficiency of the biofilter at design loadings exceeds the design control efficiency of 90%.

  7. Kinetics and dynamic modelling of batch anaerobic digestion of municipal solid waste in a stirred reactor

    SciTech Connect (OSTI)

    Nopharatana, Annop; Pullammanappallil, Pratap C.; Clarke, William P.

    2007-07-01

    A series of batch, slurry anaerobic digestion experiments were performed where the soluble and insoluble fractions, and unwashed MSW were separately digested in a 200 l stirred stainless steel vessel at a pH of 7.2 and a temperature of 38 deg. C. It was found that 7% of the total MSW COD was readily soluble, of which 80% was converted to biogas; 50% of the insoluble fraction was solubilised, of this only 80% was converted to biogas. The rate of digesting the insoluble fraction was about four times slower than the rate of digesting the soluble fraction; 48% of the total COD was converted to biogas and 40% of the total nitrogen was converted to ammonia. Soluble and insoluble fractions were broken down simultaneously. The minimum time to convert 95% of the degradable fraction to biogas was 20 days. The lag phase for the degradation of insoluble fraction of MSW can be overcome by acclimatising the culture with the soluble fraction. The rate of digestion and the methane yield was not affected by particle size (within the range of 2-50 mm). A dynamic model was developed to describe batch digestion of MSW. The parameters of the model were estimated using data from the separate digestion of soluble and insoluble fractions and validated against data from the digestion of unwashed MSW. Trends in the specific aceticlastic and formate-utilising methanogenic activity were used to estimate initial methanogenic biomass concentration and bacterial death rate coefficient. The kinetics of hydrolysis of insoluble fraction could be adequately described by a Contois equation and the kinetics of acidogenesis, and aceticlastic and hydrogen utilising methanogenesis by Monod equations.

  8. T-582: RSA systems has resulted in certain information being extracted from RSA systems that relates to RSA SecurID

    Broader source: Energy.gov [DOE]

    RSA investigation has revealed that the attack resulted in certain information being extracted from RSA's systems. Some of that information is related to RSA's SecurID two-factor authentication products.

  9. T-559: Stack-based buffer overflow in oninit in IBM Informix Dynamic Server (IDS) 11.50 allows remote execution

    Broader source: Energy.gov [DOE]

    Stack-based buffer overflow in oninit in IBM Informix Dynamic Server (IDS) 11.50 allows remote execution attackers to execute arbitrary code via crafted arguments in the USELASTCOMMITTED session environment option in a SQL SET ENVIRONMENT statement

  10. Semi-Batch Deoxygenation of Canola- and Lard-Derived Fatty Acids to Diesel-Range Hydrocarbons

    SciTech Connect (OSTI)

    Ford, JP; Thapaliya, N; Kelly, MJ; Roberts, WL; Lamb, HH

    2013-12-01

    Fatty acids (FAs) derived via thermal hydrolysis of food-grade lard and canola oil were deoxygenated in the liquid phase using a commercially available 5 wt % Pd/C catalyst. Online quadrupole mass spectrometry and gas chromatography were used to monitor the effluent gases from the semi-batch stirred autoclave reactors. Stearic, oleic, and palmitic acids were employed as model compounds. A catalyst lifetime exceeding 2200 turnovers for oleic acid deoxygenation was demonstrated at 300 degrees C and 15 atm under 10% H-2. The initial decarboxylation rate of palmitic acid under 5% H-2 decreases sharply with increasing initial concentration; in contrast, the initial decarbonylation rate increases linearly, indicative of first-order kinetics. Scale-up of diesel-range hydrocarbon production was investigated by increasing the reactor vessel size, initial FA concentration, and FA/catalyst mass ratio. Lower CO2 selectivity and batch productivity were observed at the larger scales (600 and 5000 mL), primarily because of the higher initial FA concentration (67 wt %) employed. Because unsaturated FAs must be hydrogenated before deoxygenation can proceed at an appreciable rate, the additional batch time required for FA hydrogenation reduces the batch productivity for unsaturated feedstocks. Low-temperature hydrogenation of unsaturated feedstocks (using Pd/C or another less-expensive catalyst) prior to deoxygenation is recommended.

  11. VERIFICATION OF THE DEFENSE WASTE PROCESSING FACILITY'S (DWPF) PROCESS DIGESTION METHOD FOR THE SLUDGE BATCH 7A QUALIFICATION SAMPLE

    SciTech Connect (OSTI)

    Click, D.; Edwards, T.; Jones, M.; Wiedenman, B.

    2011-03-14

    For each sludge batch that is processed in the Defense Waste Processing Facility (DWPF), the Savannah River National Laboratory (SRNL) performs confirmation of the applicability of the digestion method to be used by the DWPF lab for elemental analysis of Sludge Receipt and Adjustment Tank (SRAT) receipt samples and SRAT product process control samples. DWPF SRAT samples are typically dissolved using a room temperature HF-HNO{sub 3} acid dissolution (i.e., DWPF Cold Chem Method, see DWPF Procedure SW4-15.201) and then analyzed by inductively coupled plasma - atomic emission spectroscopy (ICP-AES). This report contains the results and comparison of data generated from performing the Aqua Regia (AR), Sodium peroxide/Hydroxide Fusion (PF) and DWPF Cold Chem (CC) method digestions of Sludge Batch 7a (SB7a) SRAT Receipt and SB7a SRAT Product samples. The SB7a SRAT Receipt and SB7a SRAT Product samples were prepared in the SRNL Shielded Cells, and the SRAT Receipt material is representative of the sludge that constituates the SB7a Batch or qualification composition. This is the sludge in Tank 51 that is to be transferred into Tank 40, which will contain the heel of Sludge Batch 6 (SB6), to form the Sb7a Blend composition.

  12. THE SLUDGE BATCH 7A GLASS VARIABILITY STUDY WITH FRIT 418 AND FRIT 702

    SciTech Connect (OSTI)

    Peeler, D.; Edwards, T.

    2011-03-24

    The Defense Waste Processing Facility (DWPF) is preparing to initiate processing of Sludge Batch 7a (SB7a) in May 2011. To support qualification of SB7a, the Savannah River National Laboratory (SRNL) was requested to execute a variability study (VS) to assess the applicability of the current Product Composition Control System (PCCS) durability models for the Frit 418-SB7a compositional region of interest. The objective of this study was to demonstrate applicability of the current durability models to the SB7a compositional region of interest and acceptability of the SB7a glasses with respect to the Environmental Assessment (EA) glass in terms of durability as defined by the Product Consistency Test (PCT). To support programmatic objectives, twenty-eight SB7a glasses were selected based on the nominal sludge projections used to support the frit recommendation. Twenty-three of the SB7a VS glasses were based on the use of Frit 418, while 5 glasses were based on the use of Frit 702. Frit 702 was also identified as a viable candidate for SB7a, especially if SO{sub 4} concentrations are found to be higher than anticipated. Frit 702 has shown a higher SO{sub 4} retention capability as compared to Frit 418. With respect to acceptability, the PCT results of the SB7a-VS glasses are acceptable relative to the EA glass regardless of thermal history (quenched or canister centerline cooled) or compositional view (target or measured). More specifically, all of the SB7a glasses have normalized boron release values (NL [B]) less than 0.9 g/L as compared to the benchmark NL [B] value for EA of 16.695 g/L. With respect to the applicability of the current durability models to the SB7a VS compositional region of interest, all of the study glasses (based on target compositions) lie within the 95% confidence intervals of the model predictions. When model applicability is based on the measured compositions, all of the SB7a VS glasses are predictable with the exception of SB7aVS-02 and SB7aVS-06. Although the NL [B] values of these two glasses range from 0.66 to 0.73 g/L (considered very acceptable), the PCT responses are not considered predictable by the current durability models. The current durability models are conservative for these glasses since they are more durable than predicted by the models. These two glasses are extreme vertices (EV) based compositions coupled with Frit 418 at 36% WL and target the maximum Na{sub 2}O content (15.01 wt% Na{sub 2}O) of the SB7a VS glasses. Higher alkali glasses for which the model overpredicts the PCT response have been observed previously in the Sludge Batch 3 (SB3) Phase 1 VS and the Sludge Batch 6 (SB6) VS.

  13. Completing Pre-Pilot Tasks To Scale Up Biomass Fractionation Pretreatment Apparatus From Batch To Continuous

    SciTech Connect (OSTI)

    Dick Wingerson

    2004-12-15

    PureVision Technology, Inc. (PureVision) was the recipient of a $200,000 Invention and Innovations (I&I) grant from the U. S. Department of Energy (DOE) to complete prepilot tasks in order to scale up its patented biomass fractionation pretreatment apparatus from batch to continuous processing. The initial goal of the I&I program, as detailed in PureVision's original application to the DOE, was to develop the design criteria to build a small continuous biomass fractionation pilot apparatus utilizing a retrofitted extruder with a novel screw configuration to create multiple reaction zones, separated by dynamic plugs within the reaction chamber that support the continuous counter-flow of liquids and solids at elevated temperature and pressure. Although the ultimate results of this 27-month I&I program exceeded the initial expectations, some of the originally planned tasks were not completed due to a modification of direction in the program. PureVision achieved its primary milestone by establishing the design criteria for a continuous process development unit (PDU). In addition, PureVision was able to complete the procurement, assembly, and initiate shake down of the PDU at Western Research Institute (WRI) in Laramie, WY during August 2003 to February 2004. During the month of March 2004, PureVision and WRI performed initial testing of the continuous PDU at WRI.

  14. Proof of concept and performance optimization of high gravity batch type centrifuge for dewatering fine coal

    SciTech Connect (OSTI)

    Smith, L.B.; Durney, T.E. Jr.

    1990-10-24

    Coal Technology Corporation (CTC) believes that the new CTC high gravity, high production, batch type centrifugal dryer technology can play a significant role in improving the product quality as well as costs of operation in coal processing plants. It is further believed that the new centrifugal dryer technology can form an important part in systems used to clean up the millions of tons of coal fines in refuse piles and ponds. Work has progressed to the point where the new centrifugal dryer technology is nearly ready for commercialization. The primary objective of this project is to prove the concept in a commercial coal processing plant environment. The proof of concept tests will include testing with a variety of coals from different regions. A further objective will be to optimize the efficiency and the cost effectiveness of the new centrifugal dryer technology. To supply some perspective on the ability of the new centrifuges to successfully dry a variety of coals from various coal fields, it was decided that coals ranging from very fine to course size consists and with both low and high inherent moistures would be tested. Coals tested include: Pittsburgh no. 8 seam (Pennsylvania), Pittsburgh no. 8 seam (West Virginia), and Blue Creek Seam (Alabama). 6 figs.

  15. Method for automatically evaluating a transition from a batch manufacturing technique to a lean manufacturing technique

    DOE Patents [OSTI]

    Ivezic, Nenad; Potok, Thomas E.

    2003-09-30

    A method for automatically evaluating a manufacturing technique comprises the steps of: receiving from a user manufacturing process step parameters characterizing a manufacturing process; accepting from the user a selection for an analysis of a particular lean manufacturing technique; automatically compiling process step data for each process step in the manufacturing process; automatically calculating process metrics from a summation of the compiled process step data for each process step; and, presenting the automatically calculated process metrics to the user. A method for evaluating a transition from a batch manufacturing technique to a lean manufacturing technique can comprise the steps of: collecting manufacturing process step characterization parameters; selecting a lean manufacturing technique for analysis; communicating the selected lean manufacturing technique and the manufacturing process step characterization parameters to an automatic manufacturing technique evaluation engine having a mathematical model for generating manufacturing technique evaluation data; and, using the lean manufacturing technique evaluation data to determine whether to transition from an existing manufacturing technique to the selected lean manufacturing technique.

  16. Utilisation of single added fatty acids by consortia of digester sludge in batch culture

    SciTech Connect (OSTI)

    Wagner, Andreas Otto; Gstrauntaler, Gudrun; Illmer, Paul

    2010-10-15

    Inocula derived from an anaerobic digester were used to study (i) their potential for methane production and (ii) the utilisation rates of different short chain fatty acids (SCFAs) by the microbial community in defined media with mono-carbon sources (formic-, acetetic-, propionic-, butyric acid) in batch culture. It could be demonstrated that the microbial reactor population could be transferred successfully to the lab, and its ability to build up methane was present even with deteriorating biogas plant performance. Therefore, this reduction in performance of the biogas plant was not due to a decrease in abundance, but due to an inactivity of the microbial community. Generally, the physico-chemical properties of the biogas plant seemed to favour hydrogenotrophic methanogens, as seen by the high metabolisation rates of formate compared with all other carbon sources. In contrast, acetoclastic methanogenesis could be shown to play a minor role in the methane production of the investigated biogas plant, although the origin of up to 66% of methane is generally suggested to be generated through acetoclastic pathway.

  17. Power/Performance Trade-offs of Small Batched LU Based Solvers on GPUs

    SciTech Connect (OSTI)

    Villa, Oreste; Fatica, Massimiliano; Gawande, Nitin A.; Tumeo, Antonino

    2013-08-26

    In this paper we propose and analyze a set of batched linear solvers for small matrices on Graphic Processing Units (GPUs), evaluating the various alternatives depending on the size of the systems to solve. We discuss three different solutions that operate with different level of parallelization and GPU features. The first, exploiting the CUBLAS library, manages matrices of size up to 32x32 and employs Warp level (one matrix, one Warp) parallelism and shared memory. The second works at Thread-block level parallelism (one matrix, one Thread-block), still exploiting shared memory but managing matrices up to 76x76. The third is Thread level parallel (one matrix, one thread) and can reach sizes up to 128x128, but it does not exploit shared memory and only relies on the high memory bandwidth of the GPU. The first and second solution only support partial pivoting, the third one easily supports partial and full pivoting, making it attractive to problems that require greater numerical stability. We analyze the trade-offs in terms of performance and power consumption as function of the size of the linear systems that are simultaneously solved. We execute the three implementations on a Tesla M2090 (Fermi) and on a Tesla K20 (Kepler).

  18. 1. CON'I'AC'r ID CODE PAGE OF PAGES AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT II 11 3

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

    CON'I'AC'r ID CODE PAGE OF PAGES AMENDMENT OF SOLICITATIONIMODIFICATION OF CONTRACT II 11 3 2. AMENDMENT/MODIFICATION NO. 3. EFFECTIVE DATE (M/D.'F) 4. REQUISITION/PURCHASE RE-Q. NO. S. PROJECT1 NO. t7fapplieoble) 27See Block 16C 12EM001839 6. ISUED13Y ODE7. ADMINISTER.ED BY (If uI/wr ius /tem 6) CODE U.S. Department of Energy Office or River Protection P. 0. Box 450, MS 146-60 Richland, WA 99352 1. NAME AND ADDRESS OF CONTRACTOR (No.,stree, county State and Z11' code) 9A, AMENDMEN f

  19. 1. CONTRACT ID CODE PAGE OF PAGES AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT I11 5

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

    Ap5,sval 2700042 1. CONTRACT ID CODE PAGE OF PAGES AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT I11 5 2. AMENDMENT/MOOIFICATION NO. 3. EFFECTIVE DATE 4. REQUISITION/PURCHASE REQ. NO.5 PROJECT NO. (If applicable) A077 See 16C 06-08RL-14383.O1 1 6. ISSUED BY CODE 7. ADMINISTERED BY (If other than Item 6) CODEJ US. Department of Energy Same as item 6. Richland Operations Office DOE Contracting POC: Richard Stimmrrel P. 0. Box 550, MSIN A7-80 (509) 376-2882 Richland, WA 99352 8 NAME AND

  20. RESULTS OF RADIOLOGICAL I'IEASUREMENTS HIGHT{AYS 18 AI.ID IO4 IN NIAGARA

    Office of Legacy Management (LM)

    9s' RESULTS OF RADIOLOGICAL I'IEASUREMENTS HIGHT{AYS 18 AI.ID IO4 IN NIAGARA az76 rl//.ry' ORNL/RASA.85/ 40 TAKEN AT JUNCTION FALLS, NEH YORK Accesr to the information in thit rcport ir limiled to tho!' inOllateO on tho dl3tribution li3t and to OePartment ot Encrgy and Oepartmcnt ol Enotgy Gontracton This report was prepared as an account of work sponsored by an agency of the United States Government. Neitherth€ U nited StatesGovernment norany agency thereof, nor any of their employees, makes

  1. AMENDMENT OF SOLlClTATlONlMODlFlCATION OF CONTRACT 1 I . CONTR"CT ID CODE

    National Nuclear Security Administration (NNSA)

    SOLlClTATlONlMODlFlCATION OF CONTRACT 1 I . CONTR"CT ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, VA 24506 PAGE 1 OF 2 PAGES Albuquerque, NM 8718Ii4400 I Amarillo, TX 79120 9B. DATED (SEE m M 11) 10A. MODIFICATION OF CONTRACTIORDER NO. 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, &ate, ZIP Code) I ( DE-ACOCOOAL66620 10B. DATED (SEE / E M 13) 2. AMENDMENT/MODIFICATION NO. M097 9A. AMENDMENT OF SOLICITATION NO. Offera must a d t n d e d p rsceipt of this m e n

  2. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT I ' CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    ' CONTRACT ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, VA 24506 PAGE 1 OF 12 PAGES 9B. DATED (SEE ITEM 11) 5. PROJECT NO. (If applicable) 4. REQUlSlTlONlPURCHASE REQ. NO. 2. AMENDMENTIMODIFICATION NO. MI39 extended. 6. ISSUED BY CODE U.S. Department of Energy National Nuclear Security Administration Service Center Property and M&O Contract Support Department P.O. Box 5400 Albuquerque, NM 871 85-5400 3. EFFECTIVE DATE See Block 16C CODE I FACILITY CODE Offers must

  3. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT I CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    CONTRACT ID CODE Babcock & Wilcox Technical Services Pantex, LLC 9B. DATED (SEE ITEM 11) PO Box 30020 Amarillo, T X 79120 PAGE 1 OF 2 PAGES Albuquerque, NM 87185-5400 I Amarillo, TX 79120 I I DE-AC04-00AL66620 10B. DATED (SEE ITEM 13) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) 2. AMENDMENTIMODIFICATION NO. MI74 9A. AMENDMENT OF SOLICITATION NO. extended. CODE I FACILITY CODE Offers must acknowledge receipt of this amendment prior to the hour and date specified

  4. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT I I, CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    I, CONTRACT ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, V A 24506 PAGE I OF 2 PAGES Albuquerque, NM 87185-5400 I Amarillo, TX 79120 9B. DATED (SEE ITEM I I ) 8. NAME AND ADDRESS OF CONTRACTOR (No.. street, county, state, ZIP Code) I ( DE-AC04-00AL66620 10B. DATED (SEE ITEM 13) 2. AMENDMENTIMODIFICATION NO. M I 3 8 9A. AMENDMENT OF SOLICITATION NO. extended. 3. EFFECTIVE DATE See Block 16C CODE I FACILITY CODE Offers must acknowledge receipt of this amendment prior to the hour

  5. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT I I. CONT" ID CODE

    National Nuclear Security Administration (NNSA)

    CONT" ID CODE Babcock & Wilcox Technical Services Pantex, LLC I 1 98. DATED (SEE ITEM 11) PAGE I OF 2 PAGES Albuquerque, NM 87185-5400 I Amarillo, TX 79120 PO Box 30020 Amarillo, TX 79120 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) 10A. MODIFICATION OF CONTRACTIORDER NO. 2. AMENDMENTIMODIFICATION NO. MI64 9A. AMENDMENT OF SOLICITATION NO. DE-AC04-00AL66620 1 I IOB. DATED (SEE ITEM 13) 3. EFFECTIVE DATE See Block 16C Offers must acknowledge receipt of this

  6. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT I I. CONTRA'T ID CODE

    National Nuclear Security Administration (NNSA)

    CONTRA'T ID CODE BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, V A 24506 PAGE I OF 2 PAGES Albuquerque, NM 871 85-5400 / Amarillo, TX 79120 I I 9B. DATED (SEE ITEM 11) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) I 10A. MODIFICATION OF CONTRACTIORDER NO. 2. AMENDMENTIMODIFICATION NO. M I 0 8 9A. AMENDMENT OF SOLICITATION NO. DE-AC04-00AL66620 1 1 108. DATED (SEE ITEM 13) 3. EFFECTIVE DATE See Block 16C Offers must acknowledge receipt of this amendment prior to

  7. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTRACT ID PAGE I OF 2

    National Nuclear Security Administration (NNSA)

    / ' ID PAGE I OF 2 PAGES - . Albuquerque, NM 87185-5400 I Amarillo, TX 79120 I ( DE-AC04-00AL66620 10B. DATED (SEE ITEM 13) 8. NAME AND ADDRESS OF CONTRACTOR (No., street, county, state, ZIP Code) Babcock & W ~ ~ C O X Technical Services Pantex, LLC 800 Main Street Lynchburg, VA 24505 2 . AMENDMENTIMODIFICATION NO. MI50 9A. AMENDMENT OF SOLICITATION NO. 9B. DATED (SEE ITEM 11) 10A. MODIFICATION OF CONTRACTIORDER NO. Offers must acknowledge receipt of this amendment prior to the hour and date

  8. RASTtk: A modular and extensible implementation of the RAST algorithm for building custom annotation pipelines and annotating batches of genomes

    SciTech Connect (OSTI)

    Brettin, Thomas; Davis, James J.; Disz, Terry; Edwards, Robert A.; Gerdes, Svetlana; Olsen, Gary J.; Olson, Robert; Overbeek, Ross; Parrello, Bruce; Pusch, Gordon D.; Shukla, Maulik; Thomason, III, James A.; Stevens, Rick; Vonstein, Veronika; Wattam, Alice R.; Xia, Fangfang

    2015-02-10

    The RAST (Rapid Annotation using Subsystem Technology) annotation engine was built in 2008 to annotate bacterial and archaeal genomes. It works by offering a standard software pipeline for identifying genomic features (i.e., protein-encoding genes and RNA) and annotating their functions. Recently, in order to make RAST a more useful research tool and to keep pace with advancements in bioinformatics, it has become desirable to build a version of RAST that is both customizable and extensible. In this paper, we describe the RAST tool kit (RASTtk), a modular version of RAST that enables researchers to build custom annotation pipelines. RASTtk offers a choice of software for identifying and annotating genomic features as well as the ability to add custom features to an annotation job. RASTtk also accommodates the batch submission of genomes and the ability to customize annotation protocols for batch submissions. This is the first major software restructuring of RAST since its inception.

  9. Determination Of Reportable Radionuclides For DWPF Sludge Batch 7B (Macrobatch 9)

    SciTech Connect (OSTI)

    Crawford, C. L.; DiPrete, D. P.

    2013-08-22

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu-242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2011-0004; Rev. 0 entitled Sludge Batch 7b Qualification Studies. Specifically, this report details results from performing Subtask II, Item 2 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00247, Rev. 0 and Analytical Study Plan (ASP), SRNL-RP-2011-00248, Rev. 0. In order to determine the reportable radionuclides for SB7b (MB9), a list of radioisotopes that may meet the criteria as specified by the Department of Energys (DOE) WAPS was developed. All radioactive U-235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 27 radionuclides have been identified as reportable for DWPF SB7b as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100-year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB7b to 29. The radionuclide measurements made for SB7b are similar to those performed in the previous SB7a MB8 work. Some method development/refine

  10. DETERMINATION OF REPORTABLE RADIONUCLIDES FOR DWPF SLUDGE BATCH 7B (MACROBATCH 9)

    SciTech Connect (OSTI)

    Crawford, C. L.; Diprete, D. P.

    2014-05-01

    The Waste Acceptance Product Specifications (WAPS) 1.2 require that The Producer shall report the inventory of radionuclides (in Curies) that have half-lives longer than 10 years and that are, or will be, present in concentrations greater than 0.05 percent of the total inventory for each waste type indexed to the years 2015 and 3115. As part of the strategy to comply with WAPS 1.2, the Defense Waste Processing Facility (DWPF) will report for each waste type, all radionuclides (with half-lives greater than 10 years) that have concentrations greater than 0.01 percent of the total inventory from time of production through the 1100 year period from 2015 through 3115. The initial listing of radionuclides to be included is based on the design-basis glass as identified in the Waste Form Compliance Plan (WCP) and Waste Form Qualification Report (WQR). However, it is required that this list be expanded if other radionuclides with half-lives greater than 10 years are identified that may meet the greater than 0.01% criterion for Curie content. Specification 1.6 of the WAPS, International Atomic Energy Agency (IAEA) Safeguards Reporting for High Level Waste (HLW), requires that the ratio by weights of the following uranium and plutonium isotopes be reported: U-233, U-234, U-235, U-236, U-238, Pu-238, Pu-239, Pu-240, Pu-241, and Pu- 242. Therefore, the complete set of reportable radionuclides must also include this set of U and Pu isotopes. The DWPF is receiving radioactive sludge slurry from HLW Tank 40. The radioactive sludge slurry in Tank 40 is a blend of the heel from Sludge Batch 7a (SB7a) and Sludge Batch 7b (SB7b) that was transferred to Tank 40 from Tank 51. The blend of sludge in Tank 40 is also referred to as Macrobatch 9 (MB9). This report develops the list of reportable radionuclides and associated activities as a function of time. The DWPF will use this list and the activities as one of the inputs for the development of the Production Records that relate to radionuclide inventory. This work was initiated through Technical Task Request (TTR) HLW-DWPF-TTR-2011-0004; Rev. 0 entitled Sludge Batch 7b Qualification Studies. Specifically, this report details results from performing Subtask II, Item 2 of the TTR and, in part, meets Deliverable 6 of the TTR. The work was performed following the Task Technical and Quality Assurance Plan (TTQAP), SRNL-RP-2011-00247, Rev. 0 and Analytical Study Plan (ASP), SRNL-RP-2011-00248, Rev. 0. In order to determine the reportable radionuclides for SB7b (MB9), a list of radioisotopes that may meet the criteria as specified by the Department of Energys (DOE) WAPS was developed. All radioactive U- 235 fission products and all radioactive activation products that could be in the SRS HLW were considered. In addition, all U and Pu isotopes identified in WAPS 1.6 were included in the list. This list was then evaluated and some isotopes were excluded from the projection calculations. Based on measurements and analytical detection limits, 27 radionuclides have been identified as reportable for DWPF SB7b as specified by WAPS 1.2. The WCP and WQR require that all of the radionuclides present in the Design Basis glass be considered as the initial set of reportable radionuclides. For SB7b, all of the radionuclides in the Design Basis glass are reportable except for three radionuclides: Pd-107, Cs-135, and Th-230. At no time during the 1100- year period between 2015 and 3115 did any of these three radionuclides contribute to more than 0.01% of the radioactivity on a Curie basis. Two additional uranium isotopes (U-235 and -236) must be added to the list of reportable radionuclides in order to meet WAPS 1.6. All of the Pu isotopes (Pu-238, -239, -240, -241, and -242) and other U isotopes (U-233, -234, and -238) identified in WAPS 1.6 were already determined to be reportable according to WAPS 1.2 This brings the total number of reportable radionuclides for SB7b to 29. The radionuclide measurements made for SB7b are similar to those performed in the previous SB7a MB8 work. Some method development/ref

  11. The Building and Commissioning of the Batch Pyrolysis Plant in Studsvik, Sweden - 12447

    SciTech Connect (OSTI)

    Lindberg, Maria; Oesterberg, Carl; Vernersson, Thomas

    2012-07-01

    After a sequence of lab scale and bench scale trials the building of a pyrolysis plant could begin at the Studsvik site in Sweden. The facility is primarily aimed at treatment of uranium contaminated organic waste originating at fuel manufacturing plants and other facilities where the main contamination is uranium. The plant is an extension/addition to the already operating incinerator. In order to further widen the waste acceptance criteria the design of the off-gas treatment system does not have the same design as that of the incinerator. The building of the facility began in April 2011, and the first heating of the facility took place in late December, 2011. The site acceptance tests are planned for January, as are the first inactive trials aimed at optimisation of process control. The facility is planned to be operating with radioactive materials from February 2012. The pyrolysis unit is primarily aimed at treatment of uranium contaminated waste, under conditions that facilitate leaching and recovery of the uranium from the ashes. However, a number of other uses are conceivable. The batch fed pyrolysis unit, with its chosen design of the off-gas treatment system, enables treatment of some waste fractions that are difficult to treat in the incinerator. For instance small campaigns, i.e. smaller quantities of waste (typically <5 tonnes), or waste containing high levels of chlorine and sulphur are possible to treat in the pyrolysis unit. The pyrolysis unit is also expected to perform well in the treatment of other 'difficult' waste fractions, for instance waste containing pyrophoric materials, or other types of waste that benefit from the high level of process control, i.e. control of temperature and atmosphere throughout the process, that can be obtained in the pyrolysis unit compared to the incinerator. Furthermore, treatment in the pyrolysis unit minimises the risk of cross contamination between different waste treatment campaigns. This feature is obtained thanks to the low gas flow rates in the vessel, which means that a higher retention of nuclides in the ashes is obtained, but also through a design that facilitates cleaning of the pyrolysis vessel and the system beyond this, or even exchanging the most critical components, such as the pyrolysis vessel itself, if need be. (authors)

  12. AMENDMENT OF SOLIr ATI ON/MODIFI CATION OF CONTRACT 1. CONTRACT ID CODE PAGE OF PAGES

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

    SOLIr ATI ON/MODIFI CATION OF CONTRACT 1. CONTRACT ID CODE PAGE OF PAGES 2 AMENDMENT/lIVDDIFICATiON NC 3. EFFECTIVE DATE [4 REDUISITION/PURCHASE REC NO IE PR3JECT NC (if applicable) 09 ISoe Bloo , 16- - ISee Soheoule S ISSUED D> CODE 7 ~ ADMINISTERED BY (if otnertrian ItemS CO DE Of fice of Ri-.er PoDLecOLODn office of Riv'er P-oCQ-ec-.iQ .S. Cet:F O<men of E-nerov,, I.S. Deparo:merio c-' Enrgv P.O. Box 4'5C 0 ... Box 45C .io ao 1 31 W YS: (-876 B. NAME AND ADDRESS CF CONTRACTOR (No seve

  13. Sludge Washing And Demonstration Of The DWPF Flowsheet In The SRNL Shielded Cells For Sludge Batch 8 Qualification

    SciTech Connect (OSTI)

    Pareizs, J. M.; Crawford, C. L.

    2013-04-26

    The current Waste Solidification Engineering (WSE) practice is to prepare sludge batches in Tank 51 by transferring sludge from other tanks to Tank 51. Tank 51 sludge is washed and transferred to Tank 40, the current Defense Waste Processing Facility (DWPF) feed tank. Prior to transfer of Tank 51 to Tank 40, the Savannah River National Laboratory (SRNL) typically simulates the Tank Farm and DWPF processes using a Tank 51 sample (referred to as the qualification sample). WSE requested the SRNL to perform characterization on a Sludge Batch 8 (SB8) sample and demonstrate the DWPF flowsheet in the SRNL shielded cells for SB8 as the final qualification process required prior to SB8 transfer from Tank 51 to Tank 40. A 3-L sample from Tank 51 (the SB8 qualification sample; Tank Farm sample HTF-51-12-80) was received by SRNL on September 20, 2012. The as-received sample was characterized prior to being washed. The washed material was further characterized and used as the material for the DWPF process simulation including a Sludge Receipt and Adjustment Tank (SRAT) cycle, a Slurry Mix Evaporator (SME) cycle, and glass fabrication and chemical durability measurements.

  14. RASTtk: A modular and extensible implementation of the RAST algorithm for building custom annotation pipelines and annotating batches of genomes

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

    Brettin, Thomas; Davis, James J.; Disz, Terry; Edwards, Robert A.; Gerdes, Svetlana; Olsen, Gary J.; Olson, Robert; Overbeek, Ross; Parrello, Bruce; Pusch, Gordon D.; et al

    2015-02-10

    The RAST (Rapid Annotation using Subsystem Technology) annotation engine was built in 2008 to annotate bacterial and archaeal genomes. It works by offering a standard software pipeline for identifying genomic features (i.e., protein-encoding genes and RNA) and annotating their functions. Recently, in order to make RAST a more useful research tool and to keep pace with advancements in bioinformatics, it has become desirable to build a version of RAST that is both customizable and extensible. In this paper, we describe the RAST tool kit (RASTtk), a modular version of RAST that enables researchers to build custom annotation pipelines. RASTtk offersmore » a choice of software for identifying and annotating genomic features as well as the ability to add custom features to an annotation job. RASTtk also accommodates the batch submission of genomes and the ability to customize annotation protocols for batch submissions. This is the first major software restructuring of RAST since its inception.« less

  15. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 6 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J.; Pickenheim, B.; Bannochie, C.; Billings, A.; Bibler, N.; Click, D.

    2010-10-01

    Prior to initiating a new sludge batch in the Defense Waste Processing Facility (DWPF), Savannah River National Laboratory (SRNL) is required to simulate this processing, including Chemical Process Cell (CPC) simulation, waste glass fabrication, and chemical durability testing. This report documents this simulation for the next sludge batch, Sludge Batch 6 (SB6). SB6 consists of Tank 12 material that has been transferred to Tank 51 and subjected to Low Temperature Aluminum Dissolution (LTAD), Tank 4 sludge, and H-Canyon Pu solutions. Following LTAD and the Tank 4 addition, Liquid Waste Operations (LWO) provided SRNL a 3 L sample of Tank 51 sludge for SB6 qualification. Pu solution from H Canyon was also received. SB6 qualification included washing the sample per LWO plans/projections (including the addition of Pu from H Canyon), DWPF CPC simulations, waste glass fabrication (vitrification), and waste glass characterization and chemical durability evaluation. The following are significant observations from this demonstration. Sludge settling improved slightly as the sludge was washed. SRNL recommended (and the Tank Farm implemented) one less wash based on evaluations of Tank 40 heel projections and projections of the glass composition following transfer of Tank 51 to Tank 40. Thorium was detected in significant quantities (>0.1 wt % of total solids) in the sludge. In past sludge batches, thorium has been determined by Inductively Coupled Plasma-Mass Spectroscopy (ICP-MS), seen in small quantities, and reported with the radionuclides. As a result of the high thorium, SRNL-AD has added thorium to their suite of Inductively Coupled Plasma-Atomic Emission Spectroscopy (ICP-AES) elements. The acid stoichiometry for the DWPF Sludge Receipt and Adjustment Tank (SRAT) processing of 115%, or 1.3 mol acid per liter of SRAT receipt slurry, was adequate to accomplish some of the goals of SRAT processing: nitrite was destroyed to below 1,000 mg/kg and mercury was removed to below the DWPF target with 750 g of steam per g of mercury. However, rheological properties did not improve and were above the design basis. Hydrogen generation rates did not exceed DWPF limits during the SRAT and Slurry Mix Evaporator (SME) cycles. However, hydrogen generation during the SRAT cycle approached the DWPF limit. The glass fabricated with the Tank 51 SB6 SME product and Frit 418 was acceptable with respect to chemical durability as measured by the Product Consistency Test (PCT). The PCT response was also predictable by the current durability models of the DWPF Product Composition Control System (PCCS). It should be noted, however, that in the first attempt to make glass from the SME product, the contents of the fabrication crucible foamed over. This may be a result of the SME product's REDOX (Reduction/Oxidation - Fe{sup 2+}/{Sigma}Fe) of 0.08 (calculated from SME product analytical results). The following are recommendations drawn from this demonstration. In this demonstration, at the request of DWPF, SRNL caustic boiled the SRAT contents prior to acid addition to remove water (to increase solids concentration). During the nearly five hours of caustic boiling, 700 ppm of antifoam was required to control foaming. SRNL recommends that DWPF not caustic boil/concentrate SRAT receipt prior to acid addition until further studies can be performed to provide a better foaming control strategy or a new antifoam is developed for caustic boiling. Based on this set of runs and a recently completed demonstration with the SB6 Waste Acceptance Product Specifications (WAPS) sample, it is recommended that DWPF not add formic acid at the design addition rate of two gallons per minute for this sludge batch. A longer acid addition time appears to be helpful in allowing slower reaction of formic acid with the sludge and possibly decreases the chance of a foam over during acid addition.

  16. Hydrogen Evolution and Sludge Suspension During the Preparation of the First Batch of Sludge at the Savannah River Site

    SciTech Connect (OSTI)

    Hay, M.S.; Lee, E.D.

    1995-03-01

    The first batch of High Level Radioactive Sludge for the Defense Waste Processing Facility is being prepared in two 4.9 million liter waste tanks. The preparation involves removing water soluble salts by washing (water addition, sludge suspension, settling and decantation). Sludge suspension is accomplished using long shafted slurry pumps that are mounted on rotating turntables. During the sludge suspension runs in 1993 and 1994, the slurry pumps` cleaning radius was determined to be less than that expected from previous determinations using synthetic sludge in a full size waste tank mockup. Hydrogen concentrations in the tanks` vapor space were monitored during the sludge suspension activities. As expected, the initial agitation of the sludge increased the hydrogen concentration, however, with the controls in place the hydrogen concentration was maintained below seven percent of the lower flammability limit

  17. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 1, 2, AND 3 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-29

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 1, 2, and 3 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  18. CRC DEPLETION CALCULATIONS FOR THE RODDED ASSEMBLIES IN BATCHES 1, 2, 3, AND 1X OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-09-03

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain rodded fuel assemblies from batches 1, 2, 3, and 1X of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for Commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A rodded assembly is one that contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) for some period of time during its irradiation history. The objective of this analysis is to provide SAS2H calculated isotopic compositions of depleted fuel and depleted burnable poison for each fuel assembly to be used in subsequent CRC reactivity calculations containing the fuel assemblies.

  19. CRC DEPLETION CALCULATIONS FOR THE NON-RODDED ASSEMBLIES IN BATCHES 4 AND 5 OF CRYSTAL RIVER UNIT 3

    SciTech Connect (OSTI)

    Kenneth D. Wright

    1997-07-30

    The purpose of this design analysis is to document the SAS2H depletion calculations of certain non-rodded fuel assemblies from batches 4 and 5 of the Crystal River Unit 3 pressurized water reactor (PWR) that are required for commercial Reactor Critical (CRC) evaluations to support the development of the disposal criticality methodology. A non-rodded assembly is one which never contains a control rod assembly (CRA) or an axial power shaping rod assembly (APSRA) during its irradiation history. The objective of this analysis is to provide SAS2H generated isotopic compositions for each fuel assembly's depleted fuel and depleted burnable poison materials. These SAS2H generated isotopic compositions are acceptable for use in CRC benchmark reactivity calculations containing the various fuel assemblies.

  20. Coal fly ash interaction with environmental fluids: Geochemical and strontium isotope results from combined column and batch leaching experiments

    SciTech Connect (OSTI)

    Brubaker, Tonya M.; Stewart, Brian W.; Capo, Rosemary C.; Schroeder, Karl T.; Chapman, Elizabeth C.; Spivak-Birndorf, Lev J.; Vesper, Dorothy J.; Cardone, Carol R.; Rohar, Paul C.

    2013-05-01

    The major element and Sr isotope systematics and geochemistry of coal fly ash and its interactions with environmental waters were investigated using laboratory flow-through column leaching experiments (sodium carbonate, acetic acid, nitric acid) and sequential batch leaching experiments (water, acetic acid, hydrochloric acid). Column leaching of Class F fly ash samples shows rapid release of most major elements early in the leaching procedure, suggesting an association of these elements with soluble and surface bound phases. Delayed release of certain elements (e.g., Al, Fe, Si) signals gradual dissolution of more resistant silicate or glass phases as leaching continues. Strontium isotope results from both column and batch leaching experiments show a marked increase in {sup 87}Sr/{sup 86}Sr ratio with continued leaching, yielding a total range of values from 0.7107 to 0.7138. For comparison, the isotopic composition of fluid output from a fly ash impoundment in West Virginia falls in a narrow range around 0.7124. The experimental data suggest the presence of a more resistant, highly radiogenic silicate phase that survives the combustion process and is leached after the more soluble minerals are removed. Strontium isotopic homogenization of minerals in coal does not always occur during the combustion process, despite the high temperatures encountered in the boiler. Early-released Sr tends to be isotopically uniform; thus the Sr isotopic composition of fly ash could be distinguishable from other sources and is a useful tool for quantifying the possible contribution of fly ash leaching to the total dissolved load in natural surface and ground waters.

  1. SUMMARY REPORT FOR THE ANALYSIS OF THE SLUDGE BATCH 7A (MACROBATCH 8) DWPF POUR STREAM GLASS SAMPLE FOR CANISTER S03619

    SciTech Connect (OSTI)

    Johnson, F.

    2012-05-01

    In order to comply with the Waste Acceptance Specifications in Sludge Batch 7a (Macrobatch 8), Savannah River National Laboratory personnel characterized the Defense Waste Processing Facility (DWPF) pour stream glass sample collected while filling canister S03619. This report summarizes the results of the compositional analysis for reportable oxides and radionuclides, and the normalized Product Consistency Test (PCT) results. The PCT responses indicate that the DWPF produced glass that is significantly more durable than the Environmental Assessment glass. Results and further details are documented in 'Analysis of DWPF Sludge Batch 7a (Macrobatch 8) Pour Stream Samples,' SRNL-STI-2012-00017.

  2. YEAR","MONTH","STATE","UTILITY_ID","UTILITY_NAME","RESIDENTIAL_GP REVENUES (Tho

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

    UTILITY_ID","UTILITY_NAME","RESIDENTIAL_GP REVENUES (Thousand $)","COMMERCIAL_GP REVENUES (Thousand $)","INDUSTRIAL_GP REVENUES (Thousand $)","TRANS_GP REVENUES (Thousand $)","TOTAL_GP REVENUES (Thousand $)","RESIDENTIAL_GP SALES (MWh)","COMMERCIAL_GP SALES (MWh)","INDUSTRIAL_GP SALES (MWh)","TRANS_GP SALES (MWh)","TOTAL_GP SALES (MWh)","RESIDENTIAL_GP

  3. DOE/ID-Number

    Office of Environmental Management (EM)

    Affecting Performance of a Salt Repository for Disposal of Heat-Generating Nuclear Waste Prepared for U.S. Department of Energy Used Nuclear Fuel S. David Sevougian, SNL Geoff...

  4. 2-ID-E

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    General Users. For example, in collaboration with G. Woloschak et al, we have looked at TiO2-DNA nanocomposites in mammalian cells 1; B. Twining et al investigate trace elements...

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    storage, conveying systems and a pellet 110 pulverizer to insure that the appropriate recipe of material enters the throat of the conversion reactor in the appropriate blends and...

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    Signage and Posting Guidelines CAES is a destination point for world-renowned researchers, private industry partners, politicians, CAES patrons and other dignitaries. For this...

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    INEELEXT-04-02423 ABB SCADAEMS System INEEL Baseline Summary Test Report J. R. Davidson ... SCADAEMS System INEEL Baseline Summary Test Report J. R. Davidson M. R. Permann B. L. ...

  8. Beamline 29-ID

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    eV Energy resolution: 1.8 meV, Angular resolution: 0.01 6-axis cryomanipulator Polar Rotation: 180 Tilt Rotation:-10 to 35 Azimutal Rotation: 45 Temperature: 800-10K...

  9. acceptable-ID.pdf

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  10. Beamline 29-ID

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    sided bounce Mirror (M1) 31.3 m Heat-sink, side bounce Monochromater (M2, LEG, MEG, HEG) 39.7 m In-Focus VLS-PGM Exit Slit 59.7 m Both RSXS and ARPES branchlines Mirror...

  11. DOE/ID-Number

    Energy Savers [EERE]

    ... 21, 2015 ACRONYMS ASME B&PVC American Society of Mechanical Engineers Boiler and Pressure Vessel Code ASTM American Society for Testing and Materials CISCC Chloride Induced ...

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    Foreign national guests and employees must have an approved visit and present a valid passport and documentation of US legal status and work authorizations. Official visitors are...

  13. ID.pdf

    Energy Savers [EERE]

  14. Beamline 29-ID

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    Lab, APS) Christa Benson Dr. Jonathan Lang Dr. Jessica McChesney Dr. Mohan Ramanathan Dr. Ruben Reininger Dr. Richard Rosenberg Dr. George Srajer IEX - Advisory Committee Dr Dario...

  15. Blind Modal ID

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    high-resolution visualization and analysis of structural dynamics. Contact Yongchao Yang (832) 335-3003 Email David Mascarenas dmascarenas@lanl.gov (505) 665-0881 Original...

  16. Beamline 29-ID

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    Resonant Soft X-ray Scattering (RSXS) Diffractometer: 7-axes "kappa" geometry 10 K closed-cycle cryostat Detectors: Microchannel plate, area detector Electron yield detector TES...

  17. DOE/ID-Number

    Office of Scientific and Technical Information (OSTI)

    M. J. Robinson Pacific Northwest National Laboratory September 2012 FCRD-SWF-2012-000214 DISCLAIMER This information was prepared as an account of work sponsored by an agency of...

  18. DOE/ID-Number

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    A Summary of Control System Security Standards Activities in the Energy Sector October 2005 National SCADA Test Bed A Summary of Control System Security Standards Activities in the Energy Sector October 2005 Sandia National Laboratories Idaho National Laboratory Argonne National Laboratory Pacific Northwest National Laboratory Prepared for the U.S. Department of Energy Office of Electricity Delivery and Energy Reliability 2 iii ABSTRACT This document is a compilation of the activities and

  19. Beamline 29-ID

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    component; implementation of beamline controls and safety systems (cleanroom, FOE progress, FOE progress2) Fall 2012 FDR approval (October 15) Installation of...

  20. DOE/ID-Number

    Office of Environmental Management (EM)

    data from short-term tests. To collect the necessary data as part of the R&D program and engineering-scale demonstration, more effective monitoring systems must be developed to...

  1. DOE/ID-Number

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    production of a range of liquid fuels and fuel blendstocks from lignocellulosic biomass feedstocks by funding fundamental and applied research that advances the state of...

  2. DOE/ID-Number

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    non-industrial private forest land who wish to establish, produce, and deliver biomass feedstocks. It provides two categories of assistance: (1) Matching payments may be...

  3. ID-2011-01526

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

  4. DOE/ID-Number

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

    Used Fuel Disposal in Crystalline Rocks: Status and FY14 Progress Prepared for U.S. Department of Energy Used Fuel Disposition Y. Wang, E. Matteo Sandia National Laboratories J. Rutqvist, J. Davis, L. Zheng, J. Houseworth, J. Birkholzer Lawrence Berkeley National Laboratory T. Dittrich, C. W. Gable, S. Karra, N. Makedonska, S. Chu, D. Harp, S. L. Painter, P. Reimus, F. Perry Los Alamos National Laboratory P. Zhao, J. Begg, M. Zavarin, S. J. Tumey, Z. Dai, A. B. Kersting Lawrence Livermore

  5. DOE/ID-Number

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

    10 FY14 Status Report: CIRFT Testing Results on High Burnup UNF Prepared for US Department of Energy Used Fuel Disposition Campaign J.-A. Wang, H. Wang, and H. Jiang B. B. Bevard and R. L. Howard Oak Ridge National Laboratory September 2014 M2-FCRD-UFD-2014-000053 DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be

  6. 11. CONTRACT ID CODE

    National Nuclear Security Administration (NNSA)

    1 PAGE 1 OF2 AMENDMENT OF SOLICITATION/MODIFICATION OF CONTRACT PAGES 2. AMENDMENT/MODIFICATION NO. I 3. EFFECTIVE DATE M191 See Block 16C 4. REQUISITION/PURCHASE I 5. PROJECT NO. (If applicable) REQ. NO. 6.ISSUED BY CODE U.S. Department of Energy National Nuclear Security Administration Service Center Property and M&O Contract Support Department P.O. Box 5400 Albuquerque, NM 87185-5400 7. ADMINISTERED BY (If other than Item 6) CODE U.S. Department of Energy National Nuclear Security

  7. DOE/ID-Number

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

    ... Clean Air Act (CAA): The Federal Clean Air Act (CAA) is the basis for the national air pollution control effort. Basic elements of the act include standards for major air ...

  8. DOE/ID-Number

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

    ... Clean Air Act (CAA): The Federal Clean Air Act, or -CAA, is the basis for the national air pollution control effort. Basic elements of the act include national ambient air ...

  9. ID@Work

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

    Engineer, Overseer of the SMC Program 1.4 minutes, (5.7 MB) 2009, August Melissa Bates, Engineer, Monitor of the Nuclear Hydrogen Initiative AFC R&D Separations 2 minutes,...

  10. DOE/ID-Number

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

    ... if all metal cladding were to react (5) Minimal H reaction rate Power uprates 3411 MWt - ... This results in a minimal impact on facility design for the later stages; the main impact ...

  11. DOE/ID-Number

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

    ... Shapiro. 1983. "Effects of Public Opinion on Policy." ... American Journal of Political Science 29(4):871-890. Sabatier, ... things that can be risks to people's health or safety. ...

  12. DOE/ID-Number

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

    ... Paris, France: Organization for Economic Cooperation ... Scale", International Journal of Rock Mechanics & Mining Sciences 38: 859 - ... Impact Statement, Management of Commercially ...

  13. DOE/ID-Number

    Office of Environmental Management (EM)

    Disposal Options for Research and Development for Spent Nuclear Fuel and High Basis for Identification of Disposal Options for Research and Development for Spent Nuclear Fuel and High-Level Waste Prepared for U.S. Department of Energy Used Fuel Disposition Campaign Rob P. Rechard Barry Goldstein Larry H. Brush Sandia National Laboratories James A. Blink Mark Sutton Lawrence Livermore National Laboratory Frank V. Perry Los Alamos National Laboratory March FCRD-USED-2011-0000 asis for

  14. DOE/ID-Number

    Office of Environmental Management (EM)

    Results of Stainless Steel Canister Corrosion Studies and Environmental Sample Investigations Prepared for U.S. Department of Energy Used Fuel Disposition Program Charles Bryan and David Enos Sandia National Laboratories September 25, 2014 FCRD-UFD-2014-000055 SAND2014-20347 O Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National Nuclear Security

  15. DOE/ID-Number

    Office of Environmental Management (EM)

    Status report: Characterization of Weld Residual Stresses on a Full- Diameter SNF Interim Storage Canister Mockup Prepared for U.S. Department of Energy Used Fuel Disposition Program D.G. Enos and C.R. Bryan Sandia National Laboratories August 21, 2015 FCRD-UFD-2015-00123 SAND2015-7068 R Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned subsidiary of Lockheed Martin Corporation, for the U.S. Department of Energy's National

  16. DOE/ID-Number

    Office of Environmental Management (EM)

    Used Fuel Disposal in Crystalline Rocks: FY15 Progress Report Prepared for U.S. Department of Energy Used Fuel Disposition Y. Wang, T. Hadgu, E. Matteo, J. N. Kruichak, M. M. Mills Sandia National Laboratories R. Tinnacher, J. Davis Lawrence Berkeley National Laboratory H. Viswanathan, S. Chu, T. Dittrich, F. Hyman, S. Karra, N. Makedonska, P. Reimus Los Alamos National Laboratory M. Zavarin, P. Zhao, C. Joseph, J. Begg, Z. Dai, A. B. Kersting Lawrence Livermore National Laboratory J. Jerden, J.

  17. DOE/ID-Number

    Office of Environmental Management (EM)

    INEEL/EXT-04-02423 ABB SCADA/EMS System INEEL Baseline Summary Test Report J. R. Davidson M. R. Permann B. L. Rolston S. J. Schaeffer November 2004 Prepared by: Idaho National Engineering and Environmental Laboratory INEEL/EXT-04-02423 ABB SCADA/EMS System INEEL Baseline Summary Test Report J. R. Davidson M. R. Permann B. L. Rolston S. J. Schaeffer November 2004 Idaho National Engineering and Environmental Laboratory INEEL National Security Division Idaho Falls, Idaho 83415 Prepared for the U.S.

  18. DOE/ID-Number

    Office of Environmental Management (EM)

    Public Preferences Related to Consent-Based Siting of Radioactive Waste Management Facilities for Storage and Disposal: Analyzing Variations over Time, Events, and Program Designs Prepared for US Department of Energy Nuclear Fuel Storage and Transportation Planning Project Hank C. Jenkins-Smith Carol L. Silva Kerry G. Herron Kuhika G. Ripberger Matthew Nowlin Joseph Ripberger Center for Risk and Crisis Management, University of Oklahoma Evaristo "Tito" Bonano Rob P. Rechard Sandia

  19. DOE/ID-Number

    Office of Environmental Management (EM)

    INL/EXT-08-13979 U.S. Department of Energy Office of Electricity Delivery and Energy Reliability Enhancing control systems security in the energy sector NSTB National SCADA Test Bed Common Cyber Security Vulnerabilities Observed in Control System Assessments by the INL NSTB Program November 2008 November 2008 INL/EXT-08-13979 Common Cyber Security Vulnerabilities Observed in Control System Assessments by the INL NSTB Program November 2008 Idaho National Laboratory Idaho Falls, Idaho 83415

  20. DOE/ID-Number

    Office of Environmental Management (EM)

    Recommended Practices Guide For Securing ZigBee Wireless Networks in Process Control System Environments Draft April 2007 Author Ken Masica Lawrence Livermore National Laboratory Ken Masica page 1 LLNL Recommended Practices Guide Securing ZigBee Wireless Networks in Process Control System Environments ( D R A F T ) Ken Masica Vulnerability & Risk Assessment Program (VRAP) Lawrence Livermore National Laboratory (LLNL) for DHS US CERT Control Systems Security Program (CSSP) April 2007 This

  1. PROJECT NAME/ID",,,"Jobs figures to report",,"October 2010 Report",,"January 201

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

    PROJECT NAME/ID",,,"Jobs figures to report",,"October 2010 Report",,"January 2011 Report",,"April 2011 Report",,"July 2011 Report",,"October 2011 Report",,"January 2012 Report",,"April 2012 Report" ,,,,"Recovery Act FTEs are reported to OMB quarterly via FederalReporting.gov. Recovery Act hours worked are reported quarterly to DOE via PAGE.",,"To OMB (FTEs)",,"To OMB

  2. AMENDMENT OF SOLlClTATlONlMODlFlCATlON OF CONTFWCT I 1 CONTRACT ID CODE PAGE I OF 2

    National Nuclear Security Administration (NNSA)

    CONTFWCT I 1 CONTRACT ID CODE PAGE I OF 2 PAGES MI10 I See Block 16C I REQ. NO. BWXT Pantex, LLC Route 726, Mt. Athos Road Lynchburg, VA 24506 2. AMENDMENTIMODIFICATION NO. 1 3. EFFECTIVE DATE 1 4. REQUISITIONIPURCHASE 1 5. PROJECT NO. (If a ~ ~ l i c a b l e l . a , U.S. Department of Energy National Nuclear Security Administration Service Center Property and M&O Contract Support Department P.O. Box 5400 Albuquerque, NM 871 85-5400 96. DATED (SEE ITEM 1 1 ) 6. ISSUED BY CODE 1 7.

  3. Parallel Batch Scripts

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

    parallel environments. Basic Parallel Example If your job requires the default 5GB of memory per slot, you can do the following: binbash Set SGE options: -- ensure...

  4. Batch Strategies for Maximizing

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

    u s t he b atch s ystem t o run

  5. Batch Strategies for Maximizing

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

    t o u se t he b atch s ystem to r un

  6. Batch Script Examples

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

    are correct before submitting more complicated jobs. First, copy the contents of hello.sh into a file. genepool% cat hello.sh binbash sleep 120 echo "Hello World" Then...

  7. Submitting Batch Jobs

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

    Verify the aprun job-launch command (similar to the MPICH mpirun command) arguments -N matches the Torque directive mppnppn. Submit the job using the qsub command. For example,...

  8. Example Batch Scripts

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

    such multiple serial jobs: Using the "serial" queue Using TaskFarmer Using CCM Using Python Using MPI to Make an Embarassingly Parallel Code In the examples below, we assume that...

  9. Submitting Batch Jobs

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

    such multiple serial jobs: Using the Serial Queue Using pbsdsh Using taskfarmer Using Python Using MPI to Make an Embarassingly Parallel Code In the examples below, we assume that...

  10. Example batch scripts

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

    Type: The only type currently available is typescratch. binbash SBATCH -p debug SBATCH -N 1 SBATCH -t 00:15:00 DW jobdw capacity10GB accessmodestriped...

  11. Example Batch Scripts

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

    therefore the job running on 64 nodes below uses 2048 cores: binbash -l SBATCH -p debug SBATCH -N 64 SBATCH -t 00:20:00 SBATCH -J myjob srun -n 2048 .mycode.exe Below is...

  12. Running Interactive Batch Jobs

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

    if the node of choice is not immediately available Start an interactive session in the debug queue qsh -l debug1 -now no qlogin -l debug1 -now no This is useful when the cluster...

  13. SLUDGE BATCH 5 ACCEPTANCE EVALUATION RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB5 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C; Ned Bibler, N; David Diprete, D

    2008-07-28

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Five (SB5) for processing in the Defense Waste Processing Facility (DWPF). Part of this SB5 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40 to complete the formation of SB5. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB4. The radionuclide concentrations were measured or estimated in the Tank 51 SB5 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry taken on March 21, 2008. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under direction of the Liquid Waste Organization it was then modified by five washes, six decants, an addition of Pu/Be from Canyon Tank 16.4, and an addition of NaNO2. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Ta Determining the radionuclide concentrations in this Tank 51 SB5 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2008-0010. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task 2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task 5) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB5 will be taken and transferred to SRNL for measurement of these radionuclides. Data presented in this report represents the measured or estimated radionuclide concentrations obtained from several standard and special analytical methods performed by Analytical Development (AD) personnel within SRNL. The method for I-129 measurement in sludge is described in detail. Most of these methods were performed on solutions resulting from the dissolutions of the slurry samples. Concentrations are given for twenty-nine radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 98% of the Tc-99 and 92% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  14. SLUDGE BATCH 6 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB6 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Bannochie, C.; Bibler, N.; Diprete, D.

    2010-05-21

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Six (SB6) for processing in the Defense Waste Processing Facility (DWPF). The SB6 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB5. The radionuclide concentrations were measured or estimated in the Tank 51 SB6 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter sample of Tank 51 sludge slurry (HTF-51-09-110) taken on October 8, 2009. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. Under the direction of the Liquid Waste Organization it was then modified by eight washes, nine decants, an addition of Pu from Canyon Tank 16.3, and an addition of NaNO{sub 2}. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB6 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2009-0014. The work with this qualification sample is covered by a Task Technical and Quality Assurance Plan and an Analytical Study Plan. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task II.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB6 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB6 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. The sample is the same as that on which the chemical composition was reported. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated. Results also indicate that 99% of the Tc-99 and at least 90% of the I-129 that could have been in this sludge batch have been removed by chemical processing steps in the SRS Canyons or Tank Farm.

  15. SLUDGE WASHING AND DEMONSTRATION OF THE DWPF FLOWSHEET IN THE SRNL SHIELDED CELLS FOR SLUDGE BATCH 5 QUALIFICATION

    SciTech Connect (OSTI)

    Pareizs, J; Cj Bannochie, C; Damon Click, D; Dan Lambert, D; Michael Stone, M; Bradley Pickenheim, B; Amanda Billings, A; Ned Bibler, N

    2008-11-10

    Sludge Batch 5 (SB5) is predominantly a combination of H-modified (HM) sludge from Tank 11 that underwent aluminum dissolution in late 2007 to reduce the total mass of sludge solids and aluminum being fed to the Defense Waste Processing Facility (DWPF) and Purex sludge transferred from Tank 7. Following aluminum dissolution, the addition of Tank 7 sludge and excess Pu to Tank 51, Liquid Waste Operations (LWO) provided the Savannah River National Laboratory (SRNL) a 3-L sample of Tank 51 sludge for SB5 qualification. SB5 qualification included washing the sample per LWO plans/projections (including the addition of a Pu/Be stream from H Canyon), DWPF Chemical Process Cell (CPC) simulations, waste glass fabrication (vitrification), and waste glass chemical durability evaluation. This report documents: (1) The washing (addition of water to dilute the sludge supernatant) and concentration (decanting of supernatant) of the Tank 51 qualification sample to adjust sodium content and weight percent insoluble solids to Tank Farm projections. (2) The performance of a DWPF CPC simulation using the washed Tank 51 sample. This includes a Sludge Receipt and Adjustment Tank (SRAT) cycle, where acid is added to the sludge to destroy nitrite and remove mercury, and a Slurry Mix Evaporator (SME) cycle, where glass frit is added to the sludge in preparation for vitrification. The SME cycle also included replication of five canister decontamination additions and concentrations. Processing parameters for the CPC processing were based on work with a non radioactive simulant. (3) Vitrification of a portion of the SME product and Product Consistency Test (PCT) evaluation of the resulting glass. (4) Rheology measurements of the initial slurry samples and samples after each phase of CPC processing. This work is controlled by a Task Technical and Quality Assurance Plan (TTQAP) , and analyses are guided by an Analytical Study Plan. This work is Technical Baseline Research and Development (R&D) for the DWPF.

  16. Early-warning process/control for anaerobic digestion and biological nitrogen transformation processes: Batch, semi-continuous, and/or chemostat experiments. Final report

    SciTech Connect (OSTI)

    Hickey, R.

    1992-09-01

    The objective of this project was to develop and test an early-warning/process control model for anaerobic sludge digestion (AD). The approach was to use batch and semi-continuously fed systems and to assemble system parameter data on a real-time basis. Specific goals were to produce a real-time early warning control model and computer code, tested for internal and external validity; to determine the minimum rate of data collection for maximum lag time to predict failure with a prescribed accuracy and confidence in the prediction; and to determine and characterize any trends in the real-time data collected in response to particular perturbations to feedstock quality. Trends in the response of trace gases carbon monoxide and hydrogen in batch experiments, were found to depend on toxicant type. For example, these trace gases respond differently for organic substances vs. heavy metals. In both batch and semi-continuously feed experiments, increased organic loading lead to proportionate increases in gas production rates as well as increases in CO and H{sub 2} concentration. An analysis of variance of gas parameters confirmed that CO was the most sensitive indicator variable by virtue of its relatively larger variance compared to the others. The other parameters evaluated including gas production, methane production, hydrogen, carbon monoxide, carbon dioxide and methane concentration. In addition, a relationship was hypothesized between gaseous CO concentration and acetate concentrations in the digester. The data from semicontinuous feed experiments were supportive.

  17. Towards the Integration of Dark- and Photo-Fermentative Waste Treatment. 4. Repeated Batch Sequential Dark- and Photofermentation using Starch as Substrate

    SciTech Connect (OSTI)

    Laurinavichene, T. V.; Belokopytov, B. F.; Laurinavichius, K. S.; Khusnutdinova, A. N.; Seibert, M.; Tsygankov, A. A.

    2012-05-01

    In this study we demonstrated the technical feasibility of a prolonged, sequential two-stage integrated process under a repeated batch mode of starch fermentation. In this durable scheme, the photobioreactor with purple bacteria in the second stage was fed directly with dark culture from the first stage without centrifugation, filtration, or sterilization (not demonstrated previously). After preliminary optimization, both the dark- and the photo-stages were performed under repeated batch modes with different process parameters. Continuous H{sub 2} production in this system was observed at a H{sub 2} yield of up to 1.4 and 3.9 mole mole{sup -1} hexose during the dark- and photo-stage, respectively (for a total of 5.3 mole mole{sup -1} hexose), and rates of 0.9 and 0.5 L L{sup -1} d{sup -1}, respectively. Prolonged repeated batch H{sub 2} production was maintained for up to 90 days in each stage and was rather stable under non-aseptic conditions. Potential for improvements in these results are discussed.

  18. Integration of the Uncertainties of Anion and TOC Measurements into the Flammability Control Strategy for Sludge Batch 8 at the DWPF

    SciTech Connect (OSTI)

    Edwards, T. B.

    2013-03-14

    The Savannah River National Laboratory (SRNL) has been working with the Savannah River Remediation (SRR) Defense Waste Processing Facility (DWPF) in the development and implementation of a flammability control strategy for DWPFs melter operation during the processing of Sludge Batch 8 (SB8). SRNLs support has been in response to technical task requests that have been made by SRRs Waste Solidification Engineering (WSE) organization. The flammability control strategy relies on measurements that are performed on Slurry Mix Evaporator (SME) samples by the DWPF Laboratory. Measurements of nitrate, oxalate, formate, and total organic carbon (TOC) standards generated by the DWPF Laboratory are presented in this report, and an evaluation of the uncertainties of these measurements is provided. The impact of the uncertainties of these measurements on DWPFs strategy for controlling melter flammability also is evaluated. The strategy includes monitoring each SME batch for its nitrate content and its TOC content relative to the nitrate content and relative to the antifoam additions made during the preparation of the SME batch. A linearized approach for monitoring the relationship between TOC and nitrate is developed, equations are provided that integrate the measurement uncertainties into the flammability control strategy, and sample calculations for these equations are shown to illustrate the impact of the uncertainties on the flammability control strategy.

  19. SLUDGE BATCH 7 ACCEPTANCE EVALUATION: RADIONUCLIDE CONCENTRATIONS IN TANK 51 SB7 QUALIFICATION SAMPLE PREPARED AT SRNL

    SciTech Connect (OSTI)

    Pareizs, J.; Hay, M.

    2011-02-22

    Presented in this report are radionuclide concentrations required as part of the program of qualifying Sludge Batch Seven (SB7) for processing in the Defense Waste Processing Facility (DWPF). The SB7 material is currently in Tank 51 being washed and prepared for transfer to Tank 40. The acceptance evaluation needs to be completed prior to the transfer of the material in Tank 51 to Tank 40. The sludge slurry in Tank 40 has already been qualified for DWPF and is currently being processed as SB6. The radionuclide concentrations were measured or estimated in the Tank 51 SB7 Qualification Sample prepared at Savannah River National Laboratory (SRNL). This sample was prepared from the three liter qualification sample of Tank 51 sludge slurry (HTF-51-10-125) received on September 18, 2010. The sample was delivered to SRNL where it was initially characterized in the Shielded Cells. With consultation from the Liquid Waste Organization, the qualification sample was then modified by several washes and decants, which included addition of Pu from H Canyon and sodium nitrite per the Tank Farm corrosion control program. This final slurry now has a composition expected to be similar to that of the slurry in Tank 51 after final preparations have been made for transfer of that slurry to Tank 40. Determining the radionuclide concentrations in this Tank 51 SB7 Qualification Sample is part of the work requested in Technical Task Request (TTR) No. HLW-DWPF-TTR-2010-0031. The radionuclides included in this report are needed for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria (TSR/WAC) Evaluation, and the DWPF Solid Waste Characterization Program (TTR Task I.2). Radionuclides required to meet the Waste Acceptance Product Specifications (TTR Task III.2.) will be measured at a later date after the slurry from Tank 51 has been transferred to Tank 40. Then a sample of the as-processed SB7 will be taken and transferred to SRNL for measurement of these radionuclides. The results presented in this report are those necessary for DWPF to assess if the Tank 51 SB7 sample prepared at SRNL meets the requirements for the DWPF Radiological Program Evaluation, the DWPF Waste Acceptance Criteria evaluation, and the DWPF Solid Waste Characterization Program. Concentrations are given for thirty-four radionuclides along with total alpha and beta activity. Values for total gamma and total gamma plus beta activities are also calculated.

  20. Development Of A Macro-Batch Qualification Strategy For The Hanford Tank Waste Treatment And Immobilization Plant

    SciTech Connect (OSTI)

    Herman, Connie C.

    2013-09-30

    The Savannah River National Laboratory (SRNL) has evaluated the existing waste feed qualification strategy for the Hanford Tank Waste Treatment and Immobilization Plant (WTP) based on experience from the Savannah River Site (SRS) Defense Waste Processing Facility (DWPF) waste qualification program. The current waste qualification programs for each of the sites are discussed in the report to provide a baseline for comparison. Recommendations on strategies are then provided that could be implemented at Hanford based on the successful Macrobatch qualification strategy utilized at SRS to reduce the risk of processing upsets or the production of a staged waste campaign that does not meet the processing requirements of the WTP. Considerations included the baseline WTP process, as well as options involving Direct High Level Waste (HLW) and Low Activity Waste (LAW) processing, and the potential use of a Tank Waste Characterization and Staging Facility (TWCSF). The main objectives of the Hanford waste feed qualification program are to demonstrate compliance with the Waste Acceptance Criteria (WAC), determine waste processability, and demonstrate unit operations at a laboratory scale. Risks to acceptability and successful implementation of this program, as compared to the DWPF Macro-Batch qualification strategy, include: Limitations of mixing/blending capability of the Hanford Tank Farm; The complexity of unit operations (i.e., multiple chemical and mechanical separations processes) involved in the WTP pretreatment qualification process; The need to account for effects of blending of LAW and HLW streams, as well as a recycle stream, within the PT unit operations; and The reliance on only a single set of unit operations demonstrations with the radioactive qualification sample. This later limitation is further complicated because of the 180-day completion requirement for all of the necessary waste feed qualification steps. The primary recommendations/changes include the following: Collection and characterization of samples for relevant process analytes from the tanks to be blended during the staging process; Initiation of qualification activities earlier in the staging process to optimize the campaign composition through evaluation from both a processing and glass composition perspective; Definition of the parameters that are important for processing in the WTP facilities (unit operations) across the anticipated range of wastes and as they relate to qualification-scale equipment; Performance of limited testing with simulants ahead of the waste feed qualification sample demonstration as needed to determine the available processing window for that campaign; and Demonstration of sufficient mixing in the staging tank to show that the waste qualification sample chemical and physical properties are representative of the transfers to be made to WTP. Potential flowcharts for derivatives of the Hanford waste feed qualification process are also provided in this report. While these recommendations are an extension of the existing WTP waste qualification program, they are more in line with the processes currently performed for SRS. The implementation of these processes at SRS has been shown to offer flexibility for processing, having identified potential processing issues ahead of the qualification or facility processing, and having provided opportunity to optimize waste loading and throughput in the DWPF.

  1. Short contact time direct coal liquefaction using a novel batch reactor. Quarterly technical progress report, September 15, 1995--January 15, 1996

    SciTech Connect (OSTI)

    Klein, M.T.; Calkins, W.H.; Huang, He

    1996-01-26

    The objective of this research is to optimize the design and operation of the bench scale batch reactor (SCTBR) f or coal liquefaction at short contact times (0.01 to 10 minutes or longer). Additional objectives are to study the kinetics of direct coal liquefaction particularly at short reaction times, and to investigate the role of the organic oxygen components of coal and their reaction pathways during liquefaction. Many of those objectives have already been achieved and others are still in progress. This quarterly report covers further progress toward those objectives.

  2. AQ AM Announcement Y150512 DRAFT jm-cpb

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

    Los Alamos Research Park Suite 301 W Jemez Road, Los Alamos, NM 87544 Phone: 505-412-4200 n Fax: 505-2 2-0049 n info@newmexicoconsortium.org July 2015 Workshop Advanced Qualification of Additive Manufacturing Materials using in situ sensors, diagnostics and modeling Venues: La Fonda on the Plaza - Santa Fe - July 20 - 21, 2015 Los Alamos National Laboratory - July 22, 2015 (LANL participants only) Sponsors: Los Alamos National Laboratory: Institute for Materials Science (IMS) and MaRIE Cost:

  3. AQ AM Announcement Y150512 DRAFT jm-cpb

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

    Sponsors: Los Alamos National Laboratory: Institute for Materials Science (IMS) and MaRIE Cost: 250 fee with the New Mexico Consortium (NMC workshop registration site to come)...

  4. EERE Program Management Guide - Appendices A-Q

    Office of Environmental Management (EM)

    EERE Multi-Year Program Plan Template Foreword Multi-Year Program Plans (MYPP) are intended primarily to serve as operational guides for programs to manage their activities and as a source of information to help Energy Efficiency and Renewable Energy (EERE) management identify clear linkages between key program activities and progress toward goals. It is understood, however, that they are also read by a broad group of program stakeholders and may serve other purposes as well. Strategic planning

  5. “Nodal Gap” induced by the incommensurate diagonal spin density modulation in underdoped high- id='M1'>Tc superconductors

    SciTech Connect (OSTI)

    Zhou, Tao; Gao, Yi; Zhu, Jian -Xin

    2015-03-07

    Recently it was revealed that the whole Fermi surface is fully gapped for several families of underdoped cuprates. The existence of the finite energy gap along the id='M2'>d-wave nodal lines (nodal gap) contrasts the common understanding of the id='M3'>d-wave pairing symmetry, which challenges the present theories for the high-id='M4'>Tcsuperconductors. Here we propose that the incommensurate diagonal spin-density-wave order can account for the above experimental observation. The Fermi surface and the local density of states are also studied. Our results are in good agreement with many important experiments in high-id='M5'>Tcsuperconductors.

  6. Method and electrochemical cell for synthesis and treatment of metal monolayer electrocatalysts metal, carbon, and oxide nanoparticles ion batch, or in continuous fashion

    DOE Patents [OSTI]

    Adzic, Radoslav; Zhang, Junliang; Sasaki, Kotaro

    2015-04-28

    An apparatus and method for synthesis and treatment of electrocatalyst particles in batch or continuous fashion is provided. In one embodiment, the apparatus comprises a sonication bath and a two-compartment chamber submerged in the sonication bath. The upper and lower compartments are separated by a microporous material surface. The upper compartment comprises a cover and a working electrode (WE) connected to a Pt foil contact, with the foil contact connected to the microporous material. The upper chamber further comprises reference counter electrodes. The lower compartment comprises an electrochemical cell containing a solution of metal ions. In one embodiment, the method for synthesis of electrocatalysts comprises introducing a plurality of particles into the apparatus and applying sonication and an electrical potential to the microporous material connected to the WE. After the non-noble metal ions are deposited onto the particles, the non-noble metal ions are displaced by noble-metal ions by galvanic displacement.

  7. Monitoring Uranium Transformations Determined by the Evolution of Biogeochemical Processes: Design of Mixed Batch Reactor and Column Studies at Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Criddle, Craig S.; Wu, Weimin

    2013-04-17

    With funds provided by the US DOE, Argonne National Laboratory subcontracted the design of batch and column studies to a Stanford University team with field experience at the ORNL IFRC, Oak Ridge, TN. The contribution of the Stanford group ended in 2011 due to budget reduction in ANL. Over the funded research period, the Stanford research team characterized ORNL IFRC groundwater and sediments and set up microcosm reactors and columns at ANL to ensure that experiments were relevant to field conditions at Oak Ridge. The results of microcosm testing demonstrated that U(VI) in sediments was reduced to U(IV) with the addition of ethanol. The reduced products were not uraninite but were instead U(IV) complexes associated with Fe. Fe(III) in solid phase was only partially reduced. The Stanford team communicated with the ANL team members through email and conference calls and face to face at the annual ERSP PI meeting and national meetings.

  8. Comparison of different liquid anaerobic digestion effluents as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover

    SciTech Connect (OSTI)

    Xu Fuqing; Shi Jian; Lv Wen; Yu Zhongtang; Li Yebo

    2013-01-15

    Highlights: Black-Right-Pointing-Pointer Compared methane production of solid AD inoculated with different effluents. Black-Right-Pointing-Pointer Food waste effluent (FWE) had the largest population of acetoclastic methanogens. Black-Right-Pointing-Pointer Solid AD inoculated with FWE produced the highest methane yield at F/E ratio of 4. Black-Right-Pointing-Pointer Dairy waste effluent (DWE) was rich of cellulolytic and xylanolytic bacteria. Black-Right-Pointing-Pointer Solid AD inoculated with DWE produced the highest methane yield at F/E ratio of 2. - Abstract: Effluents from three liquid anaerobic digesters, fed with municipal sewage sludge, food waste, or dairy waste, were evaluated as inocula and nitrogen sources for solid-state batch anaerobic digestion of corn stover in mesophilic reactors. Three feedstock-to-effluent (F/E) ratios (i.e., 2, 4, and 6) were tested for each effluent. At an F/E ratio of 2, the reactor inoculated by dairy waste effluent achieved the highest methane yield of 238.5 L/kgVS{sub feed}, while at an F/E ratio of 4, the reactor inoculated by food waste effluent achieved the highest methane yield of 199.6 L/kgVS{sub feed}. The microbial population and chemical composition of the three effluents were substantially different. Food waste effluent had the largest population of acetoclastic methanogens, while dairy waste effluent had the largest populations of cellulolytic and xylanolytic bacteria. Dairy waste also had the highest C/N ratio of 8.5 and the highest alkalinity of 19.3 g CaCO{sub 3}/kg. The performance of solid-state batch anaerobic digestion reactors was closely related to the microbial status in the liquid anaerobic digestion effluents.

  9. 4-ID-D Instrumentation

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

    Area Diffractometors 8-Circle 4Tesla Magnet 13 Tesla Magnet Focussing Zone Plate Optics K-B Mirror System Temperature Control Low Temperature Displex (4.4 to 325 K) High...

  10. DOE-ID Organization Chart

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

    Last Updated: 11/14/2011

  11. DOE-ID Operations Summary

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

    November 1, 2014 - November 30, 2014 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP)

  12. DOE-ID Operations Summary

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

    December 1, 2014 - December 31, 2014 EDITOR'S NOTE: The following is a summary of contractor operations at the Idaho National Laboratory Site, managed by the DOE- Idaho Operations Office. It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a brief summary of accomplishments at the Site. POC: Danielle Miller, (208) 526-5709. Advanced Mixed Waste Treatment Project (AMWTP)

  13. DOE-ID Operations Summary

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

    ... the treatment of residual sodium from the Experimental ... and was a leading world expert on fast reactor technology. ... feasibility of breeder reactors-or reactors that could ...

  14. DOE-ID Operations Summary

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

    D--BEA-ATR-2015-0011 March 4: While removing flooring at the Engineering Research Office Building, the bolt head a floor jack being used to hoist an office partition inadvertently...

  15. DOE-ID Operations Summary

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

    It has been compiled in response to a request from stakeholders for more information on health, safety and environmental incidents at DOE facilities in Idaho. It also includes a...

  16. DOE-ID Operations Summary

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

    has been compiled in response to a request from stakeholders for more information about health, safety and environmental incidents at DOE facilities in Idaho. It also includes a...

  17. Real ID Act in brief

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

    expertise and access to lab capabilities to help small businesses through the New Mexico Small Business Assistance Program. November 10, 2015 Molecular clocks control...

  18. DOE-ID Operations Summary

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

    Treatment Group (ITG) identified a reoccurring issue regarding an increase of the migration of radioactive contaminants onto personnel wearing anti-contamination clothing...

  19. DESTRUCTION OF TETRAPHENYLBORATE IN TANK 48H USING WET AIR OXIDATION BATCH BENCH SCALE AUTOCLAVE TESTING WITH ACTUAL RADIOACTIVE TANK 48H WASTE

    SciTech Connect (OSTI)

    Adu-Wusu, K; Paul Burket, P

    2009-03-31

    Wet Air Oxidation (WAO) is one of the two technologies being considered for the destruction of Tetraphenylborate (TPB) in Tank 48H. Batch bench-scale autoclave testing with radioactive (actual) Tank 48H waste is among the tests required in the WAO Technology Maturation Plan. The goal of the autoclave testing is to validate that the simulant being used for extensive WAO vendor testing adequately represents the Tank 48H waste. The test objective was to demonstrate comparable test results when running simulated waste and real waste under similar test conditions. Specifically: (1) Confirm the TPB destruction efficiency and rate (same reaction times) obtained from comparable simulant tests, (2) Determine the destruction efficiency of other organics including biphenyl, (3) Identify and quantify the reaction byproducts, and (4) Determine off-gas composition. Batch bench-scale stirred autoclave tests were conducted with simulated and actual Tank 48H wastes at SRNL. Experimental conditions were chosen based on continuous-flow pilot-scale simulant testing performed at Siemens Water Technologies Corporation (SWT) in Rothschild, Wisconsin. The following items were demonstrated as a result of this testing. (1) Tetraphenylborate was destroyed to below detection limits during the 1-hour reaction time at 280 C. Destruction efficiency of TPB was > 99.997%. (2) Other organics (TPB associated compounds), except biphenyl, were destroyed to below their respective detection limits. Biphenyl was partially destroyed in the process, mainly due to its propensity to reside in the vapor phase during the WAO reaction. Biphenyl is expected to be removed in the gas phase during the actual process, which is a continuous-flow system. (3) Reaction byproducts, remnants of MST, and the PUREX sludge, were characterized in this work. Radioactive species, such as Pu, Sr-90 and Cs-137 were quantified in the filtrate and slurry samples. Notably, Cs-137, boron and potassium were shown as soluble as a result of the WAO reaction. (4) Off-gas composition was measured in the resulting gas phase from the reaction. Benzene and hydrogen were formed during the reaction, but they were reasonably low in the off-gas at 0.096 and 0.0063 vol% respectively. Considering the consistency in replicating similar test results with simulated waste and Tank 48H waste under similar test conditions, the results confirm the validity of the simulant for other WAO test conditions.

  20. Thermal Analysis of Waste Glass Batches: Effect of Batch Makeup...

    Office of Scientific and Technical Information (OSTI)

    Books Please see Document Availability for additional information on obtaining the full-text document. Library patrons may search WorldCat to identify libraries that hold this book...

  1. Proof of concept and performance optimization of high gravity batch type centrifuge for dewatering fine coal. Quarterly technical progress report No. 3, March 20, 1990--June 20, 1990, Revision

    SciTech Connect (OSTI)

    Smith, L.B.; Durney, T.E. Jr.

    1990-07-24

    Coal Technology Corporation (CTC) believes that the new CTC high gravity, high production, batch type centrifugal dryer technology can play a significant role in improving the product quality as well as costs of operation in coal processing plants. It is further believed that the new centrifugal dryer technology can form an important part in systems used to clean up the millions of tons of coal fines in refuse piles and ponds. It is anticipated that the new centrifuge can become an important ancillary to the advanced deep cleaning processes for coal. Because of these convictions, CTC has been engaged in a pioneering research effort into the new art of drying fine clean coal in high gravity, high production, batch type centrifuges, since 1981. This work has progressed to the point where the new centrifugal dryer technology is nearly ready for commercialization. It promises to provide needed fine coal drying capability at somewhat lower capital costs and at substantially lower operating costs than competitive systems. It also promises to do so with no detrimental effects on either the coal quality or the evironment. The primary objective of this project is to prove the concept in a commercial coal processing plant environment. The proof of concept tests will also include testing with a variety of coals from different regions. A further objective will be to optimize the efficiency and the cost effectiveness of the new centrifugal dryer technology.

  2. Monitoring Jobs

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

    Monitoring Jobs Monitoring Jobs Overview Please see the man pages of the commands below for more options. The Job Information page has more information on current queue status, completed jobs, and job summary statistics. Command Description qsub batch_script Submit batch script to queue; returns job_id. qdel job_id Delete job from queue. qhold job_id Place job on hold in queue. qrls job_id Release held job. qalter Change attributes of submitted job. qmove new_queue job_id Move job to a different

  3. Origin State>> CA CA ID ID ID IL KY MD MO NM NM NY NY OH SC

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

    MO NM NM NY NY OH SC TN TN TN, WA, CA TN TN TN TN Total Shipments by Route Lawrence Livermore National Laboratory General Atomics Batelle Energy Alliance Idaho National Laboratory Advanced Mixed Waste Treatment Project Argonne National Laboratory Paducah Gaseous Diffusion Plant Aberdeen Proving Grounds National Security Technologies Sandia National Laboratory Los Alamos National Laboratory Brookhaven National Laboratory CH2M Hill B&W West Valley, LLC Portsmouth Gaseous Diffusion Plant

  4. Origin State>> CA CA ID ID ID IL KY MD NM NM NV NY NY OH TN

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

    NM NM NV NY NY OH TN TN TN, WA, CA TN TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory General Atomics Advanced Mixed Waste Treatment Project Batelle Energy Alliance Idaho National Laboratory Argonne National Laboratory Paducah Gaseous Diffusion Plant Aberdeen Proving Ground Los Alamos National Laboratory Sandia National Laboratory National Security Technologies Brookhaven National Laboratory West Valley Environmental Services Portsmouth Gaseous Diffusion Plant

  5. Origin State>> CA ID ID ID IL KY MD NM NM NY NY OH SC TN TN

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

    MD NM NM NY NY OH SC TN TN TN, WA, CA TN TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory Advanced Mixed Waste Treatment Project Batelle Energy Alliance Idaho National Laboratory Argonne National Laboratory Paducah Gaseous Diffusion Plant Aberdeen Proving Ground Los Alamos National Laboratory Sandia National Laboratory Brookhaven National Laboratory West Valley Environmental Services Portsmouth Gaseous Diffusion Plant Savannah River Site Duratek/Energy Solutions Babcox

  6. Origin State>> CA ID ID ID IL KY NV NY NY OH TN TN TN, WA, CA

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

    NV NY NY OH TN TN TN, WA, CA TN TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory Advanced Mixed Waste Treatment Project Batelle Energy Alliance Idaho National Laboratory Argonne National Laboratory Paducah Gaseous Diffusion Plant National Security Technologies Brookhaven National Laboratory West Valley Environmental Services Portsmouth Gaseous Diffusion Plant Duratek/Energy Solutions Babcox & Wilcox Technical Services Y-12 Plant Materials & Energy Corporation

  7. Origin State>> CA ID ID ID IL MD NM NM NV NY NY OH SC TN TN

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

    NV NY NY OH SC TN TN TN, WA, CA TN TN TN Total Shipments by Route Lawrence Livermore National Laboratory Batelle Energy Alliance Idaho National Laboratory Advanced Mixed Waste Treatment Project Argonne National Laboratory Aberdeen Proving Ground Sandia National Laboratory Los Alamos National Laboratory National Security Technologies Brookhaven National Laboratory West Valley Environmental Services Portsmouth Gaseous Diffusion Plant Savannah River Site Duratek/Energy Solutions Babcox & Wilcox

  8. Origin State>> CA ID ID ID IL MD NM NM NY OH TN TN TN, WA, CA

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

    NY OH TN TN TN, WA, CA TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory Batelle Energy Alliance Idaho National Laboratory Advanced Mixed Waste Treatment Project Argonne National Laboratory Aberdeen Proving Ground Sandia National Laboratory Los Alamos National Laboratory Brookhaven National Laboratory Portsmouth Gaseous Diffusion Plant Duratek/Energy Solutions Babcox & Wilcox Technical Services Y-12 Plant Materials & Energy Corporation (M&EC) Perma-Fix

  9. Origin State>> CA ID ID ID IL NM NM OH TN TN TN, WA, CA TN TN

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

    NM NM OH TN TN TN, WA, CA TN TN TN TN TX Total Shipments by Route Lawrence Livermore National Laboratory Batelle Energy Alliance Idaho National Laboratory Advanced Mixed Waste Treatment Project Argonne National Laboratory Sandia National Laboratory Los Alamos National Laboratory Portsmouth Gaseous Diffusion Plant Duratek/Energy Solutions Babcox & Wilcox Technical Services Y-12 Plant Materials & Energy Corporation (M&EC) Perma-Fix Nuclear Fuels Services Wastren Advantage, Inc.

  10. Enterprise Assessments Operational Awareness Record for the Follow-Up Review of the Idaho Site Fire Protection Program as Implemented for the Irradiated Materials Characterization Laboratory and the Advanced Mixed Waste Treatment Project, OAR # EA-ID-2015-10-22

    Office of Environmental Management (EM)

    EA Operational Awareness Record Report Number: EA-ID-2015-10-22 Site: Idaho Site Subject: Follow-Up Review of the Idaho Site Fire Protection Program as Implemented for the Irradiated Materials Characterization Laboratory and the Advanced Mixed Waste Treatment Project Dates of Activity: 10/19/2015 - 10/22/2015 Report Preparer: Aleem E. Boatright Activity Description / Purpose: The Office of Environment, Safety and Health Assessments, within the Office of Enterprise Assessments (EA), performed a

  11. Beamline 6-ID-D Publications

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    metastable B2 phase during solidification of Ni50Zr50 alloy: electrostatic levitation and molecular dynamics simulation studies," D.G. Quirinale, G.E. Rustan, S.R. Wilson, M.J....

  12. SLAC Dosimeter / ID Request Form A

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

    a replacement dosimeter because my dosimeter: Is lost* Was damagedcompromised* Was forgotten Was turned in Expired Other (please explain) * Submit a SLAC LostDamaged Dosimeter...

  13. 1. CONTRACT ID CODE PAGE OF PAGES

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    or print) I16A NAME AND TITILE OF CONTRACTING OFFICER (l'vpe or print) Ronnie L. Dawson Contracting Officer 15B. CONTRACTORJOFEEROR 15C. DAlE SIGNED 16B, UNITED STATES OF...

  14. Property:DSIRE/Id | Open Energy Information

    Open Energy Info (EERE)

    DSIRE Incentive Code. Pages using the property "DSIREId" Showing 25 pages using this property. (previous 25) (next 25) 2 2003 Climate Change Fuel Cell Buy-Down Program...

  15. 7-ID Home Page | Advanced Photon Source

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

    Time-resolved x-ray diffraction, including at elevated and cryogenic temperatures Laser pump, x-ray probe spectroscopy and scattering from atoms and molecules in vacuum and in...

  16. 04_ID11423_2012.pdf

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

    '

  17. UCRL-ID-119328 G I.

    Office of Scientific and Technical Information (OSTI)

    2. Information and Analysis 2 . 1 . 2 . 2 . 2 . 3 . 3 . 3 . 1 . 3 . 2 . Scope and Management of Quality and Performance Data and Information. Competitive Comparisons and...

  18. Beamline 6-ID-B,C Publications

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

    of electron doped manganites," S. Middey, M. Kareev, D. Meyers, X. Liu, Y. Cao, S. Tripathi, D. Yazici, M.B. Maple, P.J. Ryan, J.W. Freeland, J. Chakhalian, Appl. Phys. Lett....

  19. UCRL-ID-U4671 Overview

    Office of Scientific and Technical Information (OSTI)

    U4671 Overview of Uranium Atomic Vapor Laser Isotope Separation August 1993 © Unlv_W4y ¢_t(':a#loml= LL_ Lawrence Livermore N_ltional Laboratory r ' Energy Systems DISCLAIMER This document was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor the University of California nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness,

  20. Final Report: DOE/ID/14215

    SciTech Connect (OSTI)

    Kenneth Bryden; J. Richard Hess; Thomas Ulrich; Robert Zemetra

    2008-08-18

    The proposed straw separation system developed in the research project harvests the large internode sections of the straw which has the greater potential as a feedstock for lignocellulosic ethanol production while leaving the chaff and nodes in the field. This strategy ensures sustainable agriculture by preventing the depletion of soil minerals, and it restores organic matter to the soil in amounts and particle sizes that accommodate farmers needs to keep tillage and fertilizer costs low. A ton of these nutrient-rich plant tissues contains as much as $10.55 worth of fertilizer (economic and energy benefits), in terms of nitrogen, phosphorus, potassium, and other nutrients provided to the soil when incorporated by tillage instead of being burned. Biomass conversion to fermentable sugars for the purpose of producing fuels, chemicals, and other industrial products is well understood. Most bioenergy strategies rely on low-cost fermentable sugars for sustainability and economic viability in the marketplace. Exploitation of the whole cropspecifically, wheat straw or other plant material currently regarded as residue or wasteis a practical approach for obtaining a reliable and low-cost source of sugars. However, industrial-scale production of sugars from wheat straw, while technically feasible, is plagued by obstacles related to capital costs, energy consumption, waste streams, production logistics, and the quality of the biomass feedstock. Currently available separation options with combine harvesters are not able to achieve sufficient separation of the straw/stover and chaff streams to realize the full potential of selective harvest. Since ethanol yield is a function of feedstock structural carbohydrate content, biomass anatomical fractions of higher product yield can have a significant beneficial impact on minimum ethanol selling price. To address this advanced biomass separation computation engineering models were developed to more effectively and efficiently engineer high-fidelity and high throughput separation systems for biomass components. INL and Iowa State University developed a computational modeling strategy for simulating multi-phase flow with an integrated solver using various computational fluid dynamics (CFD) codes. ISU set up a classic multi-phase test problem to be solved by the various CFD codes. The benchmark case was based on experimental data for bubble gas holdup and bed expansion for a gas/solid fluidized bed. Preliminary fluidization experiments identified some unexpected fluidization behavior, where rather than the bed uniformly fluidizing, a blow out would occur where a hole would open up in the bed through which the air would preferentially flow, resulting in erratic fluidization. To improve understanding of this phenomena and aid in building a design tool, improved computational tools were developed. The virtual engineering techniques developed were tested and utilized to design a separation baffle in a CNH combine. A computational engineering approach involving modeling, analysis, and simulation was used in the form of virtual engineering to design a baffle separator capable of accomplishing the high-fidelity residue separation established by the performance targets. Through the use of the virtual engineering model, baffle designs were simulated to (1) determine the effect of the baffle on the airflow of the combine cleaning system, and (2) predict the effectiveness of the baffle in separating the residue streams. A baffle design was selected based on the virtual engineering modeling, built into the INL selective harvest test combine. The result of the baffle changes improved the crop separation capability of the combine, enabling downstream improvement in composition and theoretical ethanol yield. In addition, the positive results from the application of the virtual engineering tools to the CNH combine design resulted in further application of these tools to other INL areas of research. INL and the University of Idaho identified, characterized, and modified a key plant biosynt

  1. Beamline 4-ID-C Publications

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

    double exchange interactions and pressure tuning of magnetism in 3d-5d double perovskite Sr2FeOsO6," LS.I. Veiga, G. Fabbris, M. van Veenendaal, N.M. Souza-Neto, H.L. Feng,...

  2. Beamline 4-ID-D Publications

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

    Phys. Rev. B 91, 094413 (2015). "Competing Superexchange Interactions in Double Perovskite Osmates," Ryan C. Morrow, Ph.D.-Thesis, Ohio State University, 2015. "Effects of...

  3. ID HLW FEIS amended ROD.pdf

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

  4. Catalysts via First Principles (Agreement ID:10635)

    Broader source: Energy.gov [DOE]

    2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

  5. Property:WFSPTurbineID | Open Energy Information

    Open Energy Info (EERE)

    + Auburn-Washburn Wind Project + 120,012 + Avery County High School Wind Project + 110,607 + B Bancroft-Rosalie Public Schools Wind Project + 108,812 + Bloomfield Public Schools...

  6. Eastport, ID Natural Gas Exports to Canada

    Gasoline and Diesel Fuel Update (EIA)

    708,806 606,099 634,194 686,449 608,147 673,787 1996-2015 Pipeline Prices 4.19 3.90 2.59 3.34 4.14 2.34

  7. Eastport, ID Natural Gas Exports to Canada

    Gasoline and Diesel Fuel Update (EIA)

    09 2010 2011 2012 2013 2014 View History Pipeline Volumes 113 12 10 0 6 0 1998-2014 Pipeline Prices 4.49 5.85 4.74 -- 3.27 -- 1998-2014

  8. Employee Assistance Self-ID Form

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

    is to be used by persons who expect that they will need assistance during an emergency. ... Any information provided will be kept confidential and shared with those having a need to ...

  9. DOE-ID Mission and Vision

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

    in nuclear energy and other energy resources, national security, and environmental management. The Department's expectations of its operations offices and laboratories are:...

  10. Data ID Service | DOE Data Explorer

    Office of Scientific and Technical Information (OSTI)

    for discovery of additional data, specialized interfaces, toolkits for data analysis, etc. Because OSTI is the operating agent for Science.gov and World Wide Science.org,...

  11. Page 1, About DOE-ID

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

    the nation's critical infrastructure; continue to support the U.S. Army in developing and manufacturing vehicle armor; and ensure the INL is a leading provider of applied solutions...

  12. UCRL-ID-119328 G I.

    Office of Scientific and Technical Information (OSTI)

    A Comparison of Total Quality Management (TQM) Approaches ... Lists of Selected TQM Criteria. Principles & Tenets ... Senge's The Learning Organization ......

  13. DOE-ID FOIA Reading Room

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

    Reading Room READING ROOM Eectronic Freedom of Information Act, E-FOIA RECORDS UNDER THE E-FOIA The Electronic Freedom of Information Act Amendments of 1996 addresses the issues...

  14. APS Beamline 4-ID-C

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

    Source. Research on this beamline focuses on the study of magnetic properties of interfaces and dilute systems using x-ray spectroscopy techniques at energies between 500 to...

  15. NEPA ID# WIP:95:0002

    Office of Environmental Management (EM)

    CBFO-13-3322 2013 ANNUAL MITIGATION REPORT FOR THE WASTE ISOLATION PILOT PLANT JULY 10, 2013 DOE/CBFO-13-3322 2 TABLE OF CONTENTS ........................................................................................................................................................ 3 ........................................................................................................................................................ 4 2013 ANNUAL MITIGATION REPORT

  16. Employee Assistance Self-ID Form

    Office of Environmental Management (EM)

    Request for Assistance During an Emergency Employee Self Identification This form is to be used by persons who expect that they will need assistance during an emergency. The purpose of this form is to help Program Office supervisors and the Incident Management Team ensure that plans are in place to assist persons with temporary or permanent disabilities during an emergency. The Incident Management Team would rather work with someone on a specific plan of action before an emergency than have an

  17. U.S. NO₂ trends (2005-2013): EPA air quality system (AQS) data...

    Office of Scientific and Technical Information (OSTI)

    column density (VCD) data product from the Ozone Monitoring Instrument (OMI) on the Aura satellite.We demonstrate that the current OMI NO algorithm is of sufficient maturity ...

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

    Invalid ID

  19. Batch fabrication of precision miniature permanent magnets

    DOE Patents [OSTI]

    Christenson, Todd R. (Albuquerque, NM); Garino, Terry J. (Albuquerque, NM); Venturini, Eugene L. (Albuquerque, NM)

    2002-01-01

    A new class of processes for fabrication of precision miniature rare earth permanent magnets is disclosed. Such magnets typically have sizes in the range 0.1 to 10 millimeters, and dimensional tolerances as small as one micron. Very large magnetic fields can be produced by such magnets, lending to their potential application in MEMS and related electromechanical applications, and in miniature millimeter-wave vacuum tubes. This abstract contains simplifications, and is supplied only for purposes of searching, not to limit or alter the scope or meaning of any claims herein.

  20. Batch extracting process using magneticparticle held solvents

    DOE Patents [OSTI]

    Nunez, Luis (Elmhurst, IL); Vandergrift, George F. (Bolingbrook, IL)

    1995-01-01

    A process for selectively removing metal values which may include catalytic values from a mixture containing same, wherein a magnetic particle is contacted with a liquid solvent which selectively dissolves the metal values to absorb the liquid solvent onto the magnetic particle. Thereafter the solvent-containing magnetic particles are contacted with a mixture containing the heavy metal values to transfer metal values into the solvent carried by the magnetic particles, and then magnetically separating the magnetic particles. Ion exchange resins may be used for selective solvents.

  1. SLUDGE BATCH 6 PHASE II FLOWSHEET SIMULATIONS

    SciTech Connect (OSTI)

    Koopman, D.; Best, D.

    2010-03-30

    Two Sludge Receipt and Adjustment Tank (SRAT) runs were used to demonstrate that a fairly wide window of acid stoichiometry was available for processing SB6 Phase II flowsheet simulant (Tank 40 simulant) while still meeting the dual goals of acceptable nitrate destruction and controlled hydrogen generation. Phase II was an intermediate flowsheet study for the projected composition of Tank 40 after transfer of SB6/Tank 51 sludge to the heel of SB5. The composition was based on August 2009 projections. A window of about 50% in total acid was found between acceptable nitrite destruction and excessive hydrogen generation.

  2. Report for Batch Leach Analyses on Sediments at 100-HR-3 Operable Unit, Boreholes C7620, C7621, C7622, C7623, C7626, C7627, C7628, C7629, C7630, and C7866. Revision 1.

    SciTech Connect (OSTI)

    Lindberg, Michael J.

    2012-04-25

    This is a revision to a previously released report. This revision contains additional analytical results for the sample with HEIS number B2H4X7. Between November 4, 2010 and October 26, 2011 sediment samples were received from 100-HR-3 Operable Unit for geochemical studies. The analyses for this project were performed at the 331 building located in the 300 Area of the Hanford Site. The analyses were performed according to Pacific Northwest National Laboratory (PNNL) approved procedures and/or nationally recognized test procedures. The data sets include the sample identification numbers, analytical results, estimated quantification limits (EQL), and quality control data. The preparatory and analytical quality control requirements, calibration requirements, acceptance criteria, and failure actions are defined in the on-line QA plan 'Conducting Analytical Work in Support of Regulatory Programs' (CAW). This QA plan implements the Hanford Analytical Services Quality Assurance Requirements Documents (HASQARD) for PNNL. Samples were received with a chain of custody (COC) and were analyzed according to the sample identification numbers supplied by the client. All Samples were refrigerated upon receipt until prepared for analysis. All samples were received with custody seals intact unless noted in the Case Narrative. Holding time is defined as the time from sample preparation to the time of analyses. The prescribed holding times were met for all analytes unless noted in the Case Narrative. All reported analytical results meet the requirements of the CAW or client specified SOW unless noted in the case narrative. Due to the requirements of the statement of work and sampling events in the field, the 28 day and the 48 hr requirements cannot be met. The statement of work requires samples to be selected at the completion of the borehole. It is not always possible to complete a borehole and have the samples shipped to the laboratory within the hold time requirements. Duplicate RPD for Uranium 238 (38.9%) was above the acceptance limit (35) in 1E05003-DUP1 for ICPMS-Tc-U-WE The sample result is less than 10 times the detection limits. Duplicate recoveries are not applicable to this analyte. Duplicate RPD for Silver 107 (68.2%) was above the acceptance limit (35) in 2C06004-DUP1 for ICPMS-RCRA-AE The sample result is less than 10 times the detection limits. Duplicate recoveries are not applicable to this analyte. Matrix Spike Recovery for Chromium, Hexavalent (48.8%) was outside acceptance limits (75-125) in 1E23001-MS1 for Hexavalent Chromium/Soil. Potential Matrix interference. Sample results associated with this batch are below the EQL. There should be no impact to the data as reported. Matrix Spike Recovery for Chromium, Hexavalent (50.2%) was outside acceptance limits (75-125) in 2B22010-MS1 for Hexavalent Chromium/Soil. Potential Matrix interference. Sample results associated with this batch are below the EQL. There should be no impact to the data as reported.

  3. Vehicle Technologies Office Merit Review 2014: Catalyst Characterization (Agreement ID:9130) Project ID:18519

    Broader source: Energy.gov [DOE]

    Presentation given by Cummins at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about catalyst characterization.

  4. Vehicle Technologies Office Merit Review 2014: High Temperature Aluminum Alloys (Agreement ID:24034) Project ID:18518

    Broader source: Energy.gov [DOE]

    Presentation given by Pacific Northwest National Laboratory at 2014 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Office Annual Merit Review and Peer Evaluation Meeting about high...

  5. C:\\Forms\\2000 forms\\DOE F 742C.cdr

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

    BASIS MEAS. METHOD OTHER MEAS. POINT KEY MEASURE POINT ELEMENT WEIGHT BATCH NAME ISOTOPE WEIGHT DOE PROJECT NO. MEASUREMENT I.D. STATE ZIP CODE Page of Pages PHYSICAL INVENTORY...

  6. As you prepare for your upcoming beam time, please be aware that construction is planned to update SLAC Gate 17 with RFID proximity card access hardware and to change the stairs next to the Security hut to an ADA compliant ramp. Please forward this to your proposal collaborators (and ensure that all users have registered and completed training before they arrive). This construction is scheduled to begin Tuesday 5/28 and be completed by 6/28. During this construction, access to the LCLS and SSRL buildings and experimental facilities will be provided as follows: VEHICLES ONLY THROUGH GATE 17 5/28-6/28 0600-1530 (6 am-3:30 pm) Construction Zone. Only VEHICLE traffic will be allowed access through Gate 17 and flagman will provide traffic control. 1530-1800 (3:30-6:00 pm) Assumes construction will have stopped for the day; both traffic lanes will be open for vehicles. 1800-0600 (6 pm-6 am) As now, Gate 17 will be closed or barricaded overnight. PEDESTRIANS ONLY THROUGH GATE 16 5/28-6/28 The pedestrian turnstile at Gate 16A will not change. The turnstile is available for pedestrian use 24/7 as long as the individual has a valid SLAC ID badge (and there is a guard at Gate 30 to 'buzz' them through). 0700-1600 (6 am-4 pm) Pedestrians who would normally walk through Gate 17 will instead follow the detour to Gate 16 swing gate which will be unlocked and staffed by Security. A valid SLAC ID badge is needed to enter; new users without IDs will be allowed to proceed for check-in and badging after confirmation with the User Research Administration Office (see detour map attached). FYI - After the construction is completed and proximity card readers are fully functional, users and staff will enter Gates 17 and 30 using an activated RFID proximity card. More details to follow.

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

    Automated Proximity Access at Gate 17 and Sector 30 New SLAC ID badges with embedded RFID are used to activate these gates and for off-hours access at the main entrance off Sand Hill Road as well as Alpine Road (gates will be accessible 24/7) . New user badges include this proximity gate activation feature, but older photo IDs need to be updated. Users are advised to register, complete training and contact the User Research Administration (URA) office before arrival for beam time to help

  7. RAPID/Roadmap/18-ID-a | Open Energy Information

    Open Energy Info (EERE)

    requires notification under IDAPA 58.01.07 if the developer intends to use underground storage tanks (USTs). The notification serves as a measure to protect against ground water...

  8. NERSC Helps Physicists ID New Molecules With Unique Features

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

    applications," they wrote. "These molecules can be used for targeted non-invasive drug delivery. When assembled, the molecules can also form new high strength magnets...

  9. Property:RAPID/Contact/ID3/Name | Open Energy Information

    Open Energy Info (EERE)

    of Environmental Protection + Jon McRae + New Mexico State Land Office + Kelly Brooks Smith + O Oregon Department of Environmental Quality + David Cole + R Railroad Commission of...

  10. Property:EiaUtilityId | Open Energy Information

    Open Energy Info (EERE)

    Inc + 261 + AP Holdings LLC + 56571 + AP Holdings LLC (New York) + 56571 + APN Starfirst, L.P. + 50153 + APN Starfirst, L.P. (Illinois) + 50153 + APN Starfirst, L.P. (Ohio) + 50153...

  11. Intergral Drive Systems AG IDS | Open Energy Information

    Open Energy Info (EERE)

    Swaziland Zip: CH-8005 Sector: Wind energy Product: Zurich based producer of power electronics systems for wind turbines, PV plants, and propulsion systems. Coordinates:...

  12. RAPID/Roadmap/3-ID-c | Open Energy Information

    Open Energy Info (EERE)

    c < RAPID | Roadmap Jump to: navigation, search RAPID Regulatory and Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools...

  13. RAPID/Roadmap/18-ID-d | Open Energy Information

    Open Energy Info (EERE)

    or refuse, sludge from a waste water treatment plant, water supply treatment plant, or air pollution control facility and other discarded material including solid, liquid,...

  14. Property:RAPID/Contact/ID3/Position | Open Energy Information

    Open Energy Info (EERE)

    - Construction Permitting + U Utah Department of Environmental Quality + Nonpoint Source Pollution Contact + Utah Department of Natural Resources + Geothermal Resource and Steam...

  15. Property:RAPID/Contact/ID2/Position | Open Energy Information

    Open Energy Info (EERE)

    Division of Environmental Protection + NPDES Permitting Contact + Nevada Division of Water Resources + Groundwater Usage and Nonpoint Source Pollution Contact + New Mexico...

  16. Durability of Diesel Engine Particulate Filters (Agreement ID:10461)

    Broader source: Energy.gov [DOE]

    2013 DOE Hydrogen and Fuel Cells Program and Vehicle Technologies Program Annual Merit Review and Peer Evaluation Meeting

  17. RAPID/Roadmap/1-ID-a | Open Energy Information

    Open Energy Info (EERE)

    in Idaho is delegated to city and county governments. 01IDALandUseConsiderations.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  18. RAPID/Roadmap/18-ID-c | Open Energy Information

    Open Energy Info (EERE)

    Systems Idaho On-Site Wastewater Systems Webpage. 18IDCWastewaterPretreatmentPermit.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  19. RAPID/Roadmap/20-ID-a | Open Energy Information

    Open Energy Info (EERE)

    Code, governs the procedures for well abandonment. 20IDAWellAbandonmentProcess.pdf Error creating thumbnail: Page number not in range. Error creating thumbnail: Page number...

  20. Microsoft Word - DIOE-ID-INL-14-026.docx

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

    6 SECTION A. Project Title: Radiochemistry Laboratory (RCL) Supply Intake Filter Housing SECTION B. Project Description: The Radiochemistry Laboratory (RCL) air supply system does not adequately filter the fresh air drawn into the facility. Additional filtration on the fresh air supply is needed. The proposed action includes the following:  Add filter housing to RCL supply system which would be capable of 12,000 actual cubic feet per minute (ACFM).  Add differential gauges across the

  1. Microsoft Word - DOE-ID-10-004.doc

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

    4 SECTION A. Project Title: E-85 Fueling Systems for AMWTP and INTEC SECTION B. Project Description This project consists of installing two E-85 fueling systems (85 % ethanol and 15% petroleum based fuel) for fueling fleet vehicles. One system will be located at the Advanced Mixed Waste Treatment Project and the other at the Idaho Nuclear Technology Center. The two above ground, E85 compatible, double wall carbon steel, skid-mounted tanks have a capacity of 12,000 gallons each. The tanks will be

  2. Microsoft Word - DOE-ID-10-005.doc

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

    5 SECTION A. Project Title: CPP-663 HVAC Systems Upgrade SECTION B. Project Description The scope of work will be to repair and/or replace the existing heating, ventilation, and air conditioning system located in building CPP-663 at the Idaho National Engineering Laboratory. The scope will be to repair the existing system or identify an energy efficient replacement to the existing system and place an NFPA 70E code compliant electrical metering system that will monitor building electrical usage.

  3. Microsoft Word - DOE-ID-12-020.doc

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

    20 SECTION A. Project Title: ZPPR Surveillance Glovebox SECTION B. Project Description: The purpose of the proposed action is to limit exposure hazards and better contain airborne hazards, beyond current capabilities, associated with performing surveillance, characterization, and repackaging activities for transuranic materials in the Zero Power Physics Reactor (ZPPR) workroom hoods. In order to meet this purpose and need, the Transuranic Surveillance Glovebox (TSG) would be installed. This

  4. Microsoft Word - DOE-ID-14-042.docx

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

    SECTION A. Project Title: National Cybersecurity and Communications Integration Center (NCCIC)/Industrial Control Systems Cyber Emergency Response Team (ICS-CERT) Idaho High Frequency (HF) Shared Resources (SHARES) Station SECTION B. Project Description: The purpose of this work is to construct a new Department of Homeland Security (DHS) High Frequency (HF) Shared Resources (SHARES) Station at the Idaho National Laboratory (INL) behind the Systems Analysis Facility (SAF; Idaho Falls [IF]-627)

  5. Microsoft Word - DOE-ID-15-047.docx

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

    7 SECTION A. Project Title: New Gravel Parking Lot North of Idaho Falls (IF)-603 [Idaho National Laboratory (INL) Research Center (IRC)] SECTION B. Project Description and Purpose: . The proposed project would construct a gravel parking area north of the Idaho National Laboratory (INL) Research Center (IRC) Laboratory building IF-603. The location would be bounded by the east side of the landlord storage building (IF-610), the south side of the fence that is north of IF-610, the west side of the

  6. Microsoft Word - DOE-ID-INL-10-021.doc

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

    21 SECTION A. Project Title: Geotechnical Investigation for INL Remote-Handled Low-Level Waste Disposal SECTION B. Project Description: The proposed action would conduct geotechnical investigations at two 4-6 acre candidate sites for a Remote-Handled Low-Level Waste (RH LLW) Facility at the Idaho National Laboratory (INL). One site is located southwest of the Advanced Test Reactor (ATR)-Complex and the other site is located west of and across Lincoln Blvd. from the Idaho Comprehensive

  7. Microsoft Word - DOE-ID-INL-11-001.doc

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

    1 SECTION A. Project Title: Hex Block Shipment Project SECTION B. Project Description. This project involves the shipment of two irradiated stainless steel hex blocks presently located at the Idaho National Laboratory (INL) Materials and Fuels Complex (MFC) to a Westinghouse facility located in Pittsburgh, Pennsylvania to support Research and Development (R&D) activities. This R&D work will be performed by a private contractor and will involve the use of ultrasonic equipment to determine

  8. Microsoft Word - DOE-ID-INL-11-002.doc

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

    2 SECTION A. Project Title: Facility Construction and Modification in Support of the Material Security and Consolidation Project. SECTION B. Project Description: Additional onsite storage capabilities that meet anticipated security requirements are needed to support the accelerated processing of Experimental Breeder Reactor-II (EBR-II) spent nuclear fuel (SNF) and the potential growth of research and development activities. DOE is accelerating the processing of the highly enriched EBR-II SNF to

  9. Microsoft Word - DOE-ID-INL-11-003.doc

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

    3 SECTION A. Project Title: Specific Manufacturing Capability (SMC) Incinerator and Propane Tank System Removal SECTION B. Project Description The project will dismantle and remove the Specific Manufacturing Capability (SMC) refuse incinerator, the eighteen foot stack, and the associated propane tank system. All propane will be removed from the tank prior to physical removal. The incinerator is located on a cement slab approximately 20 meters northeast of building TAN-681 and is within the

  10. Microsoft Word - DOE-ID-INL-11-004.doc

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

    04 SECTION A. Project Title: ATR Canal AFIP-7 Channel Gap Probe Installation Project SECTION B. Project Description: The location for the proposed project is the Advanced Test Reactor (ATR) at the ATR Complex, located at the Idaho National Laboratory (INL). This project involves the following primary efforts: * Installation of the channel gap probe instrument into the East end of the ATR canal o Bolting together two pieces of the assembly o Lifting the channel gap probe into the canal o

  11. Microsoft Word - DOE-ID-INL-11-006.doc

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

    6 SECTION A. Project Title: INL - USGS Geotechnical Drilling Program (USGS 131A) SECTION B. Project Description: The U.S. Geological Survey (USGS) proposes to use an existing well pad to construct a replacement well, USGS131A, about 25 ft north of the original well head (USGS 131). USGS 131A will be drilled to about 1,300 ft below surface level (BSL) then instrumented with a multilevel monitoring system in FY 2012. The new well will replace USGS 131, which will be abandoned or used as a water

  12. Microsoft Word - DOE-ID-INL-11-008.doc

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

    8 SECTION A. Project Title: Parking area expansion along road to Range #7 SECTION B. Project Description: Additional parking is needed during breacher training and other demonstration activities on range #7 to accommodate access by emergency response vehicles. Historically, participants have parked their vehicles on the gravel road leading to range #7 which restricts access to emergency response vehicles. The proposed action is to "grub" out an area of approximately 0.06 acres (about

  13. Microsoft Word - DOE-ID-INL-11-010.doc

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

    1-010 SECTION A. Project Title: Special Manufacturing Complex (SMC) Line 1 Deactivation, Decontamination, and Decommissioning (DD&D) SECTION B. Project Description: This project proposes DD&D of Test Area North (TAN) 629, Line 1 to remove obsolete, out-of-service production equipment. Work will involve the removal of the inspection station, material transporters, laser water chiller, and laser. Associated electrical connections, utility piping, and localized ventilation will also be

  14. Microsoft Word - DOE-ID-INL-11-012.docx

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

    2 SECTION A. Project Title: ATR Primary Heat Exchanger Seismic Capacity Project SECTION B. Project Description: Modification and upgrade of the seismic support structures for the five primary heat exchangers within ATR (670-M-2, 3, 4, 5 and 85) is needed to meet new PC-4 seismic criteria. The scope of the design is to replace the upper tie-rod assemblies and wall mounted anchor plates (the existing belly band on each heat exchanger will remain unchanged). The existing concrete structures that

  15. Microsoft Word - DOE-ID-INL-11-013.doc

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

    3 SECTION A. Project Title: Modifications to Central Facilities Area (CFA)-Live Fire Range and Main Gate Drinking Water SECTION B. Project Description: Modification of the drinking water systems at the CFA Live Fire Range and Main Gate is needed to improve water quality. The drinking water chlorinator at the Live Fire Range does not function properly and cannot be modified or repaired. Personnel at the facility have been using bottled drinking water for several years. There is no disinfection at

  16. Microsoft Word - DOE-ID-INL-11-014.doc

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

    4 SECTION A. Project Title: Advanced Test Reactor Core Internals Changeout (CIC) Outage - 2015 SECTION B. Project Description: The proposed action will provide for the sixth core internals changeout (CIC) outage of the Advanced Test Reactor (ATR), which is housed in building Test Reactor Area (TRA)-670, located at the Idaho National Laboratory (INL) ATR Complex. Activities scheduled during the CIC outage include the changeout of components in the high-flux region of the ATR core and support

  17. Microsoft Word - DOE-ID-INL-12-002.doc

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

    2 SECTION A. Project Title: Underground Storage Tank (UST) Steel Line Replacements SECTION B. Project Description: The Idaho Department of Environmental Quality (DEQ) performed an inspection of Idaho National Laboratory's (INL's) USTs in September of 2011. Inspection results indicated field violations for failing to install and maintain cathodic protection systems for steel lines associated with seven underground storage tanks. DEQ did not accept the INL's "corrosion expert"

  18. Microsoft Word - DOE-ID-INL-12-004.doc

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

    4 SECTION A. Descriptive Information: Materials and Fuels Complex (MFC) Contaminated Equipment Storage Building (CESB) Conversion Scope Change SECTION B. Project Description: MFC-794 CESB is currently being modified for reasons described in Environmental Checklist (EC) Idaho National Laboratory (INL)-10- 074 (OA 12). During construction it was determined that some of the equipment that will be located in the building will need non-contact cooling water in order to operate. This EC addresses the

  19. Microsoft Word - DOE-ID-INL-12-005.doc

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

    5 SECTION A. Descriptive Information: Central Facilities Area (CFA) Shoot House Panel Installation SECTION B. Project Description: The existing shoothouse facility (Figure 1) provides little to no wind protection for trainers and observers. Trainers and observers stand in an elevated position that is mostly exposed to blowing winds. This project will install 10 new fiberglass panels (22' to 23' X 4' to 5') on the existing building to inhibit the wind and improve the usability of the facility.

  20. Microsoft Word - DOE-ID-INL-12-010.doc

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

    0 SECTION A. Project Title: Information Operations & Research Center (IORC) Room E-6 Air Conditioner Unit Installation SECTION B. Project Description: The proposed project will install an additional air conditioning (A/C) unit in the IORC (IF-608). Universal Power Supply (UPS) and server equipment are being relocated from rooms B-3 and B-6 to room E-6. The current A/C system that cools room E-6 is not adequate to cool the relocated equipment. The 5 ton cooling unit and drycooler will be

  1. Microsoft Word - DOE-ID-INL-12-011.docx

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

    1 SECTION A. Project Title: Advanced Test Reactor (ATR) Primary Coolant System (PCS) Relief Valves Monorail System SECTION B. Project Description: The purpose of this project is to provide a monorail system to aid maintenance personnel in the hoisting and transporting of the Advanced Test Reactor (ATR) Primary Coolant System (PCS) Safety Relief Valves, SF-A-1-71 and SF-A-1-72, in support of the 2 year replacement. The monorail system would consist of two independent monorail assemblies installed

  2. Microsoft Word - DOE-ID-INL-12-013.doc

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

    3 SECTION A. Project Title: Idaho National Laboratory (INL) Administration Building (IAB) Communication Room Heating, Ventilation, and Air Conditioning (HVAC) Upgrade SECTION B. Project Description: The proposed project would install new server equipment with associated uninterruptible power supplies (UPS's) and an additional air conditioning unit in the data room at the IAB (IF-606). The additional air conditioning (A/C) unit is needed to keep up with the load the new equipment requires.

  3. Microsoft Word - DOE-ID-INL-12-014.docx

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

    4 SECTION A. Project Title: M-10 Emergency Pump Backup Power SECTION B. Project Description: The proposed action would add a manually controlled electric power transfer switch and power inlet receptacle to the M-10 emergency coolant pump electrical power feed to power the M-10 pump to address safety issues that could arise with a complete loss of power on the Advanced Test Reactor (ATR)-670-E-15 diesel/commercial bus. The transfer switch and receptacle would be located outside the west wall of

  4. Microsoft Word - DOE-ID-INL-12-017.doc

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

    7 SECTION A. Project Title: Engineering Research Office Building (EROB) 1E- Human System Simulation Laboratory Modifications SECTION B. Project Description: The Nuclear Science and Technology (NS&T) customer for Human Simulation Systems Lab (HSSL) has requested additional - computer lab space to support forth coming projects in yearend FY12 and projected into FY13. Project specific is the LWRS-related project for control room upgrades for a commercial client. The project will utilize the

  5. Microsoft Word - DOE-ID-INL-12-019.doc

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

    9 SECTION A. Project Title: INL Administration Building (IAB)Telephone Room 112 Heating, Ventilating, and Air Conditioning (HVAC) Upgrade SECTION B. Project Description: The proposed project will install a new air conditioning unit in the INL Administration Building room 112. The new air conditioning system will handle the equipment heat loads within this room. Room 112 is an unclassified telephone room that is not normally occupied. This room has one supply air diffuser and one return air

  6. Microsoft Word - DOE-ID-INL-12-026.docx

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

    6 DIRECTIONS: Responsible Managers, Program Environmental Lead (PEL), and Environmental Support personnel complete this form by following the instructions found at the beginning of each section and submit to Environmental Support & Services (see Environmental Points of Contact, NEPA/Environmental Checklist Support at http://webfiles/es&h/es&s/contacts.pdf). Enter a Valid Charge Number: 101653B80 SECTION A. Project Title: Upgrade to the Concrete Masonry Unit (CMU) Wall at Test Reactor

  7. Microsoft Word - DOE-ID-INL-13-004.doc

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

    4 SECTION A. Project Title: High Density Fuel Material for Light Water Reactors (LWRs) SECTION B. Project Description This project proposes to install glove boxes, laboratory equipment and laboratory hoods in the east wing of the Experimental Fuels Facility (EFF), building 794, at the Materials and Fuels Complex (MFC) at the Idaho National Laboratory (INL). The building was previously known as the Contaminated Equipment Storage Building (CESB). The purpose of this project is to support a high

  8. Microsoft Word - DOE-ID-INL-13-005.docx

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

    5 SECTION A. Project Title: Land Mobile Radio - Bi Directional Amplifier (BDA) Installation SECTION B. Project Description The INL has contracted with White Cloud Communications to provide Land Mobile Radio Services for emergency first responders under a managed service contract. The contract includes provisions for area coverage and quality of service. Testing of the installed Radio Frequency backbone system revealed that certain buildings at the INL do not have adequate coverage. The

  9. Microsoft Word - DOE-ID-INL-13-011.docx

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

    1 SECTION A. Project Title: Install Air Conditioning in the Fuel Manufacturing Facility (FMF) (Materials and Fuel Complex [MFC]-704) Security Police Officer (SPO) Office SECTION B. Project Description: Install a 9000 BTU/hr split air conditioner in the SPO office of the FMF annex. 208V single phase power will be supplied from a new 20A breaker in the existing lighting panel (LP)-029. A new fusible disconnect switch will be installed on the outside of the building. Conduit will be field routed to

  10. Microsoft Word - DOE-ID-INL-13-012.docx

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

    12 SECTION A. Project Title: Water Security Test Bed (WSTB) SECTION B. Project Description: This project was extensively described in Environmental Checklists (ECs) Idaho National Laboratory (INL)-13-014 (Overarching [OA] 5) and INL-13-014 Revision (R) 1 (OA 5). Upon review, it was determined that additional planning and detail was required to fully describe the project and associated activities. Both INL-13-014 and R1 to that EC are canceled; this EC will replace them. Future revisions may

  11. Microsoft Word - DOE-ID-INL-13-013.docx

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

    3 SECTION A. Project Title: Advanced Test Reactor (ATR) Primary Coolant Leak Rate Determination System Equipment Replacement SECTION B. Project Description: The purpose of this project is to automate the ATR Primary Coolant Leak Rate Determination System by replacing existing flow transmitters and installing new transmitters to provide a redundant signal. This project is part of an overall effort to implement Leak Before Break (LBB) at the ATR, and will improve accuracy and timeliness, provide

  12. Microsoft Word - DOE-ID-INL-13-014.doc

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

    4 SECTION A. Project Title: Iona Relay Station Maintenance SECTION B. Project Description: This project would periodically perform maintenance related activities in and around an approximate 15 acre area at the Iona Hill Relay Station. Activities would include: maintenance/testing of the emergency generator, facility grounds and road surface repair and upkeep (e.g., grading, snow removal, resurfacing, weed control), building and structure maintenance/repair (e.g., painting, insect control,

  13. Microsoft Word - DOE-ID-INL-13-015.doc

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

    5 SECTION A. Project Title: Relocation of National and Homeland Security (N&HS) activities from Transient Reactor Experiment and Test Facility (TREAT) to Critical Infrastructure Test Range Complex (CITRC) SECTION B. Project Description: The proposed project will relocate Homeland Security personnel who currently reside at TREAT to CITRC. The scope of this environmental checklist is only for the purchase and installation of three modular trailers. Three modular buildings are to be purchased

  14. Microsoft Word - DOE-ID-INL-13-016.doc

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

    6 SECTION A. Project Title: Wildland Fire Chainsaw Training SECTION B. Project Description: The Idaho National Laboratory (INL) fire department is required by the National Wildfire Coordinating Group (NWCG) to have chainsaw packages on each of the Type 4 wildland fire engines. Prior to placing these chainsaws into service, the INL fire department must train firefighters to chainsaw operational and safety protocols, including both classroom and hands-on training in the field. To enable realistic

  15. Microsoft Word - DOE-ID-INL-13-020.doc

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

    0 SECTION A. Project Title: Interim Storage Area for Interim Storage Containers (ISCs) at the Radioactive Scrap and Waste Facility (RSWF) SECTION B. Project Description: Currently, dedicated space is unavailable for above-grade storage of Interim Storage Containers (ISCs) containing 55-gal drums of remote handled transuranic waste (RH-TRU). In the past this waste was packaged in specially constructed liners and placed into the RSWF. When ready for transfer this waste would then be removed from

  16. Microsoft Word - DOE-ID-INL-13-021.doc

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

    1 SECTION A. Project Description: Decommissioning of Shallow Injection Wells (SIW) (13-Test Reactor Area [TRA], 14-TRA, 21- TRA and 26-TRA) at the Advanced Test Reactor (ATR) Complex SECTION B. Project Description: This project will involve the decommissioning of the following Shallow Injection Wells (SIWs) at the Advanced Test Reactor (ATR) Complex: 13-TRA (Idaho Department of Water Resources [IDWR] Permit Number 34X0001020) located near the northeast corner of building TRA-614, 14-TRA (IDWR

  17. Microsoft Word - DOE-ID-INL-13-022.docx

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

    3-022 SECTION A. Project Title: Global Threat Reduction Initiative (GTRI) Irradiated Experiment Shipping Capability SECTION B. Project Description: The General Electric (GE) 2000 Model Cask is currently used to support the Global Threat Reduction Initiative (GTRI) irradiated experiment shipments from the Advanced Test Reactor (ATR) at Idaho National Laboratory's (INL) ATR Complex to the Hot Fuel Examination Facility (HFEF) at INL's Materials and Fuels Complex (MFC). However, due to changes in

  18. Microsoft Word - DOE-ID-INL-13-023.doc

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

    3 SECTION A. Project Title: Test Reactor Area (TRA)-680 Road Widening SECTION B. Project Description: The purpose and need for the proposed action is to widen the gravel interior perimeter road within the Advanced Test Reactor (ATR) Complex at a location near TRA-680 to provide room for vehicles to pass (see Figure 1). The proposed action would widen the road near TRA-680 by placing fill material in an area approximately 16 ft. by 40 ft. Fill material would be obtained from the Monroe Gravel Pit

  19. Microsoft Word - DOE-ID-INL-13-024.docx

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

    24 SECTION A. Project Title: Idaho National Laboratory (INL) Road Sign Installation/Maintenance SECTION B. Project Description: The proposed action is to install new and repair/replace existing road signs and delineator/reflector poles as needed near paved roads and Priority 1 and 2 unpaved roads (as defined in Environmental Checklist (EC) Idaho National Engineering Laboratory (INEL)-02-024) throughout the INL as part of routine maintenance and to improve traffic safety. This includes roads

  20. Microsoft Word - DOE-ID-INL-13-027.doc

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

    27 SECTION A. Project Title: Excess Facilities Deactivation and Demolition SECTION B. Project Description: The purpose of the proposed action is to deactivate, decontaminate, and demolish (DD&D) surplus vacant, inactivated, or soon to be inactivated facilities to reduce lifecycle costs associated with surveillance and maintenance. The proposed action would return the location of the facilities to near original condition. There is limited risk to site personnel posed by remaining hazards

  1. Microsoft Word - DOE-ID-INL-14-002.docx

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

    2 SECTION A. Project Title: Erection and Use of Tension Fabric Structure at the National Security Test Range (NSTR) SECTION B. Project Description: This Environmental Checklist (EC) addresses the erection and use of a tension fabric structure at the National Security Test Range (NSTR). A tension fabric structure is a non-permanent tent-like structure. The tension fabric structure would be placed in the second laydown area at the NSTR and provide personnel with a work area somewhat protected from

  2. Microsoft Word - DOE-ID-INL-14-005.doc

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

    4-005 SECTION A. Project Title: MICROGRID DEMONSTRATION PROJECT SECTION B. Project Description: The current state of the United States (U.S.) electric grid is likely incapable of supporting the Department of Energy (DOE) goal of producing 80% of U.S. electricity from clean energy sources by 2035, as stated in the DOE Strategic Plan, May 2011. Supporting such a goal will require increased system flexibility to reliably integrate new, variable, and diverse resources. The energy generation

  3. Microsoft Word - DOE-ID-INL-14-008.doc

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

    8 SECTION A. Project Title: Relocation of Environmental Monitoring Services Personnel and Equipment SECTION B. Project Description: The Environmental Monitoring Services organization at Idaho National Laboratory (INL) is currently located at the Materials and Fuels Complex (MFC) in building MFC-721, the original Transient Reactor Test Facility (TREAT) Reactor Control Building. The TREAT reactor has been in stand-by mode since 1995, and MFC-721 was converted in to office space and a sample

  4. Microsoft Word - DOE-ID-INL-14-009.docx

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

    4-009 SECTION A. Project Title: Irradiated Materials Characterization Laboratory (IMCL) Equipment Installation Project SECTION B. Project Description: The Department of Energy (DOE) has committed to multi-year funding to install Post Irradiation Examination (PIE) equipment into the Irradiated Materials Characterization Laboratory (IMCL) at the Materials and Fuels Complex (MFC) at Idaho National Laboratory (INL). The proposed action would install a number of capabilities/instruments in IMCL to

  5. Microsoft Word - DOE-ID-INL-14-010.doc

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

    10 SECTION A. Project Title: Hot Fuels and Examination Facility (HFEF) Documented Safety Analysis (DSA) Implementation Tasks SECTION B. Project Description: The Hot Fuels Examination Facility (HFEF) (MFC-785) Documented Safety Analysis (DSA) was upgraded in compliance with DOE- STD-3009 to verify that facility operations could be conducted without undue risk to the public or MFC personnel. The full implementation of the DSA requires procedure and software modifications and implementation of the

  6. Microsoft Word - DOE-ID-INL-14-011.doc

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

    1 SECTION A. Project Title: Shelley-New Sweden Parking Lot Flood Control SECTION B. Project Description: The Department of Energy-owned Shelley-New Sweden parking lot is currently unable to handle the storm water/snow melt runoff in the spring. The culvert to the north of the parking lot drains storm water/snow melt from the adjacent field under the highway and flows to the parking lot. In the spring, the parking lot pools up with storm water/snow melt causing portions of the lot to be unusable.

  7. Microsoft Word - DOE-ID-INL-14-013.doc

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

    3 SECTION A. Project Title: Zero Power Physics Reactor (ZPPR) Documented Safety Analysis (DSA) Implementation Project Tasks SECTION B. Project Description: The Zero Power Physics Reactor (ZPPR) Documented Safety Analysis (DSA) was conducted to verify that facility operations could be conducted without undue risk to the public or Materials and Fuels Complex (MFC) personnel. The DSA identified the need for implementation of the following tasks: 1. Replace 24 high-efficiency particulate air (HEPA)

  8. Microsoft Word - DOE-ID-INL-14-016.docx

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

    16 SECTION A. Project Title: Advanced Test Reactor (ATR) Primary Coolant Pump Motor Starters Replacement SECTION B. Project Description: The proposed action would replace the existing ATR Primary Coolant Pump circuit breakers located in Switchgear 670-E-1 Cubicle 3 & 4 and Switchgear 670-E-2, Cubicles 9 and 10 with Vacuum Starters specifically designed for motor starting applications. Replace the existing electrically operated auxiliary relay with a new electrically operated auxiliary relay

  9. Microsoft Word - DOE-ID-INL-14-020.docx

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

    SECTION A. Project Title: Central Facilities Area (CFA)-623/624 Electric Heat Conversion Project SECTION B. Project Description: The CFA-671 Boilers currently supply steam heat to buildings CFA-601, CFA-623 and CFA-674. Various problems such as steamline leaks/repairs, CFA-671 structural problems, age of the boilers, fuel costs, and upcoming 40 Code of Federal Regulations (CFR) 63 Subpart DDDDD regulations has led to the decision to replace the steam heat in these buildings with electric heat.

  10. Microsoft Word - DOE-ID-INL-14-023.docx

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

    4-023 SECTION A. Project Title: Materials and Fuels Complex (MFC) Fire Water Replacement and Upgrades SECTION B. Project Description: The existing combined fire/potable water supply and distribution system at Materials and Fuels Complex (MFC), including the Transient Reactor Test Facility (TREAT), has been identified as being unreliable since a single fault can prevent the system from operating as required. Additionally, the fire water supply to TREAT has also been found inadequate based upon

  11. Microsoft Word - DOE-ID-INL-14-024.docx

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

    4 SECTION A. Project Title: Idaho National Laboratory (INL) Sustainability Program 90-Day Guiding Principles Project SECTION B. Project Description: Idaho National Laboratory (INL) adopted the major programmatic sustainability goals contained in the Executive and Department of Energy (DOE) Orders and the Strategic Sustainability Performance Plan. Sustainability is a performance improvement strategy that is readily validated through performance measurement and reporting. INL Sustainability

  12. Microsoft Word - DOE-ID-INL-14-025.docx

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

    5 SECTION A. Project Title: Fiscal Year (FY)-14 Wireless Test Bed Fiber Optic Cable to Gate 1 and Experimental Breeder Reactor-I (EBR-I) Cell Sites SECTION B. Project Description: The purpose of this work is to install new fiber optic cable to support new wireless technology (4G) which will not work as well on existing microwave backhaul technology. Future projects using the new cable will be separately documented. New fiber optic cables would be installed between the Idaho National Laboratory

  13. Microsoft Word - DOE-ID-INL-14-031.docx

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

    1 SECTION A. Project Title: Energy Systems Laboratory Process Demonstration Unit Pellet Mill Exhaust Stack Installation SECTION B. Project Description: . The proposed action is needed to allow operation of the Process Demonstration Unit (PDU) at the Energy Systems Laboratory (ESL) (Idaho Falls [IF]-685). Bioenergy research and development (R&D) activities/operations that take place at the ESL have been captured in environmental checklist Idaho National Laboratory (INL)-10-003. Environmental

  14. Microsoft Word - DOE-ID-INL-14-034.docx

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

    4 SECTION A. Project Title: Materials and Fuels Complex (MFC)-765 Fuel Conditioning Facility (FCF) Fire Suppression System SECTION B. Project Description: The project scope consists of modifying three (3) separate sections of the FCF (MFC-765) Fire Suppression System to convert them from wet pipes to dry pipes. These modifications are required to comply with National Fire Protection Association (NFPA) requirements for maximum glycol/water ratios per NFPA 13 - Standard for the Installation of

  15. Microsoft Word - DOE-ID-INL-14-035.docx

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

    5 SECTION A. Project Title: Cold Waste Outdoor Pump Site System Upgrade SECTION B. Project Description: The proposed action would install new replacement equipment as part of upgrades to Test Reactor Area (TRA0-703 (Advanced Test Reactor [ATR] Cold Waste Pit) to achieve more system reliability and to address safety concerns. The current system utilizes a single motor starter cabinet (with three motor starters), push buttons, water level monitoring/pump control float type system and relays to

  16. Microsoft Word - DOE-ID-INL-14-036.docx

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

    6 SECTION A. Project Title: Green Room Mill Replacement Project SECTION B. Project Description: The proposed action would replace the Bridgeport mill in the Green Room at the Advanced Test Reactor (ATR) with the Sharp mill that is currently located in building Test Reactor Area (TRA)-653 (south east side) at the ATR Complex. The Sharp mill located in TRA-653 (south west side) would be relocated to the south east side to replace the Sharp mill being moved to the Green Room. The Bridgeport mill

  17. Microsoft Word - DOE-ID-INL-14-037.docx

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

    7 SECTION A. Project Title: Materials and Fuel Complex (MFC) Ladder and Platform Modifications SECTION B. Project Description: The scope of work is to modify, replace, or remove fixed ladders and platforms at various locations at MFC that do not meet safety requirements including:  MFC-785 Hot Fuel Examination Facility (HFEF) o Exterior Stack Platform Modification o Exterior South Second Level Ladder o Interior Basement ROV-3 Ladder and Platform o Interior Basement Generator Room Ladder o

  18. Microsoft Word - DOE-ID-INL-14-038.docx

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

    4-038 SECTION A. Project Title: Research and Development Activities at the Idaho National Laboratory (INL) Site Facilities (Overarching) SECTION B. Project Description: The proposed action would perform analytical and research and development (R&D) activities in numerous laboratories and R&D facilities located at the Idaho National Laboratory (INL), including INL facilities located at the Advanced Test Reactor (ATR) Complex, Central Facilities Area (CFA), Idaho Nuclear Technology and

  19. Microsoft Word - DOE-ID-INL-14-039.docx

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    9 SECTION A. Project Title: Idaho Falls (IF)-639 (North Holmes Laboratory [NHL]) Machine Installation SECTION B. Project Description: The North Holmes Laboratory (NHL, IF-639) Machine Shop requires several large turning centers and milling machines. The proposed action would relocate five existing machines within the facility, in order to provide sufficient space for two additional (new) turning centers and milling machines. These machines will require electrical feeds and receptacles, as well

  20. Microsoft Word - DOE-ID-INL-14-040.docx

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

    0 SECTION A. Descriptive Information: Blackfoot Parking Lot Bus Entrance Modifications SECTION B. Project Description: The proposed project would create additional parking on, and an alternate entrance to, the Blackfoot parking lot on Idaho National Laboratory (INL) leased property in Blackfoot, Idaho. The purpose is to redirect the traffic flow of the buses coming into the parking lot to make it safer to pick-up and drop off bus passengers and to create additional parking spaces. The project