National Library of Energy BETA

Sample records for flagstaff az salt

  1. Flagstaff, Arizona: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    a stub. You can help OpenEI by expanding it. Flagstaff is a city in Coconino County, Arizona. It falls under Arizona's 1st congressional district.12 Contents 1 Registered...

  2. Photovoltaic Power Generation in Flagstaff | GE Global Research

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

    Photovoltaic Power Generation in Flagstaff Click to email this to a friend (Opens in new window) Share on Facebook (Opens in new window) Click to share (Opens in new window) Click...

  3. Workplace Charging Challenge Partner: Salt River Project | Department of

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

    Energy Salt River Project Workplace Charging Challenge Partner: Salt River Project Workplace Charging Challenge Partner: Salt River Project Joined the Challenge: December 2014 Headquarters: Tempe, AZ Charging Locations: Phoenix, AZ; Scottsdale, AZ; Tempe, AZ; Tolleson, AZ Domestic Employees: 4,900 The mission of Salt River Project's (SRP) Electric Vehicle Initiative is to encourage greater use of clean energy transportation. Under this program, SRP's headquarters received two Level 2

  4. AZ Biodiesel | Open Energy Information

    Open Energy Info (EERE)

    AZ Biodiesel Jump to: navigation, search Name: AZ Biodiesel Place: Chandler, Arizona Zip: 85225 Product: AZ Biodiesel is a biodiesel producer that announced plans in July 2008 to...

  5. A-Z Link

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

    Use or Search the A-Z Index (this page) 2. Use search.lbl.gov powered by Google. 3. Use DS The Directory of both People and Organizations Frequently Requested from the A-Z Index...

  6. SPECKLE INTERFEROMETRY AT THE USNO FLAGSTAFF STATION: OBSERVATIONS OBTAINED IN 2008 AND NINE NEW ORBITS

    SciTech Connect (OSTI)

    Hartkopf, William I.; Mason, Brian D. E-mail: bdm@usno.navy.mil

    2011-08-15

    Results are presented for 299 speckle interferometric observations of double stars, obtained in 2008 at the USNO Flagstaff Station using the 1.55 m Kaj Strand Astrometric Reflector. Separations range from 0.''15 to 9.''88, with a median of 2.''22. This observing run concentrated on neglected systems, as well as systems in need of improved orbital elements; new orbital solutions have been determined for nine systems as a result.

  7. Category:Tucson, AZ | Open Energy Information

    Open Energy Info (EERE)

    VFullServiceRestaurant Tucson AZ Arizona Public Service Co.png SVFullServiceRestauran... 75 KB SVHospital Tucson AZ Arizona Public Service Co.png SVHospital Tucson AZ A... 88 KB...

  8. Openei test page | Open Energy Information

    Open Energy Info (EERE)

    Openei test page Jump to: navigation, search Net value of PV generation under various rate structures and penetration levels for a(n) FullServiceRestaurant in Flagstaff,AZ (Salt...

  9. US Mnt(S) AZ Site Consumption

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

    Mnt(S) AZ Site Consumption million Btu $0 $500 $1,000 $1,500 $2,000 $2,500 US Mnt(S) AZ Expenditures dollars ALL ENERGY average per household (excl. transportation) 0 3,000 6,000 9,000 12,000 15,000 US Mnt(S) AZ Site Consumption kilowatthours $0 $500 $1,000 $1,500 $2,000 US Mnt(S) AZ Expenditures dollars ELECTRICITY ONLY average per household * Arizona households use 66 million Btu of energy per home, 26% less than the U.S. average. * The combination of lower than average site consumption of all

  10. City of Williams - AZ, Arizona (Utility Company) | Open Energy...

    Open Energy Info (EERE)

    Williams - AZ, Arizona (Utility Company) Jump to: navigation, search Name: City of Williams - AZ Place: Arizona Phone Number: 928-635-2667 or 928-635-4451 Website:...

  11. Sasabe, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic...

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

    Sasabe, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic Feet) Sasabe, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug ...

  12. RAPID/Roadmap/6-AZ-b | Open Energy Information

    Open Energy Info (EERE)

    Permitting Information Desktop Toolkit BETA About Bulk Transmission Geothermal Hydropower Solar Tools Contribute Contact Us Construction Storm Water Permit (6-AZ-b) The Clean Water...

  13. RAPID/Roadmap/8-AZ-a | Open Energy Information

    Open Energy Info (EERE)

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

  14. WM'02 Conference, February 24-28, 2002, Tucson, AZ

    Office of Scientific and Technical Information (OSTI)

    WM'02 Conference, February 24-28, 2002, Tucson, AZ 1 COMPOSITION OF INSOLUBLE RESIDUES GENERATED DURING SPENT FUEL DISSOLUTION Y. Pokhitonov, V. Aleksandruk, B. Bibichev, G....

  15. RAPID/Roadmap/8-AZ-c | Open Energy Information

    Open Energy Info (EERE)

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

  16. A-Z Index | Jefferson Lab

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

    A-Z Index A B C D E F G H I J K L M N O P Q R S T U V W XYZ A Abbreviations, energy related About U.S. Natural Gas Pipelines (U.S. & state) Acid rain (U.S., Census division, & state) Definition Emissions data Overview Acquisitions and Divestitures by Foreign Direct Investors in U.S. Energy (report discontinued) Activities for kids Additions to storage (natural gas; includes U.S. & state) Underground, by all operators Underground, by storage type Liquefied natural gas additions and

  17. ANALYSIS RESULTS FOR BUILDING 241 702-AZ A TRAIN

    SciTech Connect (OSTI)

    DUNCAN JB; FRYE JM; COOKE CA; LI SW; BROCKMAN FJ

    2006-12-13

    This report presents the analyses results for three samples obtained under RPP-PLAN-28509, Sampling and Analysis Plan for Building 241 702-AZ A Train. The sampling and analysis was done in response to problem evaluation request number PER-2004-6139, 702-AZ Filter Rooms Need Radiological Cleanup Efforts.

  18. 241-AZ Farm Annulus Extent of Condition Baseline Inspection

    SciTech Connect (OSTI)

    Engeman, Jason K.; Girardot, Crystal L.; Vazquez, Brandon J.

    2013-05-15

    This report provides the results of the comprehensive annulus visual inspection for tanks 241- AZ-101 and 241-AZ-102 performed in fiscal year 2013. The inspection established a baseline covering about 95 percent of the annulus floor for comparison with future inspections. Any changes in the condition are also included in this document.

  19. Nogales, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic...

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

    Million Cubic Feet) Nogales, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2011 39 24 19 15 18 16 15 16 16 18 ...

  20. Sandia Energy - Molten Salt Test Loop Melted Salt

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

    Salt Home Renewable Energy Energy News Concentrating Solar Power Solar Molten Salt Test Loop Melted Salt Previous Next Molten Salt Test Loop Melted Salt The Molten Salt Test...

  1. EA-1797: Agua Caliente Solar Project in Yuma County, AZ | Department...

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

    7: Agua Caliente Solar Project in Yuma County, AZ EA-1797: Agua Caliente Solar Project in Yuma County, AZ November 1, 2010 EA-1797: Final Environmental Assessment Loan Guarantee ...

  2. Nogales, AZ Liquefied Natural Gas Exports to Mexico (Million...

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

    Million Cubic Feet) Nogales, AZ Liquefied Natural Gas Exports to Mexico (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2012 8.938 8.916 5.241 3.570 4.280 ...

  3. Douglas, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic...

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

    Million Cubic Feet) Douglas, AZ Natural Gas Pipeline Exports to Mexico (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2011 3,165 2,613 2,982 2,580 3,630 ...

  4. Mixer pump test plan for double shell tank AZ-101

    SciTech Connect (OSTI)

    STAEHR, T.W.

    1999-05-12

    Mixer pump systems have been chosen as the method for retrieval of tank wastes contained in double shell tanks at Hanford. This document describes the plan for testing and demonstrating the ability of two 300 hp mixer pumps to mobilize waste in tank AZ-101. The mixer pumps, equipment and instrumentation to monitor the test were installed by Project W-151.

  5. DOE Zero Energy Ready Home Case Study: Mandalay Homes, Phoenix, AZ,

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

    Affordable | Department of Energy Phoenix, AZ, Affordable DOE Zero Energy Ready Home Case Study: Mandalay Homes, Phoenix, AZ, Affordable DOE Zero Energy Ready Home Case Study: Mandalay Homes, Phoenix, AZ, Affordable Case study of a DOE Zero Energy Ready Home in Phoenix, AZ, that scored HERS 58 without PV or HERS 38 with PV. This 1,700-square-foot affordable home has R-21 framed walls, a sealed closed-cell spray foamed attic, an air-source heat pump with forced air, and a solar combo system

  6. DOE Zero Energy Ready Home Case Study: Mandalay Homes, Prescott Valley, AZ

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

    | Department of Energy Mandalay Homes, Prescott Valley, AZ DOE Zero Energy Ready Home Case Study: Mandalay Homes, Prescott Valley, AZ DOE Zero Energy Ready Home Case Study: Mandalay Homes, Prescott Valley, AZ Case study of a DOE Zero Energy Ready home in northern AZ that achieved a HERS score of 48 without PV or 25 if 3.5 kW PV were added. The two-story, 2,469-ft2 production home has 2x4 walls filled with R-13 open-cell spray foam plus 1-in. rigid foam over plywood sheathing, a sealed R-20

  7. 241-AZ Tank Farm Construction Extent of Condition Review for Tank Integrity

    SciTech Connect (OSTI)

    Barnes, Travis J.; Boomer, Kayle D.; Gunter, Jason R.; Venetz, Theodore J.

    2013-07-30

    This report provides the results of an extent of condition construction history review for tanks 241-AZ-101 and 241-AZ-102. The construction history of the 241-AZ tank farm has been reviewed to identify issues similar to those experienced during tank AY-102 construction. Those issues and others impacting integrity are discussed based on information found in available construction records, using tank AY-102 as the comparison benchmark. In the 241-AZ tank farm, the second DST farm constructed, both refractory quality and tank and liner fabrication were improved.

  8. Salt Waste Processing Initiatives

    Office of Environmental Management (EM)

    Patricia Suggs Salt Processing Team Lead Assistant Manager for Waste Disposition Project Office of Environmental Management Savannah River Site Salt Waste Processing Initiatives 2 ...

  9. Southwest Wind Power | Open Energy Information

    Open Energy Info (EERE)

    Power Jump to: navigation, search Name: Southwest Wind Power Place: Flagstaff, AZ Website: www.windenergy.com References: Southwest Wind Power1 Information About Partnership...

  10. Distributed Wind Energy Association | Open Energy Information

    Open Energy Info (EERE)

    Energy Association Jump to: navigation, search Name: Distributed Wind Energy Association Address: PO Box 1861 Place: Flagstaff, AZ Zip: 86002 Phone Number: 928-255-0214 Website:...

  11. Northern Arizona University | Open Energy Information

    Open Energy Info (EERE)

    University Jump to: navigation, search Name: Northern Arizona University Place: Flagstaff, AZ Zip: 86011 Phone Number: 928-523-0715 Website: nau.edu Coordinates: 35.1905403,...

  12. Nogales, AZ Liquefied Natural Gas Exports (Million Cubic Feet)

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

    (Million Cubic Feet) Nogales, AZ Liquefied Natural Gas Exports (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2013 12 16 2014 15 12 10 8 6 3 3 2 3 5 12 14 2015 12 9 9 9 8 5 3 2 3 7 15 22 2016 19 13 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 04/29/2016 Next Release Date: 05/31/2016 Referring Pages: U.S.

  13. Nogales, AZ Liquefied Natural Gas Exports to Mexico

    Gasoline and Diesel Fuel Update (EIA)

    (Million Cubic Feet) Nogales, AZ Liquefied Natural Gas Exports (Million Cubic Feet) Year Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec 2013 12 16 2014 15 12 10 8 6 3 3 2 3 5 12 14 2015 12 9 9 9 8 5 3 2 3 7 15 22 2016 19 13 - = No Data Reported; -- = Not Applicable; NA = Not Available; W = Withheld to avoid disclosure of individual company data. Release Date: 04/29/2016 Next Release Date: 05/31/2016 Referring Pages: U.S. Feet)

    Decade Year-0 Year-1 Year-2 Year-3 Year-4 Year-5 Year-6

  14. Electrolyte salts for power sources

    DOE Patents [OSTI]

    Doddapaneni, Narayan; Ingersoll, David

    1995-01-01

    Electrolyte salts for power sources comprising salts of phenyl polysulfonic acids and phenyl polyphosphonic acids. The preferred salts are alkali and alkaline earth metal salts, most preferably lithium salts.

  15. EA-1797: Agua Caliente Solar Project in Yuma County, AZ | Department of

    Energy Savers [EERE]

    Energy 7: Agua Caliente Solar Project in Yuma County, AZ EA-1797: Agua Caliente Solar Project in Yuma County, AZ November 1, 2010 EA-1797: Final Environmental Assessment Loan Guarantee for the Agua Caliente Solar Project in Yuma County, Arizona November 24, 2010 EA-1797: Finding of No Significant Impact Agua Caliente Solar Project in Yuma

  16. Slime-busting Salt

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

    past issues All Issues submit Slime-busting Salt A potential new treatment gets bacteria deep in their hiding places May 1, 2015 Slime-busting Salt Biofilms are made of...

  17. Ancient Salt Beds

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

    Ancient Salt Beds Dr. Jack Griffith The key to the search for life on other planets may go through WIPP's ancient salt beds. In 2008, a team of scientists led by Jack Griffith, from the University of North Carolina, Chapel Hill, retrieved salt samples from the WIPP underground and studied them with a transmission electron microscopy lab at the Lineberger Comprehensive Cancer Center of the University of North Carolina School of Medicine. In examining fluid inclusions in the salt and solid halite

  18. Influence of Aluminum Content on Grain Refinement and Strength of AZ31 Magnesium GTA Weld Metal

    SciTech Connect (OSTI)

    Babu, N. Kishore; Cross, Carl E.

    2012-06-28

    The goal is to characterize the effect of Al content on AZ31 weld metal, the grain size and strength, and examine role of Al on grain refinement. The approach is to systematically vary the aluminum content of AZ31 weld metal, Measure average grain size in weld metal, and Measure cross-weld tensile properties and hardness. Conclusions are that: (1) increased Al content in AZ31 weld metal results in grain refinement Reason: higher undercooling during solidification; (2) weld metal grain refinement resulted in increased strength & hardness Reason: grain boundary strengthening; and (3) weld metal strength can be raised to wrought base metal levels.

  19. 2015 Electrochemical Energy Summit at the 228th ECS Meeting (Phoenix, AZ)

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

    2015 DOE National Cleanup Workshop 2015 DOE National Cleanup Workshop Addthis 1 of 5 2 of 5 3 of 5 4 of 5 5 of 5 - JCAP

    2015 Electrochemical Energy Summit at the 228th ECS Meeting (Phoenix, AZ) 2015 Electrochemical Energy Summit at the 228th ECS Meeting (Phoenix, AZ) Sun, Oct 11, 2015 4:30pm 16:30 Fri, Oct 16, 2015 5:30pm 17:30 Phoenix, AZ USA Harry Atwater, "Artificial Photosynthesis: Progress and Prospects" View presentation here Matthew McDowell, "New Advances in

  20. File:USDA-CE-Production-GIFmaps-AZ.pdf | Open Energy Information

    Open Energy Info (EERE)

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

  1. File:NREL-az-80m.pdf | Open Energy Information

    Open Energy Info (EERE)

    NREL-az-80m.pdf Jump to: navigation, search File File history File usage Arizona Annual Average Wind Speed at 80 Meters Size of this preview: 463 599 pixels. Other resolution:...

  2. Engineering task plan for the 241-AZ-101 waste tank color video camera system

    SciTech Connect (OSTI)

    Robinson, R.S., Westinghouse Hanford

    1996-07-01

    This Engineering Task Plan (ETP) is to be distributed to communicate the design basis of the 241-AZ-101 camera system and to define system requirements and associated responsibilities.

  3. BASIN BLAN CO BLAN CO S OT ERO IGNAC IO-BLANCO AZ TEC BALLAR

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

    AZ UT NM CO 1 2 Index Map for 2 Paradox-San Juan Panels 2001 Reserve Summary for All ... UPUT (Uinta-Piceance Basin and Utah). Map created June 2005; projection is UTM-13, ...

  4. Oxide Film and Porosity Defects in Magnesium Alloy AZ91

    SciTech Connect (OSTI)

    Wang, Liang [Mississippi State University (MSU); Rhee, Hongjoo [Mississippi State University (MSU); Felicelli, Sergio D. [Mississippi State University (MSU); Sabau, Adrian S [ORNL; Berry, John T. [Mississippi State University (MSU)

    2009-01-01

    Porosity is a major concern in the production of light metal parts. This work aims to identify some of the mechanisms of microporosity formation in magnesium alloy AZ91. Microstructure analysis was performed on several samples obtained from gravity-poured ingots in graphite plate molds. Temperature data during cooling was acquired with type K thermocouples at 60 Hz at three locations of each casting. The microstructure of samples extracted from the regions of measured temperature was then characterized with optical metallography. Tensile tests and conventional four point bend tests were also conducted on specimens cut from the cast plates. Scanning electron microscopy was then used to observe the microstructure on the fracture surface of the specimens. The results of this study revealed the existence of abundant oxide film defects, similar to those observed in aluminum alloys. Remnants of oxide films were detected on some pore surfaces, and folded oxides were observed in fracture surfaces indicating the presence of double oxides entrained during pouring.

  5. Dosimetry using silver salts

    DOE Patents [OSTI]

    Warner, Benjamin P.

    2003-06-24

    The present invention provides a method for detecting ionizing radiation. Exposure of silver salt AgX to ionizing radiation results in the partial reduction of the salt to a mixture of silver salt and silver metal. The mixture is further reduced by a reducing agent, which causes the production of acid (HX) and the oxidized form of the reducing agent (R). Detection of HX indicates that the silver salt has been exposed to ionizing radiation. The oxidized form of the reducing agent (R) may also be detected. The invention also includes dosimeters employing the above method for detecting ionizing radiation.

  6. Salt Selected (FINAL)

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

    and Technical Information Salt Lake Community College Spotlights Home DOE Applauds SLCC Science and Technical Programs Salt Lake City, Utah Architectural Technology Biology Biotechnology Biomanufacturing Chemistry Computer Science Electric Sector Training Energy Management Engineering Geographic Information Sciences Geosciences InnovaBio Manufacturing & Mechanical Engineering Technology Mathematics Physics SLCC Partners with DOE's Rocky Mountain Solar Training Program This program is a

  7. Hydroxycarboxylic acids and salts

    DOE Patents [OSTI]

    Kiely, Donald E; Hash, Kirk R; Kramer-Presta, Kylie; Smith, Tyler N

    2015-02-24

    Compositions which inhibit corrosion and alter the physical properties of concrete (admixtures) are prepared from salt mixtures of hydroxycarboxylic acids, carboxylic acids, and nitric acid. The salt mixtures are prepared by neutralizing acid product mixtures from the oxidation of polyols using nitric acid and oxygen as the oxidizing agents. Nitric acid is removed from the hydroxycarboxylic acids by evaporation and diffusion dialysis.

  8. Molten salt electrolyte separator

    DOE Patents [OSTI]

    Kaun, T.D.

    1996-07-09

    The patent describes a molten salt electrolyte/separator for battery and related electrochemical systems including a molten electrolyte composition and an electrically insulating solid salt dispersed therein, to provide improved performance at higher current densities and alternate designs through ease of fabrication. 5 figs.

  9. Water purification using organic salts

    DOE Patents [OSTI]

    Currier, Robert P.

    2004-11-23

    Water purification using organic salts. Feed water is mixed with at least one organic salt at a temperature sufficiently low to form organic salt hydrate crystals and brine. The crystals are separated from the brine, rinsed, and melted to form an aqueous solution of organic salt. Some of the water is removed from the aqueous organic salt solution. The purified water is collected, and the remaining more concentrated aqueous organic salt solution is reused.

  10. Ultrasonic Spot Welding of AZ31B to Galvanized Mild Steel

    SciTech Connect (OSTI)

    Pan, Dr. Tsung-Yu; Franklin, Teresa; Pan, Professor Jwo; Brown, Elliot; Santella, Michael L

    2010-01-01

    Ultrasonic spot welds were made between sheets of 0.8-mm-thick hot-dip-galvanized mild steel and 1.6-mm-thick AZ31B-H24. Lap-shear strengths of 3.0-4.2 kN were achieved with weld times of 0.3-1.2 s. Failure to achieve strong bonding of joints where the Zn coating was removed from the steel surface indicate that Zn is essential to the bonding mechanism. Microstructure characterization and microchemical analysis indicated temperatures at the AZ31-steel interfaces reached at least 344 C in less than 0.3 s. The elevated temperature conditions promoted annealing of the AZ31-H24 metal and chemical reactions between it and the Zn coating.

  11. Amine salts of nitroazoles

    DOE Patents [OSTI]

    Kienyin Lee; Stinecipher, M.M.

    1993-10-26

    Compositions of matter, a method of providing chemical energy by burning said compositions, and methods of making said compositions are described. These compositions are amine salts of nitroazoles. 1 figure.

  12. Salt Repository Research,

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

    of Downtown Santa Fe. Begins 10 AM. Map will be provided Day 2 September 9 - Tuesday TM-behavior of salt 08:30-08:50 Update on the "Joint Project on Constitutive Laws benchmark"...

  13. Salt Repository Research,

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

    Salt Lake City Gamma Shield Thunder Exercise Concludes National Nuclear Security Administration (NNSA) and the FBI announced today the completion of the Gamma Shield Thunder counterterrorism table-top exercise at LDS Hospital. The exercise is part of NNSA's Silent Thunder table-top series, which is aimed at giving federal, state and local

    6 th US/German Workshop on Salt Repository Research, Design, and Operation Hotel Pullmann Dresden Newa Dresden September 7 - 9, 2015 September 7- Monday

  14. Flagstaff, Arizona: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Arizona Wind Energy LLC References US Census Bureau Incorporated place and minor civil division population dataset (All States, all geography) US Census Bureau...

  15. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101 & 241AZ-102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    SciTech Connect (OSTI)

    DUNCAN JB; HUBER HJ

    2011-04-21

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-l0-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FBSR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-5.2.1-2010-001, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using Hanford Waste Samples.

  16. Fundamental Properties of Salts

    SciTech Connect (OSTI)

    Toni Y Gutknecht; Guy L Fredrickson

    2012-11-01

    Thermal properties of molten salt systems are of interest to electrorefining operations, pertaining to both the Fuel Cycle Research & Development Program (FCR&D) and Spent Fuel Treatment Mission, currently being pursued by the Department of Energy (DOE). The phase stability of molten salts in an electrorefiner may be adversely impacted by the build-up of fission products in the electrolyte. Potential situations that need to be avoided, during electrorefining operations, include (i) fissile elements build up in the salt that might approach the criticality limits specified for the vessel, (ii) electrolyte freezing at the operating temperature of the electrorefiner due to changes in the liquidus temperature, and (iii) phase separation (non-homogenous solution). The stability (and homogeneity) of the phases can be monitored by studying the thermal characteristics of the molten salts as a function of impurity concentration. Simulated salt compositions consisting of the selected rare earth and alkaline earth chlorides, with a eutectic mixture of LiCl-KCl as the carrier electrolyte, were studied to determine the melting points (thermal characteristics) using a Differential Scanning Calorimeter (DSC). The experimental data were used to model the liquidus temperature. On the basis of the this data, it became possible to predict a spent fuel treatment processing scenario under which electrorefining could no longer be performed as a result of increasing liquidus temperatures of the electrolyte.

  17. Gas releases from salt

    SciTech Connect (OSTI)

    Ehgartner, B.; Neal, J.; Hinkebein, T.

    1998-06-01

    The occurrence of gas in salt mines and caverns has presented some serious problems to facility operators. Salt mines have long experienced sudden, usually unexpected expulsions of gas and salt from a production face, commonly known as outbursts. Outbursts can release over one million cubic feet of methane and fractured salt, and are responsible for the lives of numerous miners and explosions. Equipment, production time, and even entire mines have been lost due to outbursts. An outburst creates a cornucopian shaped hole that can reach heights of several hundred feet. The potential occurrence of outbursts must be factored into mine design and mining methods. In caverns, the occurrence of outbursts and steady infiltration of gas into stored product can effect the quality of the product, particularly over the long-term, and in some cases renders the product unusable as is or difficult to transport. Gas has also been known to collect in the roof traps of caverns resulting in safety and operational concerns. The intent of this paper is to summarize the existing knowledge on gas releases from salt. The compiled information can provide a better understanding of the phenomena and gain insight into the causative mechanisms that, once established, can help mitigate the variety of problems associated with gas releases from salt. Outbursts, as documented in mines, are discussed first. This is followed by a discussion of the relatively slow gas infiltration into stored crude oil, as observed and modeled in the caverns of the US Strategic Petroleum Reserve. A model that predicts outburst pressure kicks in caverns is also discussed.

  18. Salt Repository Research,

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

    th US/German Workshop on Salt Repository Research, Design, and Operation Hotel Pullman Dresden Newa September 7 - 9, 2015 September 7- Monday 08:00-08:30 Registration 08:30-08:50 Welcome by the organizers T. Lautsch, DBE F. Hansen, SNL W. Steininger, PTKA 08:50-09:15 Welcome by BMWi U. Borak, BMWi 09:15-09:30 Welcome by USDOE N. Buschman, US DOE 09:30-10:00 NEA Salt Club J. Mönig, GRS SAFETY CASE ISSUES 10:00-10:30 WIPP recovery F. Hansen, SNL 10:30-11:00 Coffee break and photo event

  19. Salt Wells Geothermal Area | Open Energy Information

    Open Energy Info (EERE)

    Salt Wells Geothermal Area Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Salt Wells Geothermal Area Contents 1 Area Overview 2 History and Infrastructure 2.1 Salt...

  20. Electrolytic orthoborate salts for lithium batteries (Patent...

    Office of Scientific and Technical Information (OSTI)

    Electrolytic orthoborate salts for lithium batteries Title: Electrolytic orthoborate salts for lithium batteries Orthoborate salts suitable for use as electrolytes in lithium ...

  1. Sandia Energy - Molten Salt Test Loop Commissioning

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

    Energy Energy News EC News & Events Concentrating Solar Power Solar Molten Salt Test Loop Commissioning Previous Next Molten Salt Test Loop Commissioning The Molten Salt...

  2. Actinide removal from spent salts

    DOE Patents [OSTI]

    Hsu, Peter C.; von Holtz, Erica H.; Hipple, David L.; Summers, Leslie J.; Adamson, Martyn G.

    2002-01-01

    A method for removing actinide contaminants (uranium and thorium) from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents are added to precipitate the thorium as thorium oxide and/or the uranium as either uranium oxide or as a diuranate salt. The precipitated materials are filtered, dried and packaged for disposal as radioactive waste. About 90% of the thorium and/or uranium present is removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 0.1 ppm of thorium or uranium.

  3. Metals removal from spent salts

    DOE Patents [OSTI]

    Hsu, Peter C.; Von Holtz, Erica H.; Hipple, David L.; Summers, Leslie J.; Brummond, William A.; Adamson, Martyn G.

    2002-01-01

    A method and apparatus for removing metal contaminants from the spent salt of a molten salt oxidation (MSO) reactor is described. Spent salt is removed from the reactor and analyzed to determine the contaminants present and the carbonate concentration. The salt is dissolved in water, and one or more reagents may be added to precipitate the metal oxide and/or the metal as either metal oxide, metal hydroxide, or as a salt. The precipitated materials are filtered, dried and packaged for disposal as waste or can be immobilized as ceramic pellets. More than about 90% of the metals and mineral residues (ashes) present are removed by filtration. After filtration, salt solutions having a carbonate concentration >20% can be spray-dried and returned to the reactor for re-use. Salt solutions containing a carbonate concentration <20% require further clean-up using an ion exchange column, which yields salt solutions that contain less than 1.0 ppm of contaminants.

  4. Best Practices Case Study: John Wesley Miller Companies - Armory Park Del Sol, Tucson, AZ

    SciTech Connect (OSTI)

    2009-10-01

    Case study of John Wesley Miller Companies, who built two net zero energy homes plus 97 other solar homes in Tucson, AZ. Masonry block walls with rigid foam exterior sheathing, rigid foam over the roof deck plus R-38 in the attic, ducts in conditioned space, 4.2 kW and 5.7 kW photovoltaics and solar water heating yielded HERS scores of 0 on the two homes.

  5. Test plan: Laboratory-scale testing of the first core sample from Tank 102-AZ

    SciTech Connect (OSTI)

    Morrey, E.V.

    1996-03-01

    The overall objectives of the Radioactive Process/Product Laboratory Testing (RPPLT), WBS 1.2.2.05.05, are to confirm that simulated HWVP feed and glass are representative of actual radioactive HWVP feed and glass and to provide radioactive leaching and glass composition data to WFQ. This study will provide data from one additional NCAW core sample (102-AZ Core 1) for these purposes.

  6. DOE Zero Ready Home Case Study: Mandalay Homes, Pronghorn Ranch,Prescott Valley, AZ

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

    Mandalay Homes Pronghorn Ranch Prescott Valley, AZ DOE ZERO ENERGY READY HOME(tm) The U.S. Department of Energy invites home builders across the country to meet the extraordinary levels of excellence and quality specified in DOE's Zero Energy Ready Home program (formerly known as Challenge Home). Every DOE Zero Energy Ready Home starts with ENERGY STAR Certified Homes Version 3.0 for an energy-efficient home built on a solid foundation of building science research. Advanced technologies are

  7. Salt Repository Research,

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

    on Salt Repository Research, Design, and Operation La Fonda Hotel Santa Fe, New Mexico September 7 - 11, 2014 Please join us Sunday September 7, 2014 for a welcome and reception at the La Fonda Hotel hosted by Sandia National Laboratories beginning at 6:00 PM. Day 1 Technical Agenda September 8 - Monday 08:00-08:45 Sign-in and distribution of meeting materials 08:45-09:45 Welcome addresses H.C. Pape (BMWi) US-DOE Offices Highlights of US/German Collaboration F. Hansen (SNL) W. Steininger (PTKA)

  8. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, Ian D.; Poris, Jaime; Huggins, Robert A.

    1982-02-09

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  9. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, Ian D.; Poris, Jaime; Huggins, Robert A.

    1983-01-01

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400.degree.-500.degree. C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell (10) which may be operated at temperatures between about 100.degree.-170.degree. C. Cell (10) comprises an electrolyte (16), which preferably includes lithium nitrate, and a lithium or lithium alloy electrode (12).

  10. Molten salt lithium cells

    DOE Patents [OSTI]

    Raistrick, I.D.; Poris, J.; Huggins, R.A.

    1980-07-18

    Lithium-based cells are promising for applications such as electric vehicles and load-leveling for power plants since lithium is very electropositive and light weight. One type of lithium-based cell utilizes a molten salt electrolyte and is operated in the temperature range of about 400 to 500/sup 0/C. Such high temperature operation accelerates corrosion problems and a substantial amount of energy is lost through heat transfer. The present invention provides an electrochemical cell which may be operated at temperatures between about 100 to 170/sup 0/C. The cell is comprised of an electrolyte, which preferably includes lithium nitrate, and a lithium or lithium alloy electrode.

  11. Electrolyte salts for nonaqueous electrolytes

    DOE Patents [OSTI]

    Amine, Khalil; Zhang, Zhengcheng; Chen, Zonghai

    2012-10-09

    Metal complex salts may be used in lithium ion batteries. Such metal complex salts not only perform as an electrolyte salt in a lithium ion batteries with high solubility and conductivity, but also can act as redox shuttles that provide overcharge protection of individual cells in a battery pack and/or as electrolyte additives to provide other mechanisms to provide overcharge protection to lithium ion batteries. The metal complex salts have at least one aromatic ring. The aromatic moiety may be reversibly oxidized/reduced at a potential slightly higher than the working potential of the positive electrode in the lithium ion battery. The metal complex salts may also be known as overcharge protection salts.

  12. Batteries using molten salt electrolyte

    DOE Patents [OSTI]

    Guidotti, Ronald A.

    2003-04-08

    An electrolyte system suitable for a molten salt electrolyte battery is described where the electrolyte system is a molten nitrate compound, an organic compound containing dissolved lithium salts, or a 1-ethyl-3-methlyimidazolium salt with a melting temperature between approximately room temperature and approximately 250.degree. C. With a compatible anode and cathode, the electrolyte system is utilized in a battery as a power source suitable for oil/gas borehole applications and in heat sensors.

  13. Electrochromic salts, solutions, and devices

    DOE Patents [OSTI]

    Burrell, Anthony K.; Warner, Benjamin P.; McClesky,7,064,212 T. Mark

    2006-06-20

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  14. Electrochromic Salts, Solutions, and Devices

    DOE Patents [OSTI]

    Burrell, Anthony K.; Warner, Benjamin P.; McClesky, T. Mark

    2008-11-11

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  15. Electrochromic Salts, Solutions, and Devices

    DOE Patents [OSTI]

    Burrell, Anthony K.; Warner, Benjamin P.; McClesky, T. Mark

    2008-10-14

    Electrochromic salts. Electrochromic salts of dicationic viologens such as methyl viologen and benzyl viologen associated with anions selected from bis(trifluoromethylsulfonyl)imide, bis(perfluoroethylsulfonyl)imide, and tris(trifluoromethylsulfonyl)methide are produced by metathesis with the corresponding viologen dihalide. They are highly soluble in molten quarternary ammonium salts and together with a suitable reductant provide electrolyte solutions that are used in electrochromic windows.

  16. Oklahoma/Wind Resources/Full Version | Open Energy Information

    Open Energy Info (EERE)

    City, OK 73104-3234 Phone: 800-879-6552 E-mail: info@okcommerce.gov State Energy Office Jennifer Jenkins Distributed Wind Energy Association PO Box 1861 Flagstaff, AZ 86002...

  17. A-Z Index - U.S. Energy Information Administration (EIA)

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

    A-Z Index A B C D E F G H I J K L M N O P Q R S T U V W XYZ A Abbreviations, energy related About U.S. Natural Gas Pipelines (U.S. & state) Acid rain (U.S., Census division, & state) Definition Emissions data Overview Acquisitions and Divestitures by Foreign Direct Investors in U.S. Energy (report discontinued) Activities for kids Additions to storage (natural gas; includes U.S. & state) Underground, by all operators Underground, by storage type Liquefied natural gas additions and

  18. DOE - Office of Legacy Management -- Salt_Lake

    Office of Legacy Management (LM)

    SaltLake Salt Lake City Sites utmap Salt Lake City Disposal Site Salt Lake City Processing Site Last Updated: 6172015...

  19. Plant salt-tolerance mechanisms

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

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selectionmore » and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.« less

  20. Plant salt-tolerance mechanisms

    SciTech Connect (OSTI)

    Deinlein, Ulrich; Stephan, Aaron B.; Horie, Tomoaki; Luo, Wei; Xu, Guohua; Schroeder, Julian I.

    2014-06-01

    Crop performance is severely affected by high salt concentrations in soils. To engineer more salt-tolerant plants it is crucial to unravel the key components of the plant salt-tolerance network. Here we review our understanding of the core salt-tolerance mechanisms in plants. Recent studies have shown that stress sensing and signaling components can play important roles in regulating the plant salinity stress response. We also review key Na+ transport and detoxification pathways and the impact of epigenetic chromatin modifications on salinity tolerance. In addition, we discuss the progress that has been made towards engineering salt tolerance in crops, including marker-assisted selection and gene stacking techniques. We also identify key open questions that remain to be addressed in the future.

  1. Characterization of fold defects in AZ91D and AE42 magnesium alloy permanent mold castings

    SciTech Connect (OSTI)

    Bichler, L. [Centre for Near-net-shape Processing of Materials, Ryerson University, 101 Gerrard St. E., Toronto, M5B 2K3 (Canada); Ravindran, C., E-mail: rravindr@ryerson.ca [Centre for Near-net-shape Processing of Materials, Ryerson University, 101 Gerrard St. E., Toronto, M5B 2K3 (Canada)

    2010-03-15

    Casting premium-quality magnesium alloy components for aerospace and automotive applications poses unique challenges. Magnesium alloys are known to freeze rapidly prior to filling a casting cavity, resulting in misruns and cold shuts. In addition, melt oxidation, solute segregation and turbulent metal flow during casting contribute to the formation of fold defects. In this research, formation of fold defects in AZ91D and AE42 magnesium alloys cast via the permanent mold casting process was investigated. Computer simulations of the casting process predicted the development of a turbulent metal flow in a critical casting region with abrupt geometrical transitions. SEM and light optical microscopy examinations revealed the presence of folds in this region for both alloys. However, each alloy exhibited a unique mechanism responsible for fold formation. In the AZ91D alloy, melt oxidation and velocity gradients in the critical casting region prevented fusion of merging metal front streams. In the AE42 alloy, limited solubility of rare-earth intermetallic compounds in the {alpha}-Mg phase resulted in segregation of Al{sub 2}RE particles at the leading edge of a metal front and created microstructural inhomogeneity across the fold.

  2. CHARACTERIZATION AND FORMABILITY OF CONTINUOUS-CAST AZ31B MAGNESIUM ALLOY SHEETS

    SciTech Connect (OSTI)

    Rohatgi, Aashish; Herling, Darrell R.; Nyberg, Eric A.

    2009-09-24

    The goal of this work is to understand the inter-relationship between the initial properties of continuous-cast magnesium alloy (AZ31B) sheets and their subsequent formability and post-formed mechanical performance for use in cost-effective, lightweight, automotive body panels. As-received sheets, provided by the Automotive Metals Division (AMD-602) team, were characterized by surface roughness measurements using mechanical profilometry. The arithmetic mean deviation of profile (Ra) and the maximum two-point height of profile (Ry) of the as-received sheets ranged from ~0.2-2 ?m and ~2-15 ?m, respectively. Several commercial lubricants were evaluated by thermal analysis and the liquid phase of the lubricants was found to evaporate/decompose upon heating leaving behind a solid residue upon heating to temperatures exceeding ~125-150C. Elevated temperature bending-under-tension (BUT) friction tests were conducted at 350C and the coefficient-of-friction values ranged from a minimum of ~0.1 (for tungsten disulfide lubricant) to ~0.7 when no lubricant was used. These results, in conjunction with those from the forming trials conducted by the AMD-602 team, will be eventually used to determine the role of sheet-die friction in determining the formability of AZ31B sheets.

  3. Structural Interactions within Lithium Salt Solvates: Acyclic...

    Office of Scientific and Technical Information (OSTI)

    Structural Interactions within Lithium Salt Solvates: Acyclic Carbonates and Esters Citation Details In-Document Search Title: Structural Interactions within Lithium Salt Solvates: ...

  4. Enterprise Assessments Salt Waste Processing Facility Construction...

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

    Salt Waste Processing Facility Construction Quality and Fire Protection Systems Follow-up Review at the Savannah River Site - January 2016 Enterprise Assessments Salt Waste ...

  5. Pump Jet Mixing and Pipeline Transfer Assessment for High-Activity Radioactive Wastes in Hanford Tank 241-AZ-102

    SciTech Connect (OSTI)

    Onishi, Yasuo; Recknagle, Kurtis P.; Wells, Beric E.

    2000-08-09

    This report evaluates how two 300-hp mixer pumps would mix solid and liquid radioactive wastes stored in Hanford double-shell Tank 241-AZ-102. It also assesses and confirms the adequacy of a 3-inch pipeline to transfer the resulting mixed waste slurry to the AP Tank Farm and ultimately to a planned waste treatment/vitrification plant on the Hanford Site.

  6. Evaluation of cracking in the 241-AZ tank farm ventilation line at the Hanford Site

    SciTech Connect (OSTI)

    ANANTATMULA, R.P.

    1999-10-20

    In the period from April to October of 1988, a series of welding operations on the outside of the AZ Tank Farm ventilation line piping at the Hanford Site produced unexpected and repeated cracking of the austenitic stainless steel base metal and of a seam weld in the pipe. The ventilation line is fabricated from type 304L stainless steel pipe of 24 inch diameter and 0.25 inch wall thickness. The pipe was wrapped in polyethylene bubble wrap and buried approximately 12 feet below grade. Except for the time period between 1980 and 1987, impressed current cathodic protection has been applied to the pipe since its installation in 1974. The paper describes the history of the cracking of the pipe, the probable cracking mechanisms, and the recommended future action for repair/replacement of the pipe.

  7. BASIN BLAN CO BLAN CO S OT ERO IGNAC IO-BLANCO AZ TEC BALLAR

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

    BOE Reserve Class No 2001 reserves 0.1 - 10 MBOE 10.1 - 100 MBOE 100.1 - 1,000 MBOE 1,000.1- 10,000 MBOE 10,000.1 - 100,000 MBOE > 100,000 MBOE Basin Outline AZ UT NM CO 1 2 Index Map for 2 Paradox-San Juan Panels 2001 Reserve Summary for All Paradox-San Juan Basin Fields Total Total Total Number Liquid Gas BOE of Reserves Reserves Reserves Fields (Mbbl) (MMcf) (Mbbl) Paradox-San Juan 250 174,193 20,653,622 3,616,464 Basin CO NM IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC IO-BLANCO

  8. BASIN BLAN CO BLAN CO S OT ERO IGNAC IO-BLANCO AZ TEC BALLAR

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

    Gas Reserve Class No 2001 gas reserves 0.1 - 10 MMCF 10.1 - 100 MMCF 100.1 - 1,000 MMCF 1,000.1- 10,000 MMCF 10,000.1 - 100,000 MMCF > 100,000 MMCF Basin Outline AZ UT NM CO 1 2 Index Map for 2 Paradox-San Juan Panels 2001 Reserve Summary for All Paradox-San Juan Basin Fields Total Total Total Number Liquid Gas BOE of Reserves Reserves Reserves Fields (Mbbl) (MMcf) (Mbbl) Paradox-San Juan 250 174,193 20,653,622 3,616,464 Basin CO NM IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC

  9. BASIN BLAN CO BLAN CO S OT ERO IGNAC IO-BLANCO AZ TEC BALLAR

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

    Liquids Reserve Class No 2001 liquids reserves 0.1 - 10 Mbbl 10.1 - 100 Mbbl 100.1 - 1,000 Mbbl 1,000.1- 10,000 Mbbl 10,000.1 - 100,000 Mbbl Basin Outline AZ UT NM CO 1 2 Index Map for 2 Paradox-San Juan Panels 2001 Reserve Summary for All Paradox-San Juan Basin Fields Total Total Total Number Liquid Gas BOE of Reserves Reserves Reserves Fields (Mbbl) (MMcf) (Mbbl) Paradox-San Juan 250 174,193 20,653,622 3,616,464 Basin CO NM IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC IO-BLANCO IGNAC

  10. Archaeological studies at Drill Hole U20az Pahute Mesa, Nye county, Nevada. [Contains bibliography

    SciTech Connect (OSTI)

    Simmons, A.H.; Hemphill, M.L.; Henton, G.H.; Lockett, C.L.; Nials, F.L.; Pippin, L.C.; Walsh, L.

    1991-07-01

    During the summer of 1987, the Quaternary Sciences Center (formerly Social Science Center) of the Desert Research Institute (DRI), University of Nevada System, conducted data recovery investigations at five archaeological sites located near Drill Hole U20az on the Nevada Test Site in southern Nevada. These sites were among 12 recorded earlier during an archaeological survey of the drill hole conducted as part of the environmental compliance activities of the Department of Energy (DOE). The five sites discussed in this report were considered eligible for the National Register of Historic Places and were in danger of being adversely impacted by construction activities or by effects of the proposed underground nuclear test. Avoidance of these sites was not a feasible alternative; thus DRI undertook a data recovery program to mitigate expected adverse impacts. DRI's research plan included controlled surface collections and excavation of the five sites in question, and had the concurrence of the Nevada Division of Historic Preservation and Archaeology and the Advisory Council of Historic Preservation. Of the five sites investigated, the largest and most complex, 26Ny5207, consists of at least three discrete artifact concentrations. Sites 26Ny5211 and 26Ny5215, both yielded considerable assemblages. Site 26Ny5206 is very small and probably is linked to 26Ny5207. Site 26Ny5205 contained a limited artifact assemblage. All of the sites were open-air occurrences, and, with one exception contained no or limited subsurface cultural deposits. Only two radiocarbon dates were obtained, both from 26Ny5207 and both relatively recent. While the investigations reported in the volume mitigate most of the adverse impacts from DOE activities at Drill Hole U20az, significant archaeological sites may still exist in the general vicinity. Should the DOE conduct further activities in the region, additional cultural resource investigations may be required. 132 refs., 71 figs., 44 tabs.

  11. Production of chlorine from chloride salts

    DOE Patents [OSTI]

    Rohrmann, Charles A. (Kennewick, WA)

    1981-01-01

    A process for converting chloride salts and sulfuric acid to sulfate salts and elemental chlorine is disclosed. A chloride salt and sulfuric acid are combined in a furnace where they react to produce a sulfate salt and hydrogen chloride. Hydrogen chloride from the furnace contacts a molten salt mixture containing an oxygen compound of vanadium, an alkali metal sulfate and an alkali metal pyrosulfate to recover elemental chlorine. In the absence of an oxygen-bearing gas during the contacting, the vanadium is reduced, but is regenerated to its active higher valence state by separately contacting the molten salt mixture with an oxygen-bearing gas.

  12. Treatment of Remediated Nitrate Salts

    Broader source: Energy.gov [DOE]

    Los Alamos National Laboratory, provided a presentation at the NNMCABs November 18, 2015 Board Meeting at New Mexico Highlands University. The topic of the presentation was the plan for remediation the nitrate salt waste from the 3706 campaign that is currently stored at Material Disposal Area G, presenter was David Funk, LANS.

  13. Salt Wells Geothermal Project | Open Energy Information

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Development Project: Salt Wells Geothermal Project Project Location Information Coordinates 39.580833333333,...

  14. Brine Migration Experimental Studies for Salt Repositories

    Broader source: Energy.gov [DOE]

    Experiments were used to examine water content in Permian salt samples including impact of variation in thermal regime on water content of evaporites and other mineral species, behavior of brine inclusions in salt, and evolution of the gas/liquid brine/salt system.

  15. Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot Granular Salt Consolidation, Constitutive Model and Micromechanics

    Broader source: Energy.gov [DOE]

    The report addresses granular salt reconsolidation from three vantage points: laboratory testing, modeling, and petrofabrics.

  16. Thermophysical properties of reconsolidating crushed salt.

    SciTech Connect (OSTI)

    Bauer, Stephen J.; Urquhart, Alexander

    2014-03-01

    Reconsolidated crushed salt is being considered as a backfilling material placed upon nuclear waste within a salt repository environment. In-depth knowledge of thermal and mechanical properties of the crushed salt as it reconsolidates is critical to thermal/mechanical modeling of the reconsolidation process. An experimental study was completed to quantitatively evaluate the thermal conductivity of reconsolidated crushed salt as a function of porosity and temperature. The crushed salt for this study came from the Waste Isolation Pilot Plant (WIPP). In this work the thermal conductivity of crushed salt with porosity ranging from 1% to 40% was determined from room temperature up to 300oC, using two different experimental methods. Thermal properties (including thermal conductivity, thermal diffusivity and specific heat) of single-crystal salt were determined for the same temperature range. The salt was observed to dewater during heating; weight loss from the dewatering was quantified. The thermal conductivity of reconsolidated crushed salt decreases with increasing porosity; conversely, thermal conductivity increases as the salt consolidates. The thermal conductivity of reconsolidated crushed salt for a given porosity decreases with increasing temperature. A simple mixture theory model is presented to predict and compare to the data developed in this study.

  17. Salt restrains maturation in subsalt plays

    SciTech Connect (OSTI)

    Mello, U.T. ); Anderson, R.N.; Karner, G.D. . Lamont-Doherty Earth Observatory)

    1994-01-31

    The thermal positive anomaly associated with the top of salt diapirs has attracted significant attention in modifying the temperature structure and history of a sedimentary basin. Here the authors explore the role of the negative thermal anomaly beneath salt in modifying the maturation history of the source rocks in subsalt sediments. Organic matter maturation is believed to follow temperature dependent chemical reactions. Therefore, any temperature anomaly associated with salt masses affects the nearby maturation of potential source rocks. The level of maturity of source rocks close to salt diapirs will differ from that predicted based on regional trends. The impact of the thermal anomaly on a given point will depend on the duration and distance of the thermal anomaly to this particular point. Consequently, the maturation history of source rocks in salt basins is closely related to the salt motion history, implying that a transient thermal analysis is necessary to evaluate the sure impact on maturation of the thermal anomalies associated with salt diapirism. The paper describes vitrinite kinetics, salt in evolving basins, correlation of salt and temperature, salt dome heat drains, and restrained maturation.

  18. Advanced characterization study of commercial conversion and electrocoating structures on magnesium alloys AZ31B and ZE10A

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

    Brady, Michael P.; Leonard, Donovan N.; Meyer, III, Harry M.; Song, Guang -Ling; Kitchen, Kris; Davis, Bruce; Thompson, J. K.; Unocic, K. A.; Elsentriecy, H. H.

    2016-03-31

    The local metal-coating interface microstructure and chemistry formed on commercial magnesium alloys Mg–3Al–1Zn (AZ31B) and Mg–1Zn–0.25Zr–<0.5Nd (ZE10A, ZEK100 type) were analyzed as-chemical conversion coated with a commercial hexafluoro-titanate/zirconate type + organic polymer based treatment (Bonderite® 5200) and a commercial hexafluoro-zirconate type + trivalent chromium Cr3 + type treatment (Surtec® 650), and after the same conversion coatings followed by electrocoating with an epoxy based coating, Cathoguard® 525. Characterization techniques included scanning electron microscopy (SEM), X-ray photoelectron spectroscopy (XPS), and cross-section scanning transmission electron microscopy (STEM). Corrosion behavior was assessed in room temperature saturated aqueous Mg(OH)2 solution with 1 wt.% NaCl. Themore » goal of the effort was to assess the degree to which substrate alloy additions become enriched in the conversion coating, and how the conversion coating was impacted by subsequent electrocoating. Key findings included the enrichment of Al from AZ31B and Zr from ZE10A, respectively, into the conversion coating, with moderate corrosion resistance benefits for AZ31B when Al was incorporated. Varying degrees of increased porosity and modification of the initial conversion coating chemistry at the metal-coating interface were observed after electrocoating. These changes were postulated to result in degraded electrocoating protectiveness. As a result, these observations highlight the challenges of coating Mg, and the need to tailor electrocoating in light of potential degradation of the initial as-conversion coated Mg alloy surface.« less

  19. 3610 N. 44th Street, Suite 250, Phoenix, AZ 85018 ● Phone 602-808-2004 ●

    Energy Savers [EERE]

    10 N. 44th Street, Suite 250, Phoenix, AZ 85018 ● Phone 602-808-2004 ● Fax 602-808-2099 ● www.sunzia.net October 17, 2013 Transmitted via electronic mail to juliea.smith@hq.doe.gov and christopher.lawrence@hq.doe.gov Subject: SunZia Southwest Transmission Project comments on Department of Energy's August 29, 2013 Federal Register Notice regarding Improving Performance of Federal Permitting and Review of Infrastructure Projects. The following comments are provided to the Department of

  20. HIA 2015 DOE Zero Energy Ready Home Case Study: Mandalay Homes, Vision Hill Lot 1, Glendale, AZ

    Energy Savers [EERE]

    Homes Vision Hill Lot 1 Glendale, AZ DOE ZERO ENERGY READY HOME(tm) The U.S. Department of Energy invites home builders across the country to meet the extraordinary levels of excellence and quality specified in DOE's Zero Energy Ready Home program (formerly known as Challenge Home). Every DOE Zero Energy Ready Home starts with ENERGY STAR Certified Homes Version 3.0 for an energy-efficient home built on a solid foundation of building science research. Advanced technologies are designed in to

  1. Estimate of the Distribution of Solids Within Mixed Hanford Double-Shell Tank AZ-101: Implications for AY-102

    SciTech Connect (OSTI)

    Wells, Beric E.; Ressler, Jennifer J.

    2009-04-29

    This paper describes the current level of understanding of the suspension of solids in Hanford double-shell waste tanks while being mixed with the baseline configuration of two 300-horsepower mixer pumps. A mixer pump test conducted in Tank AZ-101 during fiscal year 2000 provided the basis for this understanding. Information gaps must be filled to demonstrate the capability of the baseline feed delivery system to effectively mix, sample, and deliver double-shell tank waste to the Hanford Tank Waste Treatment and Immobilization Plant (WTP) for vitrification.

  2. Granular Salt Summary: Reconsolidation Principles and Applications

    SciTech Connect (OSTI)

    Hansen, Frank; Popp, Till; Wieczorek, Klaus; Stuehrenberg, Dieter

    2014-07-01

    The purposes of this paper are to review the vast amount of knowledge concerning crushed salt reconsolidation and its attendant hydraulic properties (i.e., its capability for fluid or gas transport) and to provide a sufficient basis to understand reconsolidation and healing rates under repository conditions. Topics covered include: deformation mechanisms and hydro-mechanical interactions during reconsolidation; the experimental data base pertaining to crushed salt reconsolidation; transport properties of consolidating granulated salt and provides quantitative substantiation of its evolution to characteristics emulating undisturbed rock salt; and extension of microscopic and laboratory observations and data to the applicable field scale.

  3. Electrolytic orthoborate salts for lithium batteries

    DOE Patents [OSTI]

    Angell, Charles Austen; Xu, Wu

    2008-01-01

    Orthoborate salts suitable for use as electrolytes in lithium batteries and methods for making the electrolyte salts are provided. The electrolytic salts have one of the formulae (I). In this formula anionic orthoborate groups are capped with two bidentate chelating groups, Y1 and Y2. Certain preferred chelating groups are dibasic acid residues, most preferably oxalyl, malonyl and succinyl, disulfonic acid residues, sulfoacetic acid residues and halo-substituted alkylenes. The salts are soluble in non-aqueous solvents and polymeric gels and are useful components of lithium batteries in electrochemical devices.

  4. Electrolytic orthoborate salts for lithium batteries

    DOE Patents [OSTI]

    Angell, Charles Austen [Mesa, AZ; Xu, Wu [Tempe, AZ

    2009-05-05

    Orthoborate salts suitable for use as electrolytes in lithium batteries and methods for making the electrolyte salts are provided. The electrolytic salts have one of the formulae (I). In this formula anionic orthoborate groups are capped with two bidentate chelating groups, Y1 and Y2. Certain preferred chelating groups are dibasic acid residues, most preferably oxalyl, malonyl and succinyl, disulfonic acid residues, sulfoacetic acid residues and halo-substituted alkylenes. The salts are soluble in non-aqueous solvents and polymeric gels and are useful components of lithium batteries in electrochemical devices.

  5. SEPARATION OF INORGANIC SALTS FROM ORGANIC SOLUTIONS

    DOE Patents [OSTI]

    Katzin, L.I.; Sullivan, J.C.

    1958-06-24

    A process is described for recovering the nitrates of uranium and plutonium from solution in oxygen-containing organic solvents such as ketones or ethers. The solution of such salts dissolved in an oxygen-containing organic compound is contacted with an ion exchange resin whereby sorption of the entire salt on the resin takes place and then the salt-depleted liquid and the resin are separated from each other. The reaction seems to be based on an anion formation of the entire salt by complexing with the anion of the resin. Strong base or quaternary ammonium type resins can be used successfully in this process.

  6. Remediated Nitrate Salt Drums Safety Update

    Broader source: Energy.gov [DOE]

    At the March 9, 2016 Combined Committee Meeting Mr. Nickless, Environmental Management Los Alamos, Provided a presentation on the status of the Nitrate Salt waste at Los Alamos.

  7. Noncentrosymmetric salt inclusion oxides: Role of salt lattices and counter ions in bulk polarity

    SciTech Connect (OSTI)

    West, J. Palmer; Hwu, Shiou-Jyh

    2012-11-15

    The synthesis and structural features of a newly emerged class of salt-inclusion solids (SISs) are reviewed. The descriptive chemistry with respect to the role of ionic salt and its correlation with bulk noncentrosymmetricity and polarity of the covalent oxide lattice in question is discussed by means of structure analysis. These unprecedented discoveries have opened doors to novel materials synthesis via the utilities of salt-inclusion chemistry (SIC) that are otherwise known as the molten-salt approach. The result of these investigations prove that the bulk acentricity, or cancellation of which, can be accounted for from the perspective of ionic and/or salt lattices. Highlights: Black-Right-Pointing-Pointer Synthesis and structure of newly emerged salt-inclusion solids are reviewed. Black-Right-Pointing-Pointer Salt lattice and its symmetry correlation with polar framework are discussed. Black-Right-Pointing-Pointer Preservation of acentricity is accounted for from the perspective of ionic and salt lattices.

  8. GRED III Final Report Clifton Hot Springs Geothermal Greenlee County, AZ

    SciTech Connect (OSTI)

    Brown, David E.

    2006-06-15

    Black & Veatch Corporation has prepared this report for Arizona Public Service Company, Salt River Project, and Tucson Electric Power Company (APS/SRP/TEP). The purpose of this report is to assess the prospects for significant renewable energy development in Arizona. The scope of the study is limited to Arizona projects that would export power to the grid (that is, not distributed energy projects). This study includes a review of the current status of renewable energy in Arizona, characterization of renewable power generation technologies, assessment of Arizona''s renewable resources, and an assessment of key risk factors. This section summarizes the key findings in these areas.

  9. Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt

    Energy Savers [EERE]

    Waste Processing Facility Independent Technical Review | Department of Energy Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt Waste Processing Facility Independent Technical Review This is a presentation outlining the Salt Waste Processing Facility process, major risks, approach for conducting reviews, discussion of the findings, and conclusions. PDF icon Savannah River Site -

  10. Metal salt catalysts for enhancing hydrogen spillover

    DOE Patents [OSTI]

    Yang, Ralph T; Wang, Yuhe

    2013-04-23

    A composition for hydrogen storage includes a receptor, a hydrogen dissociating metal doped on the receptor, and a metal salt doped on the receptor. The hydrogen dissociating metal is configured to spill over hydrogen to the receptor, and the metal salt is configured to increase a rate of the spill over of the hydrogen to the receptor.

  11. Nitrate Salt Surrogate Blending Scoping Test Plan

    SciTech Connect (OSTI)

    Anast, Kurt Roy

    2015-11-13

    Test blending equipment identified in the “Engineering Options Assessment Report: Nitrate Salt Waste Stream Processing”. Determine if the equipment will provide adequate mixing of zeolite and surrogate salt/Swheat stream; optimize equipment type and operational sequencing; impact of baffles and inserts on mixing performance; and means of validating mixing performance

  12. Solar Policy Environment: Salt Lake

    Broader source: Energy.gov [DOE]

    The overall objective of the “Solar Salt Lake” (SSL) team is to develop a fully-scoped city and county-level implementation plan that will facilitate at least an additional ten megawatts of solar photovoltaic (PV) installations in the government, commercial, industrial, and residential sectors by 2015. To achieve this aggressive goal, the program strategy includes a combination of barrier identification, research, and policy analysis that utilizes the input of various stakeholders. Coupled with these activities will be the development and implementation of pilot installations in the government and residential sectors, and broad outreach to builders and potential practitioners of solar energy products in the process. In this way, while creating mechanisms to enable a demand for solar, SSL will also facilitate capacity building for suppliers, thereby helping to ensure long-term sustainability for the regional market.

  13. Evaluation of Salt Coolants for Reactor Applications

    SciTech Connect (OSTI)

    Williams, David F

    2008-01-01

    Molten fluorides were initially developed for use in the nuclear industry as the high-temperature fluid fuel for the Molten Salt Reactor (MSR). The U.S. Department of Energy Office of Nuclear Energy is exploring the use of molten salts as primary and secondary coolants in a new generation of solid-fueled, thermal-spectrum, hightemperature reactors. This paper provides a review of relevant properties for use in evaluation and ranking of salt coolants for high-temperature reactors. Nuclear, physical, and chemical properties were reviewed, and metrics for evaluation are recommended. Chemical properties of the salt were examined to identify factors that affect materials compatibility (i.e., corrosion). Some preliminary consideration of economic factors for the candidate salts is also presented.

  14. SEPARATION OF METAL SALTS BY ADSORPTION

    DOE Patents [OSTI]

    Gruen, D.M.

    1959-01-20

    It has been found that certain metal salts, particularly the halides of iron, cobalt, nickel, and the actinide metals, arc readily absorbed on aluminum oxide, while certain other salts, particularly rare earth metal halides, are not so absorbed. Use is made of this discovery to separate uranium from the rare earths. The metal salts are first dissolved in a molten mixture of alkali metal nitrates, e.g., the eutectic mixture of lithium nitrate and potassium nitrate, and then the molten salt solution is contacted with alumina, either by slurrying or by passing the salt solution through an absorption tower. The process is particularly valuable for the separation of actinides from lanthanum-group rare earths.

  15. DOE - Office of Legacy Management -- Tatum Salt Dome Test Site...

    Office of Legacy Management (LM)

    Tatum Salt Dome Test Site - MS 01 FUSRAP Considered Sites Site: Tatum Salt Dome Test Site (MS.01) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  16. EIA - Natural Gas Pipeline Network - Salt Cavern Storage Reservoir...

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

    Salt Cavern Underground Natural Gas Storage Reservoir Configuration Salt Cavern Underground Natural Gas Storage Reservoir Configuration Source: PB Energy Storage Services Inc.

  17. BLM Fact Sheet- Ormat Technologies Salt Wells Geothermal Energy...

    Open Energy Info (EERE)

    Ormat Technologies Salt Wells Geothermal Energy Project Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: BLM Fact Sheet- Ormat Technologies Salt Wells...

  18. Isotopic Analysis- Fluid At Salt Wells Area (Shevenell & Garside...

    Open Energy Info (EERE)

    At Salt Wells Area (Shevenell & Garside, 2003) Exploration Activity Details Location Salt Wells Geothermal Area Exploration Technique Isotopic Analysis- Fluid Activity Date 2002 -...

  19. Compound and Elemental Analysis At Salt Wells Area (Shevenell...

    Open Energy Info (EERE)

    At Salt Wells Area (Shevenell & Garside, 2003) Exploration Activity Details Location Salt Wells Geothermal Area Exploration Technique Compound and Elemental Analysis Activity Date...

  20. Conceptual Model At Salt Wells Area (Faulds, Et Al., 2011) |...

    Open Energy Info (EERE)

    At Salt Wells Area (Faulds, Et Al., 2011) Exploration Activity Details Location Salt Wells Geothermal Area Exploration Technique Conceptual Model Activity Date 2011 Usefulness...

  1. Remediated Nitrate Salt Drums Storage at Los Alamos National...

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

    Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory As a part of its national security ...

  2. Geothermal Literature Review At Salt Wells Area (Faulds, Et Al...

    Open Energy Info (EERE)

    Salt Wells Area (Faulds, Et Al., 2011) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Geothermal Literature Review At Salt Wells Area (Faulds,...

  3. Independent Oversight Review, Savannah River Site Salt Waste...

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

    August 2013 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - August 2013 August 2013 Review of the Savannah River Site Salt Waste Processing...

  4. Sandia Energy - Molten Nitrate Salt Initial Flow Testing is a...

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

    Nitrate Salt Initial Flow Testing is a Tremendous Success Home Renewable Energy News Concentrating Solar Power Solar Molten Nitrate Salt Initial Flow Testing is a Tremendous...

  5. Magnetotellurics At Salt Wells Area (Bureau of Land Management...

    Open Energy Info (EERE)

    Salt Wells Area (Bureau of Land Management, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Magnetotellurics At Salt Wells Area (Bureau of...

  6. Salt Lake City, Utah: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Salt Lake City, Utah: Energy Resources (Redirected from Salt Lake City, UT) Jump to: navigation, search Equivalent URI DBpedia Coordinates 40.7607793, -111.8910474 Show Map...

  7. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container...

    Office of Environmental Management (EM)

    Nitrate Salt Bearing Waste Container Isolation Plan Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan The purpose of this document is to provide the ...

  8. Savannah River Site Salt Waste Processing Facility Technology...

    Office of Environmental Management (EM)

    Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report ... of Energy Washington, D.C. SRS Salt Waste Processing Facility Technology Readiness ...

  9. Development of Molten-Salt Heat Trasfer Fluid Technology for...

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

    Development of Molten-Salt Heat Trasfer Fluid Technology for Parabolic Trough Solar Power Plants Development of Molten-Salt Heat Trasfer Fluid Technology for Parabolic Trough Solar ...

  10. Novel Molten Salts Thermal Energy Storage for Concentrating Solar...

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

    Molten Salts Thermal Energy Storage for Concentrating Solar Power Generation Novel Molten Salts Thermal Energy Storage for Concentrating Solar Power Generation This presentation ...

  11. Molten salt heat transfer fluids and thermal storage technology...

    Office of Scientific and Technical Information (OSTI)

    Molten salt heat transfer fluids and thermal storage technology. Citation Details In-Document Search Title: Molten salt heat transfer fluids and thermal storage technology. No ...

  12. Liquid Salt Heat Exchanger Technology for VHTR Based Applications...

    Office of Scientific and Technical Information (OSTI)

    Liquid Salt Heat Exchanger Technology for VHTR Based Applications Citation Details In-Document Search Title: Liquid Salt Heat Exchanger Technology for VHTR Based Applications The ...

  13. Voluntary Protection Program Onsite Review, Parsons Corp., Salt...

    Office of Environmental Management (EM)

    Corp., Salt Waste Processing Facility Construction Project - May 2014 Voluntary Protection Program Onsite Review, Parsons Corp., Salt Waste Processing Facility Construction Project...

  14. DOE - Office of Legacy Management -- Penn Salt Manufacturing...

    Office of Legacy Management (LM)

    Salt Manufacturing Co Whitemarsh Research Laboratories - PA 20 FUSRAP Considered Sites Site: PENN SALT MANUFACTURING CO., WHITEMARSH RESEARCH LABORATORIES (PA.20) Eliminated from...

  15. Salt Lake County, Utah: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Creek Valley, Utah Magna, Utah Midvale, Utah Millcreek, Utah Mount Olympus, Utah Murray, Utah Riverton, Utah Salt Lake City, Utah Sandy, Utah South Jordan, Utah South Salt...

  16. Sandia Energy - Customer Interface Document for the Molten Salt...

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

    Customer Interface Document for the Molten Salt Test Loop at the NSTTF Home Partnership News News & Events Publications Customer Interface Document for the Molten Salt Test Loop at...

  17. Sandia Energy - Molten Salt Test Loop Pump Installed

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

    Energy Energy News Concentrating Solar Power Solar Energy Storage Systems Molten Salt Test Loop Pump Installed Previous Next Molten Salt Test Loop Pump Installed The pump was...

  18. Salt Waste Processing Facility, Construction Turnover to Testing...

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

    Salt Waste Processing Facility, Construction Turnover to Testing and Commissioning Oversight This procedure establishes an oversight process for the Salt Waste Processing Facility ...

  19. Salt Waste Processing Facility, Line Management Review Board...

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

    Line Management Review Board Charter Salt Waste Processing Facility, Line Management ... processes and associated deliverables for the Salt Waste Processing Facility (SWPF). ...

  20. The Salt Defense Disposal Investigations (SDDI)

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

    Salt Defense Disposal Investigations (SDDI) will utilize a newly mined Underground Research Lab (URL) in WIPP to perform a cost effective, proof-of-principle feld test of the emplacement of heat-generating radioactive waste and validate modeling efforts. The goals of the SDDI Thermal Test are to: * Demonstrate a proof-of-principle concept for in-drift disposal in salt. * Investigate, in a specifc emplacement concept, the response of the salt to heat. * Develop a full-scale response for run-of-

  1. Examination of Liquid Fluoride Salt Heat Transfer

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L

    2014-01-01

    The need for high efficiency power conversion and energy transport systems is increasing as world energy use continues to increase, petroleum supplies decrease, and global warming concerns become more prevalent. There are few heat transport fluids capable of operating above about 600oC that do not require operation at extremely high pressures. Liquid fluoride salts are an exception to that limitation. Fluoride salts have very high boiling points, can operate at high temperatures and low pressures and have very good heat transfer properties. They have been proposed as coolants for next generation fission reactor systems, as coolants for fusion reactor blankets, and as thermal storage media for solar power systems. In each case, these salts are used to either extract or deliver heat through heat exchange equipment, and in order to design this equipment, liquid salt heat transfer must be predicted. This paper discusses the heat transfer characteristics of liquid fluoride salts. Historically, heat transfer in fluoride salts has been assumed to be consistent with that of conventional fluids (air, water, etc.), and correlations used for predicting heat transfer performance of all fluoride salts have been the same or similar to those used for water conventional fluids an, water, etc). A review of existing liquid salt heat transfer data is presented, summarized, and evaluated on a consistent basis. Less than 10 experimental data sets have been found in the literature, with varying degrees of experimental detail and measured parameters provided. The data has been digitized and a limited database has been assembled and compared to existing heat transfer correlations. Results vary as well, with some data sets following traditional correlations; in others the comparisons are less conclusive. This is especially the case for less common salt/materials combinations, and suggests that additional heat transfer data may be needed when using specific salt eutectics in heat transfer equipment designs. All of the data discussed above were taken under forced convective conditions (both laminar and turbulent). Some recent data taken at ORNL under free convection conditions are also presented and results discussed. This data was taken using a simple crucible experiment with an instrumented nickel heater inserted in the salt to induce natural circulation within the crucible. The data was taken over a temperature range of 550oC to 650oC in FLiNaK salt. This data covers both laminar and turbulent natural convection conditions, and is compared to existing forms of natural circulation correlations.

  2. Abnormal macropore formation during double-sided gas tungsten arc welding of magnesium AZ91D alloy

    SciTech Connect (OSTI)

    Shen Jun You Guoqiang; Long Siyuan; Pan Fusheng

    2008-08-15

    One of the major concerns during gas tungsten arc (GTA) welding of cast magnesium alloys is the presence of large macroporosity in weldments, normally thought to occur from the presence of gas in the castings. In this study, a double-sided GTA welding process was adopted to join wrought magnesium AZ91D alloy plates. Micropores were formed in the weld zone of the first side that was welded, due to precipitation of H{sub 2} as the mushy zone freezes. When the reverse side was welded, the heat generated caused the mushy zone in the initial weld to reform. The micropores in the initial weld then coalesced and expanded to form macropores by means of gas expansion through small holes that are present at the grain boundaries in the partially melted zone. Macropores in the partially melted zone increase with increased heat input, so that when a filler metal is used the macropores are smaller in number and in size.

  3. Molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, W.A.; Upadhye, R.S.; Pruneda, C.O.

    1995-07-18

    A molten salt destruction process is used to treat and destroy energetic waste materials such as high explosives, propellants, and rocket fuels. The energetic material is pre-blended with a solid or fluid diluent in safe proportions to form a fluid fuel mixture. The fuel mixture is rapidly introduced into a high temperature molten salt bath. A stream of molten salt is removed from the vessel and may be recycled as diluent. Additionally, the molten salt stream may be pumped from the reactor, circulated outside the reactor for further processing, and delivered back into the reactor or cooled and circulated to the feed delivery system to further dilute the fuel mixture entering the reactor. 4 figs.

  4. Molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, William A. (Livermore, CA); Upadhye, Ravindra S. (Pleasanton, CA); Pruneda, Cesar O. (Livermore, CA)

    1995-01-01

    A molten salt destruction process is used to treat and destroy energetic waste materials such as high explosives, propellants, and rocket fuels. The energetic material is pre-blended with a solid or fluid diluent in safe proportions to form a fluid fuel mixture. The fuel mixture is rapidly introduced into a high temperature molten salt bath. A stream of molten salt is removed from the vessel and may be recycled as diluent. Additionally, the molten salt stream may be pumped from the reactor, circulated outside the reactor for further processing, and delivered back into the reactor or cooled and circulated to the feed delivery system to further dilute the fuel mixture entering the reactor.

  5. Salt Selection for the LS-VHTR

    SciTech Connect (OSTI)

    Williams, D.F.; Clarno, K.T.

    2006-07-01

    Molten fluorides were initially developed for use in the nuclear industry as the high temperature fluid-fuel for a Molten Salt Reactor (MSR). The Office of Nuclear Energy is exploring the use of molten fluorides as a primary coolant (rather than helium) in an Advanced High Temperature Reactor (AHTR) design, also know as the Liquid-Salt cooled Very High Temperature Reactor (LS-VHTR). This paper provides a review of relevant properties for use in evaluation and ranking of candidate coolants for the LS-VHTR. Nuclear, physical, and chemical properties were reviewed and metrics for evaluation are recommended. Chemical properties of the salt were examined for the purpose of identifying factors that effect materials compatibility (i.e., corrosion). Some preliminary consideration of economic factors for the candidate salts is also presented. (authors)

  6. Liquid salt environment stress-rupture testing

    DOE Patents [OSTI]

    Ren, Weiju; Holcomb, David E.; Muralidharan, Govindarajan; Wilson, Dane F.

    2016-03-22

    Disclosed herein are systems, devices and methods for stress-rupture testing selected materials within a high-temperature liquid salt environment. Exemplary testing systems include a load train for holding a test specimen within a heated inert gas vessel. A thermal break included in the load train can thermally insulate a load cell positioned along the load train within the inert gas vessel. The test specimen can include a cylindrical gage portion having an internal void filled with a molten salt during stress-rupture testing. The gage portion can have an inner surface area to volume ratio of greater than 20 to maximize the corrosive effect of the molten salt on the specimen material during testing. Also disclosed are methods of making a salt ingot for placement within the test specimen.

  7. Salt Lake City- High Performance Buildings Requirement

    Broader source: Energy.gov [DOE]

    Salt Lake City's mayor issued an executive order in July 2005 requiring that all public buildings owned and controlled by the city be built or renovated to meet the requirements of LEED "silver"...

  8. Director, Salt Waste Processing Facility Project Office

    Broader source: Energy.gov [DOE]

    This position is located within The Department of Energy (DOE) Savannah River (SR) Operations Office, Salt Waste Processing Facility Project Office (SWPFPO). SR is located in Aiken, South Carolina....

  9. Ethylenediamine salt of 5-nitrotetrazole and preparation

    DOE Patents [OSTI]

    Lee, Kien-yin; Coburn, Michael D.

    1985-01-01

    Ethylenediamine salt of 5-nitrotetrazole and preparation. This salt has been found to be useful as an explosive alone and in eutectic mixtures with ammonium nitrate and/or other explosive compounds. Its eutectic with ammonium nitrate has been demonstrated to behave in a similar manner to a monomolecular explosive such as TNT, and is less sensitive than the pure salt. Moreover, this eutectic mixture, which contains 87.8 mol % of ammonium nitrate, is close to the CO.sub.2 -balanced composition of 90 mol %, and has a relatively low melting point of 110.5 C. making it readily castable. The ternary eutectic system containing the ethylenediamine salt of 5-nitrotetrazole, ammonium nitrate and ethylenediamine dinitrate has a eutectic temperature of 89.5 C. and gives a measured detonation pressure of 24.8 GPa, which is 97.6% of the calculated value. Both the pure ethylenediamine salt and its known eutectic compounds behave in substantially ideal manner. Methods for the preparation of the salt are described.

  10. Thermal Characterization of Molten Salt Systems

    SciTech Connect (OSTI)

    Toni Y. Gutknecht; Guy L. Fredrickson

    2011-09-01

    The phase stability of molten salts in an electrorefiner (ER) may be adversely affected by the buildup of sodium, fission products, and transuranics in the electrolyte. Potential situations that need to be avoided are the following: (1) salt freezing due to an unexpected change in the liquidus temperature, (2) phase separation or non-homogeneity of the molten salt due to the precipitation of solids or formation of immiscible liquids, and (3) any mechanism that can result in the separation and concentration of fissile elements from the molten salt. Any of these situations would result in an off-normal condition outside the established safety basis for electrorefiner (ER) operations. The stability (and homogeneity) of the phases can potentially be monitored through the thermal characterization of the salts, which can be a function of impurity concentration. This report describes the experimental results of typical salts compositions, which consist of chlorides of potassium, lithium, strontium, samarium, praseodymium, lanthanum, barium, cerium, cesium, neodymium, sodium and gadolinium chlorides as a surrogate for both uranium and plutonium, used for the processing of used nuclear fuels.

  11. Savannah River Site - Salt Waste Processing Facility Independent Technical

    Energy Savers [EERE]

    Review | Department of Energy Facility Independent Technical Review Savannah River Site - Salt Waste Processing Facility Independent Technical Review Full Document and Summary Versions are available for download PDF icon Savannah River Site - Salt Waste Processing Facility Independent Technical Review PDF icon Summary - Salt Waste Processing Facility Design at the Savannah River Site More Documents & Publications Savannah River Site - Salt Waste Processing Facility: Briefing on the Salt

  12. Low temperature oxidation using support molten salt catalysts

    DOE Patents [OSTI]

    Weimer, Alan W.; Czerpak, Peter J.; Hilbert, Patrick M.

    2003-05-20

    Molten salt reactions are performed by supporting the molten salt on a particulate support and forming a fluidized bed of the supported salt particles. The method is particularly suitable for combusting hydrocarbon fuels at reduced temperatures, so that the formation NO.sub.x species is reduced. When certain preferred salts are used, such as alkali metal carbonates, sulfur and halide species can be captured by the molten salt, thereby reducing SO.sub.x and HCl emissions.

  13. Liquid fuel molten salt reactors for thorium utilization (Journal Article)

    Office of Scientific and Technical Information (OSTI)

    | SciTech Connect Journal Article: Liquid fuel molten salt reactors for thorium utilization Citation Details In-Document Search This content will become publicly available on April 8, 2017 Title: Liquid fuel molten salt reactors for thorium utilization Molten salt reactors (MSRs) represent a class of reactors that use liquid salt, usually fluoride- or chloride-based, as either a coolant with a solid fuel (such as fluoride salt-cooled high temperature reactors) or as a combined coolant and

  14. Chemistry control and corrosion mitigation of heat transfer salts for the fluoride salt reactor (FHR)

    SciTech Connect (OSTI)

    Kelleher, B. C.; Sellers, S. R.; Anderson, M. H.; Sridharan, K.; Scheele, R. D.

    2012-07-01

    The Molten Salt Reactor Experiment (MSRE) was a prototype nuclear reactor which operated from 1965 to 1969 at Oak Ridge National Laboratory. The MSRE used liquid fluoride salts as a heat transfer fluid and solvent for fluoride based {sup 235}U and {sup 233}U fuel. Extensive research was performed in order to optimize the removal of oxide and metal impurities from the reactor's heat transfer salt, 2LiF-BeF{sub 2} (FLiBe). This was done by sparging a mixture of anhydrous hydrofluoric acid and hydrogen gas through the FLiBe at elevated temperatures. The hydrofluoric acid reacted with oxides and hydroxides, fluorinating them while simultaneously releasing water vapor. Metal impurities such as iron and chromium were reduced by hydrogen gas and filtered out of the salt. By removing these impurities, the corrosion of reactor components was minimized. The Univ. of Wisconsin - Madison is currently researching a new chemical purification process for fluoride salts that make use of a less dangerous cleaning gas, nitrogen trifluoride. Nitrogen trifluoride has been predicted as a superior fluorinating agent for fluoride salts. These purified salts will subsequently be used for static and loop corrosion tests on a variety of reactor materials to ensure materials compatibility for the new FHR designs. Demonstration of chemistry control methodologies along with potential reduction in corrosion is essential for the use of a fluoride salts in a next generator nuclear reactor system. (authors)

  15. Characterization of the molten salt reactor experiment fuel and flush salts

    SciTech Connect (OSTI)

    Williams, D.F.; Peretz, F.J.

    1996-05-01

    Wise decisions about the handling and disposition of spent fuel from the Molten Salt Reactor Experiment (MSRE) must be based upon an understanding of the physical, chemical, and radiological properties of the frozen fuel and flush salts. These {open_quotes}static{close_quotes} properties can be inferred from the extensive documentation of process history maintained during reactor operation and the knowledge gained in laboratory development studies. Just as important as the description of the salt itself is an understanding of the dynamic processes which continue to transform the salt composition and govern its present and potential physicochemical behavior. A complete characterization must include a phenomenological characterization in addition to the typical summary of properties. This paper reports on the current state of characterization of the fuel and flush salts needed to support waste management decisions.

  16. FINAL REPORT DM1200 TESTS WITH AZ 101 HLW SIMULANTS VSL-03R3800-4 REV 0 2/17/04

    SciTech Connect (OSTI)

    KRUGER AA; MATLACK KS; BARDAKCI T; D'ANGELO NA; GONG W; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM 1200 HLW Pilot Melter during processing of simulated HLW AZ-101 feed. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW AZ-101 feed; determine the effect of bubbling rate and feed solids content on production rate; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and to perform pre- and post-test inspections of system components. The test objectives (including test success criteria), along with how they were met, are outlined in a table.

  17. Corrosion of aluminides by molten nitrate salt

    SciTech Connect (OSTI)

    Tortorelli, P.F.; Bishop, P.S.

    1990-01-01

    The corrosion of titanium-, iron-, and nickel-based aluminides by a highly aggressive, oxidizing NaNO{sub 3}(-KNO{sub 3})-Na{sub 2}O{sub 2} has been studied at 650{degree}C. It was shown that weight changes could be used to effectively evaluate corrosion behavior in the subject nitrate salt environments provided these data were combined with salt analyses and microstructural examinations. The studies indicated that the corrosion of relatively resistant aluminides by these nitrate salts proceeded by oxidation and a slow release from an aluminum-rich product layer into the salt at rates lower than that associated with many other types of metallic materials. The overall corrosion process and resulting rate depended on the particular aluminide being exposed. In order to minimize corrosion of nickel or iron aluminides, it was necessary to have aluminum concentrations in excess of 30 at. %. However, even at a concentration of 50 at. % Al, the corrosion resistance of TiAl was inferior to that of Ni{sub 3}Al and Fe{sub 3}Al. At higher aluminum concentrations, iron, nickel, and iron-nickel aluminides exhibited quite similar weight changes, indicative of the principal role of aluminum in controlling the corrosion process in NaNO{sub 3}(-KNO{sub 3})-Na{sub 2}O{sub 2} salts. 20 refs., 5 figs., 3 tabs.

  18. Ethylenediamine salt of 5-nitrotetrazole and preparation

    DOE Patents [OSTI]

    Lee, K.; Coburn, M.D.

    1984-05-17

    The ethylenediamine salt of 5-nitrotetrazole has been found to be useful as an explosive alone and in eutectic mixtures with ammonium nitrate and/or other explosive compounds. Its eutectic with ammonium nitrate has been demonstrated to behave in a similar manner to a monomolecular explosive such as TNT, and is less sensitive than the pure salt. Moreover, this eutectic mixture, which contains 87.8 mol% of ammonium nitrate, is close to the CO/sub 2/-balanced composition of 90 mol%, and has a relatively low melting point of 110.5 C making it readily castable. The ternary eutectic system containing the ethylenediamine salt of 5-nitrotetrazole, ammonium nitrate and ethylenediamine dinitrate has a eutectic temperature of 89.5 C and gives a measured detonation pressure of 24.8 GPa, which is 97.6% of the calculated value. Both the pure ethylenediamine salt and its known eutectic compounds behave in substantially ideal manner. Methods for the preparation of the salt are described.

  19. Brine flow in heated geologic salt.

    SciTech Connect (OSTI)

    Kuhlman, Kristopher L.; Malama, Bwalya

    2013-03-01

    This report is a summary of the physical processes, primary governing equations, solution approaches, and historic testing related to brine migration in geologic salt. Although most information presented in this report is not new, we synthesize a large amount of material scattered across dozens of laboratory reports, journal papers, conference proceedings, and textbooks. We present a mathematical description of the governing brine flow mechanisms in geologic salt. We outline the general coupled thermal, multi-phase hydrologic, and mechanical processes. We derive these processes' governing equations, which can be used to predict brine flow. These equations are valid under a wide variety of conditions applicable to radioactive waste disposal in rooms and boreholes excavated into geologic salt.

  20. Surface composition, microstructure and corrosion resistance of AZ31 magnesium alloy irradiated by high-intensity pulsed ion beam

    SciTech Connect (OSTI)

    Li, P., E-mail: pli@sqnc.edu.cn [Department of Physics and Information Engineering, Shangqiu Normal University, Shangqiu 476000 (China); Surface Engineering Laboratory, School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024 (China); Lei, M.K., E-mail: surfeng@dlut.edu.cn [Surface Engineering Laboratory, School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024 (China); Zhu, X.P. [Surface Engineering Laboratory, School of Materials Science and Engineering, Dalian University of Technology, Dalian 116024 (China)

    2011-06-15

    High-intensity pulsed ion beam (HIPIB) irradiation of AZ31 magnesium alloy is performed and electrochemical corrosion experiment of irradiated samples is carried out by using potentiodynamic polarization technology in order to explore the effect of HIPIB irradiation on corrosion resistance of magnesium alloy. The surface composition, cross-sectional morphology and microstructure are characterized by using electron probe microanalyzer, optical microscope and transmission electron microscope, respectively. The results indicated that HIPIB irradiation leads to a significant improvement in corrosion resistance of magnesium alloy, in terms of the considerable increase in both corrosion potential and pitting breakdown potential. The microstructural refinement and surface purification induced by HIPIB irradiation are responsible for the improved corrosion resistance. - Research Highlights: {yields} A modified layer about 30 {mu}m thick is obtained by HIPIB irradiation. {yields} Selective ablation of element/impurity phase having lower melting point is observed. {yields} More importantly, microstructural refinement occurred on the irradiated surface. {yields} The modified layer exhibited a significantly improved corrosion resistance. {yields} Improved corrosion resistance is ascribed to the combined effect induced by HIPIB.

  1. Microstructure formation in partially melted zone during gas tungsten arc welding of AZ91 Mg cast alloy

    SciTech Connect (OSTI)

    Zhu Tianping Chen, Zhan W.; Gao Wei

    2008-11-15

    During gas tungsten arc (GTA) welding of AZ91 Mg cast alloy, constitutional liquid forms locally in the original interdendritic regions in the partially melted zone (PMZ). The PMZ re-solidification behaviour has not been well understood. In this study, the gradual change of the re-solidification microstructure within PMZ from base metal side to weld metal side was characterised. High cooling rate experiments using Gleeble thermal simulator were also conducted to understand the morphological change of the {alpha}-Mg/{beta}-Mg{sub 17}Al{sub 12} phase interface formed during re-solidification after partial melting. It was found that the original partially divorced eutectic structure has become a more regular eutectic phase in most of the PMZ, although close to the fusion boundary the re-solidified eutectic is again a divorced one. Proceeding the eutectic re-solidification, if the degree of partial melting is sufficiently high, {alpha}-Mg re-solidified with a cellular growth, resulting in a serrated interface between {alpha}-Mg and {alpha}-Mg/{beta}-Mg{sub 17}Al{sub 12} in the weld sample and between {alpha}-Mg and {beta}-Mg{sub 17}Al{sub 12} (fully divorced eutectic) in Gleeble samples. The morphological changes affected by the peak temperature and cooling rate are also explained.

  2. High Temperature Fluoride Salt Test Loop

    SciTech Connect (OSTI)

    Aaron, Adam M.; Cunningham, Richard Burns; Fugate, David L.; Holcomb, David Eugene; Kisner, Roger A.; Peretz, Fred J.; Robb, Kevin R.; Wilson, Dane F.; Yoder, Jr, Graydon L.

    2015-12-01

    Effective high-temperature thermal energy exchange and delivery at temperatures over 600°C has the potential of significant impact by reducing both the capital and operating cost of energy conversion and transport systems. It is one of the key technologies necessary for efficient hydrogen production and could potentially enhance efficiencies of high-temperature solar systems. Today, there are no standard commercially available high-performance heat transfer fluids above 600°C. High pressures associated with water and gaseous coolants (such as helium) at elevated temperatures impose limiting design conditions for the materials in most energy systems. Liquid salts offer high-temperature capabilities at low vapor pressures, good heat transport properties, and reasonable costs and are therefore leading candidate fluids for next-generation energy production. Liquid-fluoride-salt-cooled, graphite-moderated reactors, referred to as Fluoride Salt Reactors (FHRs), are specifically designed to exploit the excellent heat transfer properties of liquid fluoride salts while maximizing their thermal efficiency and minimizing cost. The FHR s outstanding heat transfer properties, combined with its fully passive safety, make this reactor the most technologically desirable nuclear power reactor class for next-generation energy production. Multiple FHR designs are presently being considered. These range from the Pebble Bed Advanced High Temperature Reactor (PB-AHTR) [1] design originally developed by UC-Berkeley to the Small Advanced High-Temperature Reactor (SmAHTR) and the large scale FHR both being developed at ORNL [2]. The value of high-temperature, molten-salt-cooled reactors is also recognized internationally, and Czechoslovakia, France, India, and China all have salt-cooled reactor development under way. The liquid salt experiment presently being developed uses the PB-AHTR as its focus. One core design of the PB-AHTR features multiple 20 cm diameter, 3.2 m long fuel channels with 3 cm diameter graphite-based fuel pebbles slowly circulating up through the core. Molten salt coolant (FLiBe) at 700°C flows concurrently (at significantly higher velocity) with the pebbles and is used to remove heat generated in the reactor core (approximately 1280 W/pebble), and supply it to a power conversion system. Refueling equipment continuously sorts spent fuel pebbles and replaces spent or damaged pebbles with fresh fuel. By combining greater or fewer numbers of pebble channel assemblies, multiple reactor designs with varying power levels can be offered. The PB-AHTR design is discussed in detail in Reference [1] and is shown schematically in Fig. 1. Fig. 1. PB-AHTR concept (drawing taken from Peterson et al., Design and Development of the Modular PB-AHTR Proceedings of ICApp 08). Pebble behavior within the core is a key issue in proving the viability of this concept. This includes understanding the behavior of the pebbles thermally, hydraulically, and mechanically (quantifying pebble wear characteristics, flow channel wear, etc). The experiment being developed is an initial step in characterizing the pebble behavior under realistic PB-AHTR operating conditions. It focuses on thermal and hydraulic behavior of a static pebble bed using a convective salt loop to provide prototypic fluid conditions to the bed, and a unique inductive heating technique to provide prototypic heating in the pebbles. The facility design is sufficiently versatile to allow a variety of other experimentation to be performed in the future. The facility can accommodate testing of scaled reactor components or sub-components such as flow diodes, salt-to-salt heat exchangers, and improved pump designs as well as testing of refueling equipment, high temperature instrumentation, and other reactor core designs.

  3. CESIUM REMOVAL FROM TANKS 241-AN-103 & 241-SX-105 & 241-AZ-101/102 COMPOSITE FOR TESTING IN BENCH SCALE STEAM REFORMER

    SciTech Connect (OSTI)

    DUNCAN JB; HUBER HJ

    2011-06-08

    This report documents the preparation of three actual Hanford tank waste samples for shipment to the Savannah River National Laboratory (SRNL). Two of the samples were dissolved saltcakes from tank 241-AN-103 (hereafter AN-103) and tank 241-SX-105 (hereafter SX-105); one sample was a supernate composite from tanks 241-AZ-101 and 241-AZ-102 (hereafter AZ-101/102). The preparation of the samples was executed following the test plans LAB-PLAN-10-00006, Test Plan for the Preparation of Samples from Hanford Tanks 241-SX-105, 241-AN-103, 241-AN-107, and LAB-PLN-10-00014, Test Plan for the Preparation of a Composite Sample from Hanford Tanks 241-AZ-101 and 241-AZ-102 for Steam Reformer Testing at the Savannah River National Laboratory. All procedural steps were recorded in laboratory notebook HNF-N-274 3. Sample breakdown diagrams for AN-103 and SX-105 are presented in Appendix A. The tank samples were prepared in support of a series of treatability studies of the Fluidized Bed Steam Reforming (FBSR) process using a Bench-Scale Reformer (BSR) at SRNL. Tests with simulants have shown that the FBSR mineralized waste form is comparable to low-activity waste glass with respect to environmental durability (WSRC-STI-2008-00268, Mineralization of Radioactive Wastes by Fluidized Bed Steam Reforming (FBSR): Comparisons to Vitreous Waste Forms and Pertinent Durability Testing). However, a rigorous assessment requires long-term performance data from FB SR product formed from actual Hanford tank waste. Washington River Protection Solutions, LLC (WRPS) has initiated a Waste Form Qualification Program (WP-S.2.1-20 1 0-00 1, Fluidized Bed Steam Reformer Low-level Waste Form Qualification) to gather the data required to demonstrate that an adequate FBSR mineralized waste form can be produced. The documentation of the selection process of the three tank samples has been separately reported in RPP-48824, 'Sample Selection Process for Bench-Scale Steam Reforming Treatability Studies Using Hanford Waste Samples.'

  4. Hybrid Molten Salt Reactor (HMSR) System Study

    SciTech Connect (OSTI)

    Woolley, Robert D; Miller, Laurence F

    2014-04-01

    Can the hybrid system combination of (1) a critical fission Molten Salt Reactor (MSR) having a thermal spectrum and a high Conversion Ratio (CR) with (2) an external source of high energy neutrons provide an attractive solution to the world's expanding demand for energy? The present study indicates the answer is an emphatic yes.

  5. Salt repository project closeout status report

    SciTech Connect (OSTI)

    1988-06-01

    This report provides an overview of the scope and status of the US Department of Energy (DOE`s) Salt Repository Project (SRP) at the time when the project was terminated by the Nuclear Waste Policy Amendments Act of 1987. The report reviews the 10-year program of siting a geologic repository for high-level nuclear waste in rock salt formations. Its purpose is to aid persons interested in the information developed during the course of this effort. Each area is briefly described and the major items of information are noted. This report, the three salt Environmental Assessments, and the Site Characterization Plan are the suggested starting points for any search of the literature and information developed by the program participants. Prior to termination, DOE was preparing to characterize three candidate sites for the first mined geologic repository for the permanent disposal of high-level nuclear waste. The sites were in Nevada, a site in volcanic tuff; Texas, a site in bedded salt (halite); and Washington, a site in basalt. These sites, identified by the screening process described in Chapter 3, were selected from the nine potentially acceptable sites shown on Figure I-1. These sites were identified in accordance with provisions of the Nuclear Waste Policy Act of 1982. 196 refs., 21 figs., 11 tabs.

  6. Accelerators for Subcritical Molten-Salt Reactors

    SciTech Connect (OSTI)

    Johnson, Roland

    2011-08-03

    Accelerator parameters for subcritical reactors have usually been based on using solid nuclear fuel much like that used in all operating critical reactors as well as the thorium burning accelerator-driven energy amplifier proposed by Rubbia et al. An attractive alternative reactor design that used molten salt fuel was experimentally studied at ORNL in the 1960s, where a critical molten salt reactor was successfully operated using enriched U235 or U233 tetrafluoride fuels. These experiments give confidence that an accelerator-driven subcritical molten salt reactor will work better than conventional reactors, having better efficiency due to their higher operating temperature, having the inherent safety of subcritical operation, and having constant purging of volatile radioactive elements to eliminate their accumulation and potential accidental release in dangerous amounts. Moreover, the requirements to drive a molten salt reactor can be considerably relaxed compared to a solid fuel reactor, especially regarding accelerator reliability and spallation neutron targetry, to the point that much of the required technology exists today. It is proposed that Project-X be developed into a prototype commercial machine to produce energy for the world by, for example, burning thorium in India and nuclear waste from conventional reactors in the USA.

  7. BLM Fact Sheet- Vulcan Power Company Salt Wells Geothermal Energy...

    Open Energy Info (EERE)

    Vulcan Power Company Salt Wells Geothermal Energy Project Jump to: navigation, search OpenEI Reference LibraryAdd to library Report: BLM Fact Sheet- Vulcan Power Company Salt Wells...

  8. File:Salt2.pdf | Open Energy Information

    Open Energy Info (EERE)

    Salt2.pdf Jump to: navigation, search File File history File usage Metadata File:Salt2.pdf Size of this preview: 463 599 pixels. Other resolution: 464 600 pixels. Go to page...

  9. Completing Salt Waste Processing Facility is an EM Priority and...

    Office of Environmental Management (EM)

    Completing Salt Waste Processing Facility is an EM Priority and Key to SRS Cleanup Progress Completing Salt Waste Processing Facility is an EM Priority and Key to SRS Cleanup ...

  10. Development of Molten-Salt Heat Trasfer Fluid Technology for...

    Office of Environmental Management (EM)

    Abengoa Solar Sunshot Conf erence Project Review Development of M olt en-Salt Heat Transf ... generat ion of organic heat t ransport f luids w it h low f reeze point molt en salt s. ...

  11. Energy Efficient Buildings, Salt Lake County, Utah

    SciTech Connect (OSTI)

    Barnett, Kimberly

    2012-04-30

    Executive Summary Salt Lake County's Solar Photovoltaic Project - an unprecedented public/private partnership Salt Lake County is pleased to announce the completion of its unprecedented solar photovoltaic (PV) installation on the Calvin R. Rampton Salt Palace Convention Center. This 1.65 MW installation will be one the largest solar roof top installations in the country and will more than double the current installed solar capacity in the state of Utah. Construction is complete and the system will be operational in May 2012. The County has accomplished this project using a Power Purchase Agreement (PPA) financing model. In a PPA model a third-party solar developer will finance, develop, own, operate, and maintain the solar array. Salt Lake County will lease its roof, and purchase the power from this third-party under a long-term Power Purchase Agreement contract. In fact, this will be one of the first projects in the state of Utah to take advantage of the recent (March 2010) legislation which makes PPA models possible for projects of this type. In addition to utilizing a PPA, this solar project will employ public and private capital, Energy Efficiency and Conservation Block Grants (EECBG), and public/private subsidized bonds that are able to work together efficiently because of the recent stimulus bill. The project also makes use of recent changes to federal tax rules, and the recent re-awakening of private capital markets that make a significant public-private partnership possible. This is an extremely innovative project, and will mark the first time that all of these incentives (EECBG grants, Qualified Energy Conservation Bonds, New Markets tax credits, investment tax credits, public and private funds) have been packaged into one project. All of Salt Lake County's research documents and studies, agreements, and technical information is available to the public. In addition, the County has already shared a variety of information with the public through webinars, site tours, presentations, and written correspondence.

  12. Molten salt considerations for accelerator-driven subcritical fission to

    Office of Scientific and Technical Information (OSTI)

    close the nuclear fuel cycle (Journal Article) | SciTech Connect Molten salt considerations for accelerator-driven subcritical fission to close the nuclear fuel cycle Citation Details In-Document Search Title: Molten salt considerations for accelerator-driven subcritical fission to close the nuclear fuel cycle The host salt selection, molecular modeling, physical chemistry, and processing chemistry are presented here for an accelerator-driven subcritical fission in a molten salt core

  13. PROJECT PROFILE: Salt Lake City Corporation (Solar Market Pathways) |

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

    Department of Energy Salt Lake City Corporation (Solar Market Pathways) PROJECT PROFILE: Salt Lake City Corporation (Solar Market Pathways) Title: Wasatch Solar Project WASATCH solar logo.png Funding Opportunity: Solar Market Pathways SunShot Subprogram: Soft Costs Location: Salt Lake City, UT Amount Awarded: $600,000 Awardee Cost Share: $164,645 Salt Lake City and its partners are developing a comprehensive long-term solar deployment strategy, which includes an analysis of the value of

  14. Savannah River Site Salt Waste Processing Facility Technology Readiness

    Energy Savers [EERE]

    Assessment Report | Department of Energy Salt Waste Processing Facility Technology Readiness Assessment Report Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report Full Document and Summary Versions are available for download PDF icon Savannah River Site Salt Waste Processing Facility Technology Readiness Assessment Report PDF icon Summary - SRS Salt Waste Processing Facility More Documents & Publications Compilation of TRA Summaries Basis for Section

  15. Method for preparing salt solutions having desired properties

    DOE Patents [OSTI]

    Ally, Moonis R.; Braunstein, Jerry

    1994-01-01

    The specification discloses a method for preparing salt solutions which exhibit desired thermodynamic properties. The method enables prediction of the value of the thermodynamic properties for single and multiple salt solutions over a wide range of conditions from activity data and constants which are independent of concentration and temperature. A particular application of the invention is in the control of salt solutions in a process to provide a salt solution which exhibits the desired properties.

  16. Liquid Fluoride Salt Experimentation Using a Small Natural Circulation Cell

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect SciTech Connect Search Results Technical Report: Liquid Fluoride Salt Experimentation Using a Small Natural Circulation Cell Citation Details In-Document Search Title: Liquid Fluoride Salt Experimentation Using a Small Natural Circulation Cell A small molten fluoride salt experiment has been constructed and tested to develop experimental techniques for application in liquid fluoride salt systems. There were five major objectives in developing this test

  17. Combinations of fluorinated solvents with imide salts or methide salts for electrolytes

    DOE Patents [OSTI]

    Tikhonov, Konstantin; Yip, Ka Ki; Lin, Tzu-Yuan; Lei, Norman; Guerrero-Zavala, Guillermo; Kwong, Kristie W

    2015-11-10

    Provided are electrochemical cells and electrolytes used to build such cells. The electrolytes include imide salts and/or methide salts as well as fluorinated solvents capable of maintaining single phase solutions at between about -30.degree. C. to about 80.degree. C. The fluorinated solvents, such as fluorinated carbonates, fluorinated esters, and fluorinated esters, are less flammable than their non-fluorinated counterparts and improve safety characteristics of cells containing these solvents. The amount of fluorinated solvents in electrolytes may be between about 30% and 80% by weight not accounting weight of the salts. Linear and cyclic imide salts, such as LiN(SO.sub.2CF.sub.2CF.sub.3).sub.2, and LiN(SO.sub.2CF.sub.3).sub.2, as well as methide salts, such as LiC(SO.sub.2CF.sub.3).sub.3 and LiC(SO.sub.2CF.sub.2CF.sub.3).sub.3, may be used in these electrolytes. Fluorinated alkyl groups enhance solubility of these salts in the fluorinated solvents. In some embodiments, the electrolyte may also include a flame retardant, such as a phosphazene, and/or one or more ionic liquids.

  18. Production of carboxylic acid and salt co-products

    DOE Patents [OSTI]

    Hanchar, Robert J.; Kleff, Susanne; Guettler, Michael V.

    2014-09-09

    This invention provide processes for producing carboxylic acid product, along with useful salts. The carboxylic acid product that is produced according to this invention is preferably a C.sub.2-C.sub.12 carboxylic acid. Among the salts produced in the process of the invention are ammonium salts.

  19. EIA - Natural Gas Pipeline Network - Salt Cavern Storage Reservoir

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

    Configuration Salt Cavern Storage Reservoir Configuration About U.S. Natural Gas Pipelines - Transporting Natural Gas based on data through 2007/2008 with selected updates Salt Cavern Underground Natural Gas Storage Reservoir Configuration Salt Cavern Underground Natural Gas Storage Reservoir Configuration Source: PB Energy Storage Services Inc.

  20. SOLUTION MINING IN SALT DOMES OF THE GULF COAST EMBAYMENT

    SciTech Connect (OSTI)

    Griswold, G. B.

    1981-02-01

    Following a description of salt resources in the salt domes of the gulf coast embayment, mining, particularly solution mining, is described. A scenario is constructed which could lead to release of radioactive waste stored in a salt dome via inadvertent solution mining and the consequences of this scenario are analyzed.

  1. Advanced heat exchanger development for molten salts

    SciTech Connect (OSTI)

    Sabharwall, Piyush; Clark, Denis; Glazoff, Michael; Zheng, Guiqiu; Sridharan, Kumar; Anderson, Mark

    2014-12-01

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.

  2. Supplemental Cooling for Nitrate Salt Waste

    SciTech Connect (OSTI)

    Goldberg, Mitchell S.

    2015-08-19

    In July 2015, Los Alamos National Laboratory completed installation of a supplemental cooling system in the structure where remediated nitrate salt waste drums are stored. Although the waste currently is in a safe configuration and is monitored daily,controlling the temperature inside the structure adds another layer of protection for workers, the public,and the environment.This effort is among several layers of precautions designed to secure the waste.

  3. Molten salt battery having inorganic paper separator

    DOE Patents [OSTI]

    Walker, Jr., Robert D.

    1977-01-01

    A high temperature secondary battery comprises an anode containing lithium, a cathode containing a chalcogen or chalcogenide, a molten salt electrolyte containing lithium ions, and a separator comprising a porous sheet comprising a homogenous mixture of 2-20 wt.% chrysotile asbestos fibers and the remainder inorganic material non-reactive with the battery components. The non-reactive material is present as fibers, powder, or a fiber-powder mixture.

  4. Advanced heat exchanger development for molten salts

    SciTech Connect (OSTI)

    Sabharwall, Piyush; Clark, Denis; Glazoff, Michael; Zheng, Guiqiu; Sridharan, Kumar; Anderson, Mark

    2014-12-01

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet material in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.

  5. 2015 VIII MECHANICAL BEHAVIOR OF SALT

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

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

  6. Stationary phase deposition based on onium salts

    DOE Patents [OSTI]

    Wheeler, David R.; Lewis, Patrick R.; Dirk, Shawn M.; Trudell, Daniel E.

    2008-01-01

    Onium salt chemistry can be used to deposit very uniform thickness stationary phases on the wall of a gas chromatography column. In particular, the stationary phase can be bonded to non-silicon based columns, especially microfabricated metal columns. Non-silicon microfabricated columns may be manufactured and processed at a fraction of the cost of silicon-based columns. In addition, the method can be used to phase-coat conventional capillary columns or silicon-based microfabricated columns.

  7. Advanced heat exchanger development for molten salts

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

    Sabharwall, Piyush; Clark, Denis; Glazoff, Michael; Zheng, Guiqiu; Sridharan, Kumar; Anderson, Mark

    2014-12-01

    This study addresses present work concerned with advanced heat exchanger development for molten salt in nuclear and non nuclear thermal systems. The molten salt systems discussed herein use alloys, such as Hastelloy N and 242, which show corrosion resistance to molten salt at nominal operating temperatures up to 700°C. These alloys were diffusion welded, and the corresponding information is presented. Test specimens were prepared for exposing diffusion welds to molten salt environments. Hastelloy N and 242 were found to be weldable by diffusion welding, with ultimate tensile strengths about 90% of base metal values. Both diffusion welds and sheet materialmore » in Hastelloy N were corrosion tested in?58 mol% KF and 42 mol% ZrF4 at 650, 700, and 850°C for 200, 500, and 1,000 hours. Corrosion rates found were similar between welded and nonwelded materials, typically <10 mils per year. For materials of construction, nickel and alloys with dense nickel coatings are effectively inert to corrosion in fluorides, but not so in chlorides. Hence, additional testing of selected alloys for resistance to intergranular corrosion is needed, as is a determination of corrosion rate as a function of contaminant type and alloy composition with respect to chromium and carbon to better define the optimal chromium and carbon composition, independent of galvanic or differential solubility effects. Also presented is the division of the nuclear reactor and high temperature components per ASME standards, along with design requirements for a subcritical Rankine power cycle heat exchanger that has to overcome pressure difference of about 17 MPa.« less

  8. Waste Isolation Pilot Plant Salt Decontamination Testing

    SciTech Connect (OSTI)

    Rick Demmer; Stephen Reese

    2014-09-01

    On February 14, 2014, americium and plutonium contamination was released in the Waste Isolation Pilot Plant (WIPP) salt caverns. At the request of WIPP’s operations contractor, Idaho National Laboratory (INL) personnel developed several methods of decontaminating WIPP salt, using surrogate contaminants and also americium (241Am). The effectiveness of the methods is evaluated qualitatively, and to the extent possible, quantitatively. One of the requirements of this effort was delivering initial results and recommendations within a few weeks. That requirement, in combination with the limited scope of the project, made in-depth analysis impractical in some instances. Of the methods tested (dry brushing, vacuum cleaning, water washing, strippable coatings, and mechanical grinding), the most practical seems to be water washing. Effectiveness is very high, and it is very easy and rapid to deploy. The amount of wastewater produced (2 L/m2) would be substantial and may not be easy to manage, but the method is the clear winner from a usability perspective. Removable surface contamination levels (smear results) from the strippable coating and water washing coupons found no residual removable contamination. Thus, whatever is left is likely adhered to (or trapped within) the salt. The other option that shows promise is the use of a fixative barrier. Bartlett Nuclear, Inc.’s Polymeric Barrier System (PBS) proved the most durable of the coatings tested. The coatings were not tested for contaminant entrapment, only for coating integrity and durability.

  9. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOE Patents [OSTI]

    Mullins, Lawrence J.; Christensen, Dana C.

    1984-01-01

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium from electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  10. Pyrochemical process for extracting plutonium from an electrolyte salt

    DOE Patents [OSTI]

    Mullins, L.J.; Christensen, D.C.

    1982-09-20

    A pyrochemical process for extracting plutonium from a plutonium-bearing salt is disclosed. The process is particularly useful in the recovery of plutonium for electrolyte salts which are left over from the electrorefining of plutonium. In accordance with the process, the plutonium-bearing salt is melted and mixed with metallic calcium. The calcium reduces ionized plutonium in the salt to plutonium metal, and also causes metallic plutonium in the salt, which is typically present as finely dispersed metallic shot, to coalesce. The reduced and coalesced plutonium separates out on the bottom of the reaction vessel as a separate metallic phase which is readily separable from the overlying salt upon cooling of the mixture. Yields of plutonium are typically on the order of 95%. The stripped salt is virtually free of plutonium and may be discarded to low-level waste storage.

  11. Liquid Fluoride Salt Experimentation Using a Small Natural Circulation Cell

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L; Heatherly, Dennis Wayne; Williams, David F; Elkassabgi, Yousri M.; Caja, Joseph; Caja, Mario; Jordan, John; Salinas, Roberto

    2014-04-01

    A small molten fluoride salt experiment has been constructed and tested to develop experimental techniques for application in liquid fluoride salt systems. There were five major objectives in developing this test apparatus: Allow visual observation of the salt during testing (how can lighting be introduced, how can pictures be taken, what can be seen) Determine if IR photography can be used to examine components submerged in the salt Determine if the experimental configuration provides salt velocity sufficient for collection of corrosion data for future experimentation Determine if a laser Doppler velocimeter can be used to quantify salt velocities. Acquire natural circulation heat transfer data in fluoride salt at temperatures up to 700oC All of these objectives were successfully achieved during testing with the exception of the fourth: acquiring velocity data using the laser Doppler velocimeter. This paper describes the experiment and experimental techniques used, and presents data taken during natural circulation testing.

  12. Polymeric salt bridges for conducting electric current in microfluidic devices

    DOE Patents [OSTI]

    Shepodd, Timothy J.; Tichenor, Mark S.; Artau, Alexander

    2009-11-17

    A "cast-in-place" monolithic microporous polymer salt bridge for conducting electrical current in microfluidic devices, and methods for manufacture thereof is disclosed. Polymeric salt bridges are formed in place in capillaries or microchannels. Formulations are prepared with monomer, suitable cross-linkers, solvent, and a thermal or radiation responsive initiator. The formulation is placed in a desired location and then suitable radiation such as UV light is used to polymerize the salt bridge within a desired structural location. Embodiments are provided wherein the polymeric salt bridges have sufficient porosity to allow ionic migration without bulk flow of solvents therethrough. The salt bridges form barriers that seal against fluid pressures in excess of 5000 pounds per square inch. The salt bridges can be formulated for carriage of suitable amperage at a desired voltage, and thus microfluidic devices using such salt bridges can be specifically constructed to meet selected analytical requirements.

  13. An Overview of Liquid Fluoride Salt Heat Transport Technology

    SciTech Connect (OSTI)

    Cetiner, Mustafa Sacit; Holcomb, David Eugene

    2010-01-01

    Liquid fluoride salts are a leading candidate heat transport medium for high-temperature applications. This report provides an overview of the current status of liquid salt heat transport technology. The report includes a high-level, parametric evaluation of liquid fluoride salt heat transport loop performance to allow intercomparisons between heat-transport fluid options as well as providing an overview of the properties and requirements for a representative loop. Much of the information presented here derives from the earlier molten salt reactor program and a significant advantage of fluoride salts, as high temperature heat transport media is their consequent relative technological maturity. The report also includes a compilation of relevant thermophysical properties of useful heat transport fluoride salts. Fluoride salts are both thermally stable and with proper chemistry control can be relatively chemically inert. Fluoride salts can, however, be highly corrosive depending on the container materials selected, the salt chemistry, and the operating procedures used. The report also provides an overview of the state-of-the-art in reduction-oxidation chemistry control methodologies employed to minimize salt corrosion as well as providing a general discussion of heat transfer loop operational issues such as start-up procedures and freeze-up vulnerability.

  14. Tank 37H Salt Removal Batch Process and Salt Dissolution Mixing Study

    SciTech Connect (OSTI)

    Kwon, K.C.

    2001-09-18

    Tank 30H is the receipt tank for concentrate from the 3H Evaporator. Tank 30H has had problems, such as cooling coil failure, which limit its ability to receive concentrate from the 3H Evaporator. SRS High Level Waste wishes to use Tank 37H as the receipt tank for the 3H Evaporator concentrate. Prior to using Tank 37H as the 3H Evaporator concentrate receipt tank, HLW must remove 50 inches of salt cake from the tank. They requested SRTC to evaluate various salt removal methods for Tank 37H. These methods include slurry pumps, Flygt mixers, the modified density gradient method, and molecular diffusion.

  15. Salt disposal of heat-generating nuclear waste.

    SciTech Connect (OSTI)

    Leigh, Christi D.; Hansen, Francis D.

    2011-01-01

    This report summarizes the state of salt repository science, reviews many of the technical issues pertaining to disposal of heat-generating nuclear waste in salt, and proposes several avenues for future science-based activities to further the technical basis for disposal in salt. There are extensive salt formations in the forty-eight contiguous states, and many of them may be worthy of consideration for nuclear waste disposal. The United States has extensive experience in salt repository sciences, including an operating facility for disposal of transuranic wastes. The scientific background for salt disposal including laboratory and field tests at ambient and elevated temperature, principles of salt behavior, potential for fracture damage and its mitigation, seal systems, chemical conditions, advanced modeling capabilities and near-future developments, performance assessment processes, and international collaboration are all discussed. The discussion of salt disposal issues is brought current, including a summary of recent international workshops dedicated to high-level waste disposal in salt. Lessons learned from Sandia National Laboratories' experience on the Waste Isolation Pilot Plant and the Yucca Mountain Project as well as related salt experience with the Strategic Petroleum Reserve are applied in this assessment. Disposal of heat-generating nuclear waste in a suitable salt formation is attractive because the material is essentially impermeable, self-sealing, and thermally conductive. Conditions are chemically beneficial, and a significant experience base exists in understanding this environment. Within the period of institutional control, overburden pressure will seal fractures and provide a repository setting that limits radionuclide movement. A salt repository could potentially achieve total containment, with no releases to the environment in undisturbed scenarios for as long as the region is geologically stable. Much of the experience gained from United States repository development, such as seal system design, coupled process simulation, and application of performance assessment methodology, helps define a clear strategy for a heat-generating nuclear waste repository in salt.

  16. Supai salt karst features: Holbrook Basin, Arizona

    SciTech Connect (OSTI)

    Neal, J.T.

    1994-12-31

    More than 300 sinkholes, fissures, depressions, and other collapse features occur along a 70 km (45 mi) dissolution front of the Permian Supai Formation, dipping northward into the Holbrook Basin, also called the Supai Salt Basin. The dissolution front is essentially coincident with the so-called Holbrook Anticline showing local dip reversal; rather than being of tectonic origin, this feature is likely a subsidence-induced monoclinal flexure caused by the northward migrating dissolution front. Three major areas are identified with distinctive attributes: (1) The Sinks, 10 km WNW of Snowflake, containing some 200 sinkholes up to 200 m diameter and 50 m depth, and joint controlled fissures and fissure-sinks; (2) Dry Lake Valley and contiguous areas containing large collapse fissures and sinkholes in jointed Coconino sandstone, some of which drained more than 50 acre-feet ({approximately}6 {times} 10{sup 4} m{sup 3}) of water overnight; and (3) the McCauley Sinks, a localized group of about 40 sinkholes 15 km SE of Winslow along Chevelon Creek, some showing essentially rectangular jointing in the surficial Coconino Formation. Similar salt karst features also occur between these three major areas. The range of features in Supai salt are distinctive, yet similar to those in other evaporate basins. The wide variety of dissolution/collapse features range in development from incipient surface expression to mature and old age. The features began forming at least by Pliocene time and continue to the present, with recent changes reportedly observed and verified on airphotos with 20 year repetition. The evaporate sequence along interstate transportation routes creates a strategic location for underground LPG storage in leached caverns. The existing 11 cavern field at Adamana is safely located about 25 miles away from the dissolution front, but further expansion initiatives will require thorough engineering evaluation.

  17. AZ Automotive: Presentation

    Broader source: Energy.gov [DOE]

    The role of midsize automotive module suppliers in meeting the goals of the Energy Independence and Security act of 2007

  18. Molecular dynamics study of saltsolution interface: Solubility and surface charge of salt in water

    SciTech Connect (OSTI)

    Kobayashi, Kazuya; Liang, Yunfeng E-mail: matsuoka@earth.kumst.kyoto-u.ac.jp; Matsuoka, Toshifumi E-mail: matsuoka@earth.kumst.kyoto-u.ac.jp; Sakka, Tetsuo

    2014-04-14

    The NaCl saltsolution interface often serves as an example of an uncharged surface. However, recent laser-Doppler electrophoresis has shown some evidence that the NaCl crystal is positively charged in its saturated solution. Using molecular dynamics (MD) simulations, we have investigated the NaCl saltsolution interface system, and calculated the solubility of the salt using the direct method and free energy calculations, which are kinetic and thermodynamic approaches, respectively. The direct method calculation uses a saltsolution combined system. When the system is equilibrated, the concentration in the solution area is the solubility. In the free energy calculation, we separately calculate the chemical potential of NaCl in two systems, the solid and the solution, using thermodynamic integration with MD simulations. When the chemical potential of NaCl in the solution phase is equal to the chemical potential of the solid phase, the concentration of the solution system is the solubility. The advantage of using two different methods is that the computational methods can be mutually verified. We found that a relatively good estimate of the solubility of the system can be obtained through comparison of the two methods. Furthermore, we found using microsecond time-scale MD simulations that the positively charged NaCl surface was induced by a combination of a sodium-rich surface and the orientation of the interfacial water molecules.

  19. Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control,

    Office of Scientific and Technical Information (OSTI)

    Corrosion Mitigation, and Modeling (Technical Report) | SciTech Connect Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling Citation Details In-Document Search Title: Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling The concept of a molten salt reactor has existed for nearly sixty years. Previously all work was done during a large collaborative effort at Oak Ridge National Laboratory,

  20. Independent Oversight Review, Savannah River Site Salt Waste Processing

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

    Facility - April 2014 | Department of Energy Salt Waste Processing Facility - April 2014 Independent Oversight Review, Savannah River Site Salt Waste Processing Facility - April 2014 April 2014 Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Fire Protection Systems The U.S. Department of Energy (DOE) Office of Enforcement and Oversight (Independent Oversight), within the Office of Health, Safety and Security, conducted an independent review of the

  1. Liquid Salt Heat Exchanger Technology for VHTR Based Applications

    Office of Scientific and Technical Information (OSTI)

    (Technical Report) | SciTech Connect Liquid Salt Heat Exchanger Technology for VHTR Based Applications Citation Details In-Document Search Title: Liquid Salt Heat Exchanger Technology for VHTR Based Applications The objective of this research is to evaluate performance of liquid salt fluids for use as a heat carrier for transferring high-temperature process heat from the very high-temperature reactor (VHTR) to chemical process plants. Currently, helium is being considered as the heat

  2. Enterprise Assessments Salt Waste Processing Facility Construction Quality

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

    and Fire Protection Systems Follow-up Review at the Savannah River Site - January 2016 | Department of Energy Salt Waste Processing Facility Construction Quality and Fire Protection Systems Follow-up Review at the Savannah River Site - January 2016 Enterprise Assessments Salt Waste Processing Facility Construction Quality and Fire Protection Systems Follow-up Review at the Savannah River Site - January 2016 February 2016 Follow-up Review of the Salt Waste Processing Systems and Fire

  3. Voluntary Protection Program Onsite Review, Salt Waste Processing Facility

    Energy Savers [EERE]

    Construction Project - February 2013 | Department of Energy Salt Waste Processing Facility Construction Project - February 2013 Voluntary Protection Program Onsite Review, Salt Waste Processing Facility Construction Project - February 2013 February 2013 Evaluation to determine whether Salt Waste Processing Facility Construction Project is continuing to perform at a level deserving DOE-VPP Star recognition. The Team conducted its review during February 5 - 14, 2013 to determine whether

  4. DOE Issues Salt Waste Determination for the Savannah River Site |

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

    Department of Energy Salt Waste Determination for the Savannah River Site DOE Issues Salt Waste Determination for the Savannah River Site January 18, 2006 - 10:49am Addthis WASHINGTON, DC - The U.S. Department of Energy (DOE) today issued the waste determination for the treatment and stabilization of low activity salt-waste at the Savannah River Site allowing for significant reductions in environmental and health risks posed by the material. Stored in forty-nine underground tanks,

  5. Salts of alkali metal anions and process of preparing same

    DOE Patents [OSTI]

    Dye, James L.; Ceraso, Joseph M.; Tehan, Frederick J.; Lok, Mei Tak

    1978-01-01

    Compounds of alkali metal anion salts of alkali metal cations in bicyclic polyoxadiamines are disclosed. The salts are prepared by contacting an excess of alkali metal with an alkali metal dissolving solution consisting of a bicyclic polyoxadiamine in a suitable solvent, and recovered by precipitation. The salts have a gold-color crystalline appearance and are stable in a vacuum at -10.degree. C. and below.

  6. Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory |

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

    Department of Energy Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory As a part of its national security mission, the Laboratory conducts research that generates waste contaminated with radioactive isotopes. During operations, waste is processed, packaged, and shipped to licensed disposal facilities. PDF icon Remediated-Nitrate-Salt-Drums-Storage-at-Los-Alamos-National-Laboratory.pdf More Documents

  7. Delivery system for molten salt oxidation of solid waste

    DOE Patents [OSTI]

    Brummond, William A. (Livermore, CA); Squire, Dwight V. (Livermore, CA); Robinson, Jeffrey A. (Manteca, CA); House, Palmer A. (Walnut Creek, CA)

    2002-01-01

    The present invention is a delivery system for safety injecting solid waste particles, including mixed wastes, into a molten salt bath for destruction by the process of molten salt oxidation. The delivery system includes a feeder system and an injector that allow the solid waste stream to be accurately metered, evenly dispersed in the oxidant gas, and maintained at a temperature below incineration temperature while entering the molten salt reactor.

  8. DOE - Office of Legacy Management -- Penn Salt Manufacturing Co Whitemarsh

    Office of Legacy Management (LM)

    Research Laboratories - PA 20 Salt Manufacturing Co Whitemarsh Research Laboratories - PA 20 FUSRAP Considered Sites Site: PENN SALT MANUFACTURING CO., WHITEMARSH RESEARCH LABORATORIES (PA.20) Eliminated from further consideration under FUSRAP Designated Name: Not Designated Alternate Name: Penn Salt Company PA.20-1 Location: Philiadelphia , Pennsylvania PA.20-1 Evaluation Year: 1987 PA.20-1 Site Operations: Conducted process studies for recovery of uranium from fluoride scrap. PA.20-1 Site

  9. Section 3116 Waste Determinationfor Salt Disposal at the Savannah River

    Office of Environmental Management (EM)

    Site, signed by Secretary of Energy, Samuel W. Bodman | Department of Energy Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman PDF icon Section 3116 Waste Determinationfor Salt Disposal at the Savannah River Site, signed by Secretary of Energy, Samuel W. Bodman More Documents &

  10. Analysis of SPR salt cavern remedial leach program 2013. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Title: Analysis of SPR salt cavern remedial leach program 2013. The storage caverns of the US Strategic Petroleum Reserve (SPR) exhibit creep behavior resulting in reduction of ...

  11. ENEL Salt Wells Geothermal Facility | Open Energy Information

    Open Energy Info (EERE)

    Salt Wells Geothermal Facility Sector Geothermal energy Location Information Location Churchill, NV Coordinates 39.651603422063, -118.49778413773 Loading map......

  12. Hybrid Molten Salt Reactor (HMSR): Method and System to fully...

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

    Hybrid Molten Salt Reactor (HMSR): Method and System to fully fission actinides for electric power production without ... produce heat suitable for efficient electricity production. ...

  13. Assessment of Nuclear Safety Culture at the Salt Waste Processing...

    Office of Environmental Management (EM)

    Oversight Assessment of Nuclear Safety Culture at the Salt Waste Processing Facility Project ... Commission (NRC), several nuclear power generating utilities, and associated ...

  14. Accident Investigation of the February 5, 2014, Underground Salt...

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

    Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM March 26, 2014 Accident Investigation of the ...

  15. Lithium Salt-doped, Gelled Polymer Electrolyte with a Nanoporous...

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

    Find More Like This Return to Search Lithium Salt-doped, Gelled Polymer Electrolyte with a ... electrolyte material for use in lithium ion batteries that exhibits better ion ...

  16. Project Profile: Novel Molten Salts Thermal Energy Storage for...

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

    Innovation Alabama's LMP molten salt is projected to have the following ... Lower melting point Higher energy density Lower power-generation cost This program aims to develop a ...

  17. Enterprise Assessments Review of the Savannah River Site Salt...

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

    and Startup Test Plans - June 2015 Enterprise Assessments Review of the Savannah River Site Salt Waste Processing Facility Construction Quality and Startup Test Plans - June ...

  18. Sandia Energy - New Liquid Salt Electrolytes Could Lead to Cost...

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

    Salt Electrolytes Could Lead to Cost-Effective Flow Batteries Chemical technologist Harry Pratt synthesizes a copper-based ionic liquid. (Photo by Randy Montoya) Sandia...

  19. Radiometrics At Salt Wells Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Henkle, Et Al., 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Radiometrics At Salt Wells Area (Henkle, Et Al., 2005) Exploration Activity...

  20. Development Wells At Salt Wells Area (Nevada Bureau of Mines...

    Open Energy Info (EERE)

    (Nevada Bureau of Mines and Geology, 2009) Exploration Activity Details Location Salt Wells Geothermal Area Exploration Technique Development Drilling Activity Date 2005 - 2005...

  1. Savannah River Site - Salt Waste Processing Facility: Briefing...

    Office of Environmental Management (EM)

    Salt Waste Processing Facility Independent Technical Review Harry Harmon January 9, 2007 2 U.S. Department of Energy Outline * SWPF Process Overview * Major Risks * Approach for ...

  2. Salt Wells Geothermal Energy Projects Environmental Impact Statement...

    Open Energy Info (EERE)

    Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Salt Wells Geothermal Energy Projects Environmental Impact Statement Abstract Abstract unavailable....

  3. Molten salt bath circulation design for an electrolytic cell

    DOE Patents [OSTI]

    Dawless, R.K.; LaCamera, A.F.; Troup, R.L.; Ray, S.P.; Hosler, R.B.

    1999-08-17

    An electrolytic cell for reduction of a metal oxide to a metal and oxygen has an inert anode and an upwardly angled roof covering the inert mode. The angled roof diverts oxygen bubbles into an upcomer channel, thereby agitating a molten salt bath in the upcomer channel and improving dissolution of a metal oxide in the molten salt bath. The molten salt bath has a lower velocity adjacent the inert anode in order to minimize corrosion by substances in the bath. A particularly preferred cell produces aluminum by electrolysis of alumina in a molten salt bath containing aluminum fluoride and sodium fluoride. 4 figs.

  4. Molten salt bath circulation design for an electrolytic cell

    DOE Patents [OSTI]

    Dawless, Robert K.; LaCamera, Alfred F.; Troup, R. Lee; Ray, Siba P.; Hosler, Robert B.

    1999-01-01

    An electrolytic cell for reduction of a metal oxide to a metal and oxygen has an inert anode and an upwardly angled roof covering the inert mode. The angled roof diverts oxygen bubbles into an upcomer channel, thereby agitating a molten salt bath in the upcomer channel and improving dissolution of a metal oxide in the molten salt bath. The molten salt bath has a lower velocity adjacent the inert anode in order to minimize corrosion by substances in the bath. A particularly preferred cell produces aluminum by electrolysis of alumina in a molten salt bath containing aluminum fluoride and sodium fluoride.

  5. Liquid Fluoride Salt Experimentation Using a Small Natural Circulation...

    Office of Scientific and Technical Information (OSTI)

    be introduced, how can pictures be taken, what can be seen) Determine if IR photography can be used to examine components submerged in the salt Determine if the ...

  6. Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control...

    Office of Scientific and Technical Information (OSTI)

    Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, ... guide to allow anyone to learn the fundamentals of chemistry, engineering, and safety ...

  7. Salt Waste Processing Facility, Line Management Review Board Charter

    Broader source: Energy.gov [DOE]

    The Line Management Review Board (LMRB) serves an important oversight function to monitor the readiness processes and associated deliverables for the Salt Waste Processing Facility (SWPF). The...

  8. Method for the production of uranium chloride salt

    DOE Patents [OSTI]

    Westphal, Brian R.; Mariani, Robert D.

    2013-07-02

    A method for the production of UCl.sub.3 salt without the use of hazardous chemicals or multiple apparatuses for synthesis and purification is provided. Uranium metal is combined in a reaction vessel with a metal chloride and a eutectic salt- and heated to a first temperature under vacuum conditions to promote reaction of the uranium metal with the metal chloride for the production of a UCl.sub.3 salt. After the reaction has run substantially to completion, the furnace is heated to a second temperature under vacuum conditions. The second temperature is sufficiently high to selectively vaporize the chloride salts and distill them into a condenser region.

  9. Evaluation of Salt Coolants for Reactor Applications (Journal Article) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Evaluation of Salt Coolants for Reactor Applications Citation Details In-Document Search Title: Evaluation of Salt Coolants for Reactor Applications Molten fluorides were initially developed for use in the nuclear industry as the high-temperature fluid fuel for the Molten Salt Reactor (MSR). The U.S. Department of Energy Office of Nuclear Energy is exploring the use of molten salts as primary and secondary coolants in a new generation of solid-fueled, thermal-spectrum,

  10. Analysis of SPR salt cavern remedial leach program 2013. (Technical...

    Office of Scientific and Technical Information (OSTI)

    Analysis of SPR salt cavern remedial leach program 2013. Citation Details In-Document ... Sponsoring Org: USDOE National Nuclear Security Administration (NNSA) Country of ...

  11. Inexpensive, Nonfluorinated Anions for Lithium Salts and Ionic...

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

    Electrolytes Inexpensive, Nonfluorinated Anions for Lithium Salts and Ionic Liquids for Lithium Battery Electrolytes 2010 DOE Vehicle Technologies and Hydrogen Programs Annual...

  12. Coupled Thermal-Hydrological-Mechanical Processes in Salt, Hot...

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

    pressure solution and dislocation creep, with both terms dependent on effective stress to account for the effects of porosity. This provides insight into granular salt...

  13. Exploratory Well At Salt Wells Area (Bureau of Land Management...

    Open Energy Info (EERE)

    Bureau of Land Management, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Exploratory Well At Salt Wells Area (Bureau of Land Management,...

  14. Salt Lake City, Utah: Energy Resources | Open Energy Information

    Open Energy Info (EERE)

    Salt Lake City, Utah: Energy Resources Jump to: navigation, search Equivalent URI DBpedia Coordinates 40.7607793, -111.8910474 Show Map Loading map... "minzoom":false,"mapping...

  15. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

    Nitrate Salt Bearing Waste Container Isolation Plan Prepared in Response to New Mexico ... (DOE) and Nuclear Waste Partnership LLC (NWP), collectively referred to as the Permittees. ...

  16. Project Profile: Molten Salt-Carbon Nanotube Thermal Storage

    Broader source: Energy.gov [DOE]

    Texas Engineering Experiment Station (TEES), under the Thermal Storage FOA, created a composite thermal energy storage material by embedding nanoparticles in a molten salt base material.

  17. Accelerator-driven subcritical fission in molten salt core: Closing...

    Office of Scientific and Technical Information (OSTI)

    Accelerator-driven subcritical fission in molten salt core: Closing the nuclear fuel cycle for green nuclear energy Citation Details In-Document Search Title: Accelerator-driven ...

  18. Molten salt considerations for accelerator-driven subcritical...

    Office of Scientific and Technical Information (OSTI)

    to close the nuclear fuel cycle Citation Details In-Document Search Title: Molten salt considerations for accelerator-driven subcritical fission to close the nuclear fuel cycle ...

  19. BLM Approves Salt Wells Geothermal Energy Projects | Open Energy...

    Open Energy Info (EERE)

    Energy Projects Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: BLM Approves Salt Wells Geothermal Energy Projects Abstract Abstract unavailable....

  20. Enterprise Assessments Review of the Savannah River Site Salt...

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

    Salt Waste Processing Facility Construction Quality and Startup Test Plans June 2015 Office of Nuclear Safety and Environmental Assessments Office of Environment, Safety and...

  1. Voluntary Protection Program Onsite Review, Salt Waste Processing...

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

    The Team conducted its review during February 5 - 14, 2013 to determine whether Parsons ... Voluntary Protection Program Onsite Review, Parsons Corporation Salt Waste Processing ...

  2. Independent Oversight Review, Savannah River Site Salt Waste...

    Office of Environmental Management (EM)

    Salt Waste Processing Facility - April 2014 Independent Oversight Review, Savannah River Site ... 2015 Independent Oversight Review, Waste Treatment and Immobilization Plant - May 2013

  3. Salt River Electric- Residential Energy Efficiency Rebate Programs

    Broader source: Energy.gov [DOE]

    Salt River Electric serves as the rural electric provider in Kentucky's Bullitt, Nelson, Spencer, and Washington counties. Residential customers are eligible for a variety of cash incentives for...

  4. WIPP Nitrate Salt Bearing Waste Container Isolation Plan Implementatio...

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

    Nitrate Salt Bearing Waste Container Isolation Plan Implementation Update May 12, 2015 Panel 6 and Panel 7, Room 7 a. Rollback * Contamination Assessment-This prerequisite is ...

  5. Liquid fuel molten salt reactors for thorium utilization (Journal...

    Office of Scientific and Technical Information (OSTI)

    resulted in two experimental systems operating at ORNL in the 1960s, the Aircraft Reactor Experiment and the Molten Salt Reactor Experiment. Subsequent design studies in the ...

  6. Domestic Material Content in Molten-Salt Concentrating Solar...

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

    Domestic Material Content in Molten-Salt Concentrating Solar Power Plants Craig Turchi, Parthiv Kurup, Sertac Akar, and Francisco Flores Technical Report NRELTP-5500-64429 August...

  7. Water Sampling At Salt Wells Area (Shevenell & Garside, 2003...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Shevenell & Garside, 2003) Exploration Activity Details...

  8. Water Sampling At Salt Wells Area (Coolbaugh, Et Al., 2006) ...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Coolbaugh, Et Al., 2006) Exploration Activity Details...

  9. Controlled Source Frequency-Domain Magnetics At Salt Wells Area...

    Open Energy Info (EERE)

    At Salt Wells Area (Montgomery, Et Al., 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Controlled Source Frequency-Domain Magnetics At...

  10. An Overview of Liquid Fluoride Salt Heat Transport Systems

    SciTech Connect (OSTI)

    Holcomb, David Eugene; Cetiner, Sacit M

    2010-09-01

    Heat transport is central to all thermal-based forms of electricity generation. The ever increasing demand for higher thermal efficiency necessitates power generation cycles transitioning to progressively higher temperatures. Similarly, the desire to provide direct thermal coupling between heat sources and higher temperature chemical processes provides the underlying incentive to move toward higher temperature heat transfer loops. As the system temperature rises, the available materials and technology choices become progressively more limited. Superficially, fluoride salts at {approx}700 C resemble water at room temperature being optically transparent and having similar heat capacity, roughly three times the viscosity, and about twice the density. Fluoride salts are a leading candidate heat-transport material at high temperatures. Fluoride salts have been extensively used in specialized industrial processes for decades, yet they have not entered widespread deployment for general heat transport purposes. This report does not provide an exhaustive screening of potential heat transfer media and other high temperature liquids such as alkali metal carbonate eutectics or chloride salts may have economic or technological advantages. A particular advantage of fluoride salts is that the technology for their use is relatively mature as they were extensively studied during the 1940s-1970s as part of the U.S. Atomic Energy Commission's program to develop molten salt reactors (MSRs). However, the instrumentation, components, and practices for use of fluoride salts are not yet developed sufficiently for commercial implementation. This report provides an overview of the current understanding of the technologies involved in liquid salt heat transport (LSHT) along with providing references to the more detailed primary information resources. Much of the information presented here derives from the earlier MSR program. However, technology has evolved over the intervening years, and this report also describes more recently developed technologies such as dry gas seals. This report also provides a high-level, parametric evaluation of LSHT loop performance to allow general intercomparisons between heat-transport fluid options as well as provide an overview of the properties and requirements for a representative loop. A compilation of relevant thermophysical properties of useful fluoride salts is also included for salt heat transport systems. Fluoride salts can be highly corrosive depending on the container materials selected, the salt chemistry, and the operating procedures used. The report includes an overview of the state-of-the-art in reduction-oxidation chemistry control methodologies employed to minimize corrosion issues. Salt chemistry control technology, however, remains at too low a level of understanding for widespread industrial usage. Loop operational issues such as start-up procedures and system freeze-up vulnerability are also discussed. Liquid fluoride salts are a leading candidate heat transport medium for high-temperature applications. This report provides an overview of the current status of liquid salt heat transport technology. The report includes a high-level, parametric evaluation of liquid fluoride salt heat transport loop performance to allow intercomparisons between heat-transport fluid options as well as providing an overview of the properties and requirements for a representative loop. Much of the information presented here derives from the earlier molten salt reactor program and a significant advantage of fluoride salts, as high temperature heat transport media is their consequent relative technological maturity. The report also includes a compilation of relevant thermophysical properties of useful heat transport fluoride salts. Fluoride salts are both thermally stable and with proper chemistry control can be relatively chemically inert. Fluoride salts can, however, be highly corrosive depending on the container materials selected, the salt chemistry, and the operating procedures used. The report also provides an overview of the state-of-the-art in reduction-oxidation chemistry control methodologies employed to minimize salt corrosion as well as providing a general discussion of heat transfer loop operational issues such as start-up procedures and freeze-up vulnerability.

  11. Laboratory investigation of crushed salt consolidation and fracture healing

    SciTech Connect (OSTI)

    Not Available

    1987-01-01

    A laboratory test program was conducted to investigate the consolidation behavior of crushed salt and fracture healing in natural and artificial salt. Crushed salt is proposed for use as backfill in a nuclear waste repository in salt. Artificial block salt is proposed for use in sealing a repository. Four consolidation tests were conducted in a hydrostatic pressure vessel at a maximum pressure of 2500 psi (17.2 MPa) and at room temperature. Three 1-month tests were conducted on salt obtained from the Waste Isolation Pilot Plant and one 2-month test was conducted on salt from Avery Island. Permeability was obtained using argon and either a steady-state or transient method. Initial porosities ranged from 0.26 to 0.36 and initial permeabilities from 2000 to 50,000 md. Final porosities and permeabilities ranged from 0.05 to 0.19 and from <10/sup -5/ md to 110 md, respectively. The lowest final porosity (0.05) and permeability (<10/sup -5/ md) were obtained in a 1-month test in which 2.3% moisture was added to the salt at the beginning of the test. The consolidation rate was much more rapid than in any of the dry salt tests. The fracture healing program included 20 permeability tests conducted on fractured and unfractured samples. The tests were conducted in a Hoek cell at hydrostatic pressures up to 3000 psi (20.6 MPa) with durations up to 8 days. For the natural rock salt tested, permeability was strongly dependent on confining pressure and time. The effect of confining pressure was much weaker in the artificial salt. In most cases the combined effects of time and pressure were to reduce the permeability of fractured samples to the same order of magnitude (or less) as the permeability measured prior to fracturing.

  12. Alternative Waste Forms for Electro-Chemical Salt Waste

    SciTech Connect (OSTI)

    Crum, Jarrod V.; Sundaram, S. K.; Riley, Brian J.; Matyas, Josef; Arreguin, Shelly A.; Vienna, John D.

    2009-10-28

    This study was undertaken to examine alternate crystalline (ceramic/mineral) and glass waste forms for immobilizing spent salt from the Advanced Fuel Cycle Initiative (AFCI) electrochemical separations process. The AFCI is a program sponsored by U.S. Department of Energy (DOE) to develop and demonstrate a process for recycling spent nuclear fuel (SNF). The electrochemical process is a molten salt process for the reprocessing of spent nuclear fuel in an electrorefiner and generates spent salt that is contaminated with alkali, alkaline earths, and lanthanide fission products (FP) that must either be cleaned of fission products or eventually replaced with new salt to maintain separations efficiency. Currently, these spent salts are mixed with zeolite to form sodalite in a glass-bonded waste form. The focus of this study was to investigate alternate waste forms to immobilize spent salt. On a mole basis, the spent salt is dominated by alkali and Cl with minor amounts of alkaline earth and lanthanides. In the study reported here, we made an effort to explore glass systems that are more compatible with Cl and have not been previously considered for use as waste forms. In addition, alternate methods were explored with the hope of finding a way to produce a sodalite that is more accepting of as many FP present in the spent salt as possible. This study was done to investigate two different options: (1) alternate glass families that incorporate increased concentrations of Cl; and (2) alternate methods to produce a mineral waste form.

  13. Salt Lake County Residential Solar Financing Study | Department of Energy

    Energy Savers [EERE]

    Salt Lake City, Utah A White House Climate Action Champions Case Study INDEX Executive Summary.............................. 2 Climate Action Champion.................... 2 Project Spotlight.................................... 3 Challenges and lessons learned.......... 4 Resources & Contacts........................... 5 2 Executive Summary Salt Lake City has a robust set of ambitious climate goals that target reducing emissions while simultaneously prioritizing ways to become more resilient

  14. Treatment of plutonium process residues by molten salt oxidation

    SciTech Connect (OSTI)

    Stimmel, J.; Wishau, R.; Ramsey, K.B.; Montoya, A.; Brock, J.; Heslop, M.; Wernly, K.

    1999-04-01

    Molten Salt Oxidation (MSO) is a thermal process that can remove more than 99.999% of the organic matrix from combustible {sup 238}Pu material. Plutonium processing residues are injected into a molten salt bed with an excess of air. The salt (sodium carbonate) functions as a catalyst for the conversion of the organic material to carbon dioxide and water. Reactive species such as fluorine, chlorine, bromine, iodine, sulfur, phosphorous and arsenic in the organic waste react with the molten salt to form the corresponding neutralized salts, NaF, NaCl, NaBr, NaI, Na{sub 2}SO{sub 4}, Na{sub 3}PO{sub 4} and NaAsO{sub 2} or Na{sub 3}AsO4. Plutonium and other metals react with the molten salt and air to form metal salts or oxides. Saturated salt will be recycled and aqueous chemical separation will be used to recover the {sup 238}Pu. The Los Alamos National Laboratory system, which is currently in the conceptual design stage, will be scaled down from current systems for use inside a glovebox.

  15. Voluntary Protection Program Onsite Review, Parsons Corporation Salt Waste

    Office of Environmental Management (EM)

    Processing Facility Construction Project - October 2015 | Department of Energy Corporation Salt Waste Processing Facility Construction Project - October 2015 Voluntary Protection Program Onsite Review, Parsons Corporation Salt Waste Processing Facility Construction Project - October 2015 October 2015 Parsons SWPF Construction Project will continue participating in the Department of Energy Voluntary Protection Program and be elevated to a Star participant. This report summarizes the results

  16. Disposal of NORM waste in salt caverns

    SciTech Connect (OSTI)

    Veil, J.A.; Smith, K.P.; Tomasko, D.; Elcock, D.; Blunt, D.; Williams, G.P.

    1998-07-01

    Some types of oil and gas production and processing wastes contain naturally occurring radioactive materials (NORM). If NORM is present at concentrations above regulatory levels in oil field waste, the waste requires special disposal practices. The existing disposal options for wastes containing NORM are limited and costly. This paper evaluates the legality, technical feasibility, economics, and human health risk of disposing of NORM-contaminated oil field wastes in salt caverns. Cavern disposal of NORM waste is technically feasible and poses a very low human health risk. From a legal perspective, there are no fatal flaws that would prevent a state regulatory agency from approving cavern disposal of NORM. On the basis of the costs charged by caverns currently used for disposal of nonhazardous oil field waste (NOW), NORM waste disposal caverns could be cost competitive with existing NORM waste disposal methods when regulatory agencies approve the practice.

  17. Technical review of Molten Salt Oxidation

    SciTech Connect (OSTI)

    Not Available

    1993-12-01

    The process was reviewed for destruction of mixed low-level radioactive waste. Results: extensive development work and scaleup has been documented on coal gasification and hazardous waste which forms a strong experience base for this MSO process; it is clearly applicable to DOE wastes such as organic liquids and low-ash wastes. It also has potential for processing difficult-to-treat wastes such as nuclear grade graphite and TBP, and it may be suitable for other problem waste streams such as sodium metal. MSO operating systems may be constructed in relatively small units for small quantity generators. Public perceptions could be favorable if acceptable performance data are presented fairly; MSO will likely require compliance with regulations for incineration. Use of MSO for offgas treatment may be complicated by salt carryover. Figs, tabs, refs.

  18. The Role of Friction Stir Welding on the Microstructure and Mechanical Properties of AZ31B-H24 Mg alloy

    SciTech Connect (OSTI)

    Darzi, Kh.; Saeid, T. [Advanced Materials Research Center - Faculty of Materials Engineering, Sahand University of Technology - Tabriz (Iran, Islamic Republic of)

    2011-12-26

    In this study, an attempt was made to join AZ31B magnesium alloy by friction stir welding (FSW) process. A single tool with cylindrical screw threaded pin was used to investigate the effect of welding parameters on microstructure and mechanical properties of stir zone (SZ). Several welds were made at different rotational ({omega}) and traverse ({upsilon}) speeds, while the {omega}/{upsilon} ratios were kept constant. The optical and scanning electron microscopy were used to study the variation of microstructure across the welds. Moreover, micro-hardness and tensile tests were carried out to evaluate the mechanical properties of joints. It was found that {omega} plays more significant role on the resulted grain structure than {upsilon}, and at a constant {omega}/{upsilon} ratio, decreasing rotational speed decreased the size of grains, and hence, improved the hardness value and the tensile strength of the SZ.

  19. A new family of salts for lithium secondary batteries

    SciTech Connect (OSTI)

    Baril, D.; Beranger, S.; Ravet, N.; Michot, C.; Armand, M.

    2000-07-01

    A novel family of salts suitable for lithium battery application was synthesized and characterized. These salts have a large delocalized anion whose charge is spread over a single SO{sub 2} and a phenyl ring. Remarkable properties were obtained for the lithium N-(3-trifluoromethyl phenyl) trifluoromethanesulfonamide salt or LiTFPTS. The electrochemical stability window is around 4.0 V and its conductivity in solid poly(ethylene oxide) or PEO is close to the one of the lithium perchlorate salt. Calorimetric analysis also showed that LiTFPTS behaves as a plasticizer since it hinders, to a certain extent, the PEO crystallization when it is used in a solid polymer matrix. Above all, its synthesis is quite straightforward and leads to potentially inexpensive salts as the starting amines are made commercially on a large scale.

  20. Parametric study of natural circulation flow in molten salt fuel in molten salt reactor

    SciTech Connect (OSTI)

    Pauzi, Anas Muhamad; Cioncolini, Andrea; Iacovides, Hector

    2015-04-29

    The Molten Salt Reactor (MSR) is one of the most promising system proposed by Generation IV Forum (GIF) for future nuclear reactor systems. Advantages of the MSR are significantly larger compared to other reactor system, and is mainly achieved from its liquid nature of fuel and coolant. Further improvement to this system, which is a natural circulating molten fuel salt inside its tube in the reactor core is proposed, to achieve advantages of reducing and simplifying the MSR design proposed by GIF. Thermal hydraulic analysis on the proposed system was completed using a commercial computation fluid dynamics (CFD) software called FLUENT by ANSYS Inc. An understanding on theory behind this unique natural circulation flow inside the tube caused by fission heat generated in molten fuel salt and tube cooling was briefly introduced. Currently, no commercial CFD software could perfectly simulate natural circulation flow, hence, modeling this flow problem in FLUENT is introduced and analyzed to obtain best simulation results. Results obtained demonstrate the existence of periodical transient nature of flow problem, hence improvements in tube design is proposed based on the analysis on temperature and velocity profile. Results show that the proposed system could operate at up to 750MW core power, given that turbulence are enhanced throughout flow region, and precise molten fuel salt physical properties could be defined. At the request of the authors and the Proceedings Editor the name of the co-author Andrea Cioncolini was corrected from Andrea Coincolini. The same name correction was made in the Acknowledgement section on page 030004-10 and in reference number 4. The updated article was published on 11 May 2015.

  1. Ion aggregation in high salt solutions. III. Computational vibrational spectroscopy of HDO in aqueous salt solutions

    SciTech Connect (OSTI)

    Choi, Jun-Ho; Lim, Sohee; Chon, Bonghwan; Cho, Minhaeng; Kim, Heejae; Kim, Seongheun

    2015-05-28

    The vibrational frequency, frequency fluctuation dynamics, and transition dipole moment of the OD stretch mode of HDO molecule in aqueous solutions are strongly dependent on its local electrostatic environment and hydrogen-bond network structure. Therefore, the time-resolved vibrational spectroscopy the OD stretch mode has been particularly used to investigate specific ion effects on water structure. Despite prolonged efforts to understand the interplay of OD vibrational dynamics with local water hydrogen-bond network and ion aggregate structures in high salt solutions, still there exists a gap between theory and experiment due to a lack of quantitative model for accurately describing OD stretch frequency in high salt solutions. To fill this gap, we have performed numerical simulations of Raman scattering and IR absorption spectra of the OD stretch mode of HDO in highly concentrated NaCl and KSCN solutions and compared them with experimental results. Carrying out extensive quantum chemistry calculations on not only water clusters but also ion-water clusters, we first developed a distributed vibrational solvatochromic charge model for the OD stretch mode in aqueous salt solutions. Furthermore, the non-Condon effect on the vibrational transition dipole moment of the OD stretch mode was fully taken into consideration with the charge response kernel that is non-local polarizability density. From the fluctuating OD stretch mode frequencies and transition dipole vectors obtained from the molecular dynamics simulations, the OD stretch Raman scattering and IR absorption spectra of HDO in salt solutions could be calculated. The polarization effect on the transition dipole vector of the OD stretch mode is shown to be important and the asymmetric line shapes of the OD stretch Raman scattering and IR absorption spectra of HDO especially in highly concentrated NaCl and KSCN solutions are in quantitative agreement with experimental results. We anticipate that this computational approach will be of critical use in interpreting linear and nonlinear vibrational spectroscopies of HDO molecule that is considered as an excellent local probe for monitoring local electrostatic and hydrogen-bonding environment in not just salt but also other confined and crowded solutions.

  2. Soil Sampling At Salt Wells Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Salt Wells Area (Henkle, Et Al., 2005) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Soil Sampling At Salt Wells Area (Henkle, Et Al., 2005)...

  3. Slim Holes At Salt Wells Area (Combs, Et Al., 1999) | Open Energy...

    Open Energy Info (EERE)

    Salt Wells Area (Combs, Et Al., 1999) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Slim Holes At Salt Wells Area (Combs, Et Al., 1999)...

  4. Thermal Gradient Holes At Salt Wells Area (Bureau of Land Management...

    Open Energy Info (EERE)

    Salt Wells Area (Bureau of Land Management, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Thermal Gradient Holes At Salt Wells Area...

  5. Fluoroalkyl containing salts combined with fluorinated solvents for electrolytes

    SciTech Connect (OSTI)

    Tikhonov, Konstantin; Yip, Ka Ki; Lin, Tzu-Yuan; Erickson, Michael Jason

    2015-04-21

    Provided are electrochemical cells and electrolytes used to build such cells. An electrolyte may include a fluoroalkyl-substituted LiPF.sub.6 salt or a fluoroalkyl-substituted LiBF.sub.4 salt. In some embodiments, at least one fluorinated alkyl of the salt has a chain length of from 1 to 8 or, more specifically, between about 2 and 8. These fluorinated alkyl groups, in particular, relatively large fluorinated alkyl groups improve solubility of these salts in fluorinated solvents that are less flammable than, for example, conventional carbonate solvents. At the same time, the size of fluoroalkyl-substituted salts should be limited to ensure adequate concentration of the salt in an electrolyte and low viscosity of the electrolyte. In some embodiments, the concentration of a fluoroalkyl-substituted salt is at least about 0.5M. Examples of fluorinated solvents include various fluorinated esters, fluorinated ethers, and fluorinated carbonates, such a 1-methoxyheptafluoropropane, methyl nonafluorobutyl ether, ethyl nonafluorobutyl ether, 1,1,1,2,2,3,4,5,5,5-decafluoro-3-methoxy-4-(trifluoromethyl)-pentane, 3-ethoxy-1,1,1,2,3,4,4,5,5,6,6,6-dodecafluoro-2-trifluoromethyl-hexane, and 1,1,1,2,3,3-hexafluoro-4-(1,1,2,3,3,3-hexafluoropropoxy)-pentane.

  6. Fast Thorium Molten Salt Reactors Started with Plutonium

    SciTech Connect (OSTI)

    Merle-Lucotte, E.; Heuer, D.; Le Brun, C.; Brissot, R.; Liatard, E.; Meplan, O.; Nuttin, A.

    2006-07-01

    One of the pending questions concerning Molten Salt Reactors based on the {sup 232}Th/{sup 233}U fuel cycle is the supply of the fissile matter, and as a consequence the deployment possibilities of a fleet of Molten Salt Reactors, since {sup 233}U does not exist on earth and is not yet produced in the current operating reactors. A solution may consist in producing {sup 233}U in special devices containing Thorium, in Pressurized Water or Fast Neutrons Reactors. Two alternatives to produce {sup 233}U are examined here: directly in standard Molten Salt Reactors started with Plutonium as fissile matter and then operated in the Th/{sup 233}U cycle; or in dedicated Molten Salt Reactors started and fed with Plutonium as fissile matter and Thorium as fertile matter. The idea is to design a critical reactor able to burn the Plutonium and the minor actinides presently produced in PWRs, and consequently to convert this Plutonium into {sup 233}U. A particular reactor configuration is used, called 'unique channel' configuration in which there is no moderator in the core, leading to a quasi fast neutron spectrum, allowing Plutonium to be used as fissile matter. The conversion capacities of such Molten Salt Reactors are excellent. For Molten Salt Reactors only started with Plutonium, the assets of the Thorium fuel cycle turn out to be quickly recovered and the reactor's characteristics turn out to be equivalent to Molten Salt Reactors operated with {sup 233}U only. Using a combination of Molten Salt Reactors started or operated with Plutonium and of Molten Salt Reactors started with {sup 233}U, the deployment capabilities of these reactors fully satisfy the condition of sustainability. (authors)

  7. Electrolyte materials containing highly dissociated metal ion salts

    DOE Patents [OSTI]

    Lee, Hung-Sui; Geng, Lin; Skotheim, Terje A.

    1996-07-23

    The present invention relates to metal ion salts which can be used in electrolytes for producing electrochemical devices, including both primary and secondary batteries, photoelectrochemical cells and electrochromic displays. The salts have a low energy of dissociation and may be dissolved in a suitable polymer to produce a polymer solid electrolyte or in a polar aprotic liquid solvent to produce a liquid electrolyte. The anion of the salts may be covalently attached to polymer backbones to produce polymer solid electrolytes with exclusive cation conductivity.

  8. Electrolyte materials containing highly dissociated metal ion salts

    DOE Patents [OSTI]

    Lee, H.S.; Geng, L.; Skotheim, T.A.

    1996-07-23

    The present invention relates to metal ion salts which can be used in electrolytes for producing electrochemical devices, including both primary and secondary batteries, photoelectrochemical cells and electrochromic displays. The salts have a low energy of dissociation and may be dissolved in a suitable polymer to produce a polymer solid electrolyte or in a polar aprotic liquid solvent to produce a liquid electrolyte. The anion of the salts may be covalently attached to polymer backbones to produce polymer solid electrolytes with exclusive cation conductivity. 2 figs.

  9. Sol-gel processing with inorganic metal salt precursors

    DOE Patents [OSTI]

    Hu, Zhong-Cheng

    2004-10-19

    Methods for sol-gel processing that generally involve mixing together an inorganic metal salt, water, and a water miscible alcohol or other organic solvent, at room temperature with a macromolecular dispersant material, such as hydroxypropyl cellulose (HPC) added. The resulting homogenous solution is incubated at a desired temperature and time to result in a desired product. The methods enable production of high quality sols and gels at lower temperatures than standard methods. The methods enable production of nanosize sols from inorganic metal salts. The methods offer sol-gel processing from inorganic metal salts.

  10. Gradient zone boundary control in salt gradient solar ponds

    DOE Patents [OSTI]

    Hull, John R.

    1984-01-01

    A method and apparatus for suppressing zone boundary migration in a salt gradient solar pond includes extending perforated membranes across the pond at the boundaries, between the convective and non-convective zones, the perforations being small enough in size to prevent individual turbulence disturbances from penetrating the hole, but being large enough to allow easy molecular diffusion of salt thereby preventing the formation of convective zones in the gradient layer. The total area of the perforations is a sizable fraction of the membrane area to allow sufficient salt diffusion while preventing turbulent entrainment into the gradient zone.

  11. Experimental Investigation of Two-Phase Flow in Rock Salt

    SciTech Connect (OSTI)

    Malama, Bwalya; Howard, Clifford L.

    2014-07-01

    This Test Plan describes procedures for conducting laboratory scale flow tests on intact, damaged, crushed, and consolidated crushed salt to measure the capillary pressure and relative permeability functions. The primary focus of the tests will be on samples of bedded geologic salt from the WIPP underground. However, the tests described herein are directly applicable to domal salt. Samples being tested will be confined by a range of triaxial stress states ranging from atmospheric pressure up to those approximating lithostatic. Initially these tests will be conducted at room temperature, but testing procedures and equipment will be evaluated to determine adaptability to conducting similar tests under elevated temperatures.

  12. Engineering Evaluation of Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiement for the Oak Ridge National Laboratory

    SciTech Connect (OSTI)

    Carlberg, Jon A.; Roberts, Kenneth T.; Kollie, Thomas G.; Little, Leslie E.; Brady, Sherman D.

    2009-09-30

    This evaluation was performed by Pro2Serve in accordance with the Technical Specification for an Engineering Evaluation of the Proposed Alternative Salt Transfer Method for the Molten Salt Reactor Experiment at the Oak Ridge National Laboratory (BJC 2009b). The evaluators reviewed the Engineering Evaluation Work Plan for Molten Salt Reactor Experiment Residual Salt Removal, Oak Ridge National Laboratory, Oak Ridge, Tennessee (DOE 2008). The Work Plan (DOE 2008) involves installing a salt transfer probe and new drain line into the Fuel Drain Tanks and Fuel Flush Tank and connecting them to the new salt transfer line at the drain tank cell shield. The probe is to be inserted through the tank ball valve and the molten salt to the bottom of the tank. The tank would then be pressurized through the Reactive Gas Removal System to force the salt into the salt canisters. The Evaluation Team reviewed the work plan, interviewed site personnel, reviewed numerous documents on the Molten Salt Reactor (Sects. 7 and 8), and inspected the probes planned to be used for the transfer. Based on several concerns identified during this review, the team recommends not proceeding with the salt transfer via the proposed alternate salt transfer method. The major concerns identified during this evaluation are: (1) Structural integrity of the tanks - The main concern is with the corrosion that occurred during the fluorination phase of the uranium removal process. This may also apply to the salt transfer line for the Fuel Flush Tank. Corrosion Associated with Fluorination in the Oak Ridge National Laboratory Fluoride Volatility Process (Litman 1961) shows that this problem is significant. (2) Continued generation of Fluorine - Although the generation of Fluorine will be at a lower rate than experienced before the uranium removal, it will continue to be generated. This needs to be taken into consideration regardless of what actions are taken with the salt. (3) More than one phase of material - There are likely multiple phases of material in the salt (metal or compound), either suspended through the salt matrix, layered in the bottom of the tank, or both. These phases may contribute to plugging during any planned transfer. There is not enough data to know for sure. (4) Probe heat trace - The alternate transfer method does not include heat tracing of the bottom of the probe. There is a concern that this may cool the salt and other phases of materials present enough to block the flow of salt. (5) Stress-corrosion cracking - Additionally, there is a concern regarding moisture that may have been introduced into the tanks. Due to time constraints, this concern was not validated. However, if moisture was introduced into the tanks and not removed during heating the tanks before HF and F2 sparging, there would be an additional concern regarding the potential for stress-corrosion cracking of the tank walls.

  13. Category:Salt Lake City, UT | Open Energy Information

    Open Energy Info (EERE)

    UT Jump to: navigation, search Go Back to PV Economics By Location Media in category "Salt Lake City, UT" The following 16 files are in this category, out of 16 total....

  14. Surface Indicators of Geothermal Activity at Salt Wells, Nevada...

    Open Energy Info (EERE)

    of geothermal fluids. An example is provided by the Salt Wells geothermal system in Churchill County, Nevada, USA, where surface features define a 9-km-long area that matches the...

  15. BLM Approves Salt Wells Geothermal Plant in Churchill County...

    Open Energy Info (EERE)

    Plant in Churchill County Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: BLM Approves Salt Wells Geothermal Plant in Churchill County Abstract...

  16. Project Profile: Deep Eutectic Salt Formulations Suitable as...

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

    J.W. Raade and D. Padowitz, "Development of Molten Salt Heat Transfer Fluid with Low Melting Point and High Thermal Stability," Journal of Solar Energy Engineering, Vol. 133, No. ...

  17. Climate Action Champions: Salt Lake City, UT | Department of...

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

    decreasing total building energy use in the City by 5 percent, and generating 10 megawatts of solar energy in the community by 2015. In addition, Salt Lake City aims to reduce ...

  18. Prediction of Heat Capacities of Solid Inorganic Salts from Group

    Office of Scientific and Technical Information (OSTI)

    from Group Contributions. )&-SUB -- 7 5- g 7 A. T. M. Golam Mostafa, James M. Eakman* ... a group contribution method for predicting A H ? and A G F of solid inorganic salts. ...

  19. Project Profile: Modular and Scalable Baseload Molten Salt Plant...

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

    J. E. Pacheco, C. Moursund, D. Rogers; D. Wasyluk. "Conceptual Design of a 100 MWe Modular Molten Salt Power Tower Plant" in Proceedings of SolarPACES 2011, Granada Spain, ...

  20. Salt Wells Geothermal Exploratory Drilling Program EA(DOI-BLM...

    Open Energy Info (EERE)

    Exploratory Drilling Program EA (DOI-BLM-NV-C010-2009-0006-EA) Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Salt Wells Geothermal Exploratory...

  1. Direct esterification of ammonium salts of carboxylic acids

    DOE Patents [OSTI]

    Halpern, Yuval

    2003-06-24

    A non-catalytic process for producing esters, the process comprising reacting an ammonium salt of a carboxylic acid with an alcohol and removing ammonia from the reaction mixture. Selectivities for the desired ester product can exceed 95 percent.

  2. Oxidation of aqueous pollutants using ultrasound: Salt-induced enhancement

    SciTech Connect (OSTI)

    Seymour, J.D.; Gupta, R.B.

    1997-09-01

    Ultrasound can be used to oxidize aqueous pollutants; however, due to economic reasons, higher oxidation/destruction rates are needed. This study reports enhancements of reaction rates by the addition of sodium chloride salt. Using 20 kHz ultrasound, large salt-induced enhancements are observed--6-fold for chlorobenzene, 7-fold for p-ethylphenol, and 3-fold for phenol oxidation. The reaction rate enhancements are proportional to the diethyl ether--water partitioning coefficient of the pollutants. It appears that the majority of oxidation reactions occur in the bubble-bulk interface region. The addition of salt increases the ionic strength of the aqueous phase which drives the organic pollutants toward the bubble-bulk interface. A first order reaction rate equation is proposed which can represent the observed enhancement with a good accuracy. A new sonochemical-waste-oxidation process is proposed utilizing the salt-induced enhancement.

  3. Apparatus and method for making metal chloride salt product

    DOE Patents [OSTI]

    Miller, William E. (Naperville, IL); Tomczuk, Zygmunt (Homer Glen, IL); Richmann, Michael K. (Carlsbad, NM)

    2007-05-15

    A method of producing metal chlorides is disclosed in which chlorine gas is introduced into liquid Cd. CdCl.sub.2 salt is floating on the liquid Cd and as more liquid CdCl.sub.2 is formed it separates from the liquid Cd metal and dissolves in the salt. The salt with the CdCl.sub.2 dissolved therein contacts a metal which reacts with CdCl.sub.2 to form a metal chloride, forming a mixture of metal chloride and CdCl.sub.2. After separation of bulk Cd from the salt, by gravitational means, the metal chloride is obtained by distillation which removes CdCl.sub.2 and any Cd dissolved in the metal chloride.

  4. Polyimide amic acid salts and polyimide membranes formed therefrom

    DOE Patents [OSTI]

    Ding, Yong; Bikson, Benjamin; Nelson, Joyce Katz; Macheras, James Timothy

    2004-04-06

    The invention relates to preparation and uses of novel polymeric materials, polyimide amic acid salts (PIAAS). The use of these materials for the fabrication of fluid separation membranes is further disclosed.

  5. DOE - Office of Legacy Management -- Salt Lake City Vitro Chemical...

    Office of Legacy Management (LM)

    Vitro Chemical - UT 0-04 FUSRAP Considered Sites Site: Salt Lake City Vitro Chemical (UT.0-04 ) Designated Name: Alternate Name: Location: Evaluation Year: Site Operations: Site ...

  6. Transfer Lines to Connect Liquid Waste Facilities and Salt Waste...

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

    ... of tank waste at SRS. SWPF will separate the salt waste into a low-volume, high radioactivity fraction for vitrification in the Defense Waste Processing Facility (DWPF) and ...

  7. Salt River Electric Coop Corp | Open Energy Information

    Open Energy Info (EERE)

    River Electric Coop Corp Jump to: navigation, search Name: Salt River Electric Coop Corp Place: Kentucky References: EIA Form EIA-861 Final Data File for 2010 - File1a1 EIA Form...

  8. Expected brine movement at potential nuclear waste repository salt sites

    SciTech Connect (OSTI)

    McCauley, V.S.; Raines, G.E.

    1987-08-01

    The BRINEMIG brine migration code predicts rates and quantities of brine migration to a waste package emplaced in a high-level nuclear waste repository in salt. The BRINEMIG code is an explicit time-marching finite-difference code that solves a mass balance equation and uses the Jenks equation to predict velocities of brine migration. Predictions were made for the seven potentially acceptable salt sites under consideration as locations for the first US high-level nuclear waste repository. Predicted total quantities of accumulated brine were on the order of 1 m/sup 3/ brine per waste package or less. Less brine accumulation is expected at domal salt sites because of the lower initial moisture contents relative to bedded salt sites. Less total accumulation of brine is predicted for spent fuel than for commercial high-level waste because of the lower temperatures generated by spent fuel. 11 refs., 36 figs., 29 tabs.

  9. Salt Wells, Eight Mile Flat | Open Energy Information

    Open Energy Info (EERE)

    Eight Mile Flat Jump to: navigation, search OpenEI Reference LibraryAdd to library Web Site: Salt Wells, Eight Mile Flat Abstract Abstract unavailable. Author Nevada Bureau...

  10. Texas-Louisiana- Mississippi Salt Basin Greater Green River Basin

    Gasoline and Diesel Fuel Update (EIA)

    Texas-Louisiana- Mississippi Salt Basin Greater Green River Basin W. Gulf Coast Basin ... Major Tight Gas Plays, Lower 48 States 0 200 400 100 300 Miles Source: Energy ...

  11. Project Profile: Advanced Nitrate Salt Central Receiver Power Plant

    Broader source: Energy.gov [DOE]

    Abengoa, under the Baseload CSP FOA, will demonstrate a 100-megawatt electrical (MWe) central receiver plant using nitrate salt as the receiver coolant, thermal storage medium, and heat transport fluid in the steam generator.

  12. Molten salt electrolyte battery cell with overcharge tolerance

    DOE Patents [OSTI]

    Kaun, Thomas D.; Nelson, Paul A.

    1989-01-01

    A molten salt electrolyte battery having an increased overcharge tolerance employs a negative electrode with two lithium alloy phases of different electrochemical potential, one of which allows self-discharge rates which permits battery cell equalization.

  13. Aksaray And Ecemis Faults - Diapiric Salt Relationships- Relevance...

    Open Energy Info (EERE)

    To The Hydrocarbon Exploration In The Tuz Golu (Salt Lake) Basin, Central Anatolia, Turkey Jump to: navigation, search OpenEI Reference LibraryAdd to library Journal Article:...

  14. Molten Salt Heat Transfer Fluid (HTF) - Energy Innovation Portal

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

    Find More Like This Return to Search Molten Salt Heat Transfer Fluid (HTF) Sandia National ... Sandia has developed a heat transfer fluid (HTF) for use at elevated temperatures that has ...

  15. Current and proposed regulations for salt water disposal wells

    SciTech Connect (OSTI)

    Moody, T.

    1994-09-01

    In recent years, all aspects of hydrocarbon exploration and production (E & P) activities have drawn closer scrutiny in terms of existing and potential impairment of the environment. In addition to drilling, production, and transportation activities, the USEPA has focused on the nature of E & P generated wastes, and the subsequent management of both hazardous and nonhazardous E & P wastes. Approximately 98% of all of the volume of wastes generated by E & P activities is salt water associated with the recovery of hydrocarbons. By far the majority of this waste is disposed of in class II salt water disposal wells. Due to the tremendous volume of salt water generated, the USEPA continues to reevaluate the federal class II salt water injection well program, offering comments, revising its interpretation of existing regulations, and promulgating new regulations. The purpose of the presentation will be to provide a review of existing class II federal regulations, and to provide an overview of potential or newly promulgated regulations.

  16. Liquid Salt Heat Exchanger Technology for VHTR Based Applications

    SciTech Connect (OSTI)

    Anderson, Mark; Sridhara, Kumar; Allen, Todd; Peterson, Per

    2012-10-11

    The objective of this research is to evaluate performance of liquid salt fluids for use as a heat carrier for transferring high-temperature process heat from the very high-temperature reactor (VHTR) to chemical process plants. Currently, helium is being considered as the heat transfer fluid; however, the tube size requirements and the power associated with pumping helium may not be economical. Recent work on liquid salts has shown tremendous potential to transport high-temperature heat efficiently at low pressures over long distances. This project has two broad objectives: To investigate the compatibility of Incoloy 617 and coated and uncoated SiC ceramic composite with MgCl2-KCl molten salt to determine component lifetimes and aid in the design of heat exchangers and piping; and, To conduct the necessary research on the development of metallic and ceramic heat exchangers, which are needed for both the helium-to-salt side and salt-to-process side, with the goal of making these heat exchangers technologically viable. The research will consist of three separate tasks. The first task deals with material compatibility issues with liquid salt and the development of techniques for on-line measurement of corrosion products, which can be used to measure material loss in heat exchangers. Researchers will examine static corrosion of candidate materials in specific high-temperature heat transfer salt systems and develop an in situ electrochemical probe to measure metallic species concentrations dissolved in the liquid salt. The second task deals with the design of both the intermediate and process side heat exchanger systems. Researchers will optimize heat exchanger design and study issues related to corrosion, fabrication, and thermal stresses using commercial and in-house codes. The third task focuses integral testing of flowing liquid salts in a heat transfer/materials loop to determine potential issues of using the salts and to capture realistic behavior of the salts in a small scale prototype system. This includes investigations of plugging issues, heat transfer, pressure drop, and the corrosion and erosion of materials in the flowing system.

  17. Liquid Fuel Molten Salt Reactors For Thorium Utilization (Conference) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Liquid Fuel Molten Salt Reactors For Thorium Utilization Citation Details In-Document Search Title: Liquid Fuel Molten Salt Reactors For Thorium Utilization Authors: Gehin, Jess C [1] + Show Author Affiliations ORNL Publication Date: 2014-01-01 OSTI Identifier: 1185589 DOE Contract Number: AC05-00OR22725 Resource Type: Conference Resource Relation: Conference: 2014 ANS Winter Meeting and Nuclear Technology Expo, Anaheim, CA, USA, 20141109, 20141113 Research Org: Oak Ridge

  18. Molten salt heat transfer fluids and thermal storage technology.

    Office of Scientific and Technical Information (OSTI)

    (Conference) | SciTech Connect Molten salt heat transfer fluids and thermal storage technology. Citation Details In-Document Search Title: Molten salt heat transfer fluids and thermal storage technology. No abstract prepared. Authors: Glatzmaier, Greg [1] ; Siegel, Nathan Phillip + Show Author Affiliations (NREL) Publication Date: 2010-06-01 OSTI Identifier: 1020492 Report Number(s): SAND2010-3826C TRN: US201116%%508 DOE Contract Number: AC04-94AL85000 Resource Type: Conference Resource

  19. Salt Waste Processing Facility, Construction Turnover to Testing and

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

    Commissioning Oversight | Department of Energy Construction Turnover to Testing and Commissioning Oversight Salt Waste Processing Facility, Construction Turnover to Testing and Commissioning Oversight This procedure establishes an oversight process for the Salt Waste Processing Facility Project Office (SWPFPO) Integrated Project Team (IPT) personnel assigned to perform oversight of system turnover from Construction to Commissioning and Testing. September 2015 PDF icon Procedure Key Resources

  20. Mechanochemical Preparation of Phosphonium Salts and Phosphorus Ylides -

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

    Energy Innovation Portal Industrial Technologies Industrial Technologies Find More Like This Return to Search Mechanochemical Preparation of Phosphonium Salts and Phosphorus Ylides Ames Laboratory Contact AMES About This Technology Technology Marketing Summary Researchers at Iowa State University and Ames Laboratory have developed a unique, solvent-free mechanochemical preparation method to prepare phosphonium salts and phosphorous ylides. The phosphorous ylides are then utilized in carrying

  1. Pyrochemical investigations into recovering plutonium from americium extraction salt residues

    SciTech Connect (OSTI)

    Fife, K.W.; West, M.H.

    1987-05-01

    Progress into developing a pyrochemical technique for separating and recovering plutonium from spent americium extraction waste salts has concentrated on selective chemical reduction with lanthanum metal and calcium metal and on the solvent extraction of americium with calcium metal. Both techniques are effective for recovering plutonium from the waste salt, although neither appears suitable as a separation technique for recycling a plutonium stream back to mainline purification processes. 17 refs., 13 figs., 2 tabs.

  2. CAVERN ROOF STABILITY FOR NATURAL GAS STORAGE IN BEDDED SALT

    SciTech Connect (OSTI)

    DeVries, Kerry L; Mellegard, Kirby D; Callahan, Gary D; Goodman, William M

    2005-06-01

    This report documents research performed to develop a new stress-based criterion for predicting the onset of damage in salt formations surrounding natural gas storage caverns. Laboratory tests were conducted to investigate the effects of shear stress, mean stress, pore pressure, temperature, and Lode angle on the strength and creep characteristics of salt. The laboratory test data were used in the development of the new criterion. The laboratory results indicate that the strength of salt strongly depends on the mean stress and Lode angle. The strength of the salt does not appear to be sensitive to temperature. Pore pressure effects were not readily apparent until a significant level of damage was induced and the permeability was increased to allow penetration of the liquid permeant. Utilizing the new criterion, numerical simulations were used to estimate the minimum allowable gas pressure for hypothetical storage caverns located in a bedded salt formation. The simulations performed illustrate the influence that cavern roof span, depth, roof salt thickness, shale thickness, and shale stiffness have on the allowable operating pressure range. Interestingly, comparison of predictions using the new criterion with that of a commonly used criterion indicate that lower minimum gas pressures may be allowed for caverns at shallow depths. However, as cavern depth is increased, less conservative estimates for minimum gas pressure were determined by the new criterion.

  3. Independent Oversight Review, Savannah River Site Salt Waste Processing Facility- August 2013

    Broader source: Energy.gov [DOE]

    Review of the Savannah River Site Salt Waste Processing Facility Safety Basis and Design Development.

  4. EIS-0099: Remedial Actions at the Former Vitro Chemical Company Site, South Salt Lake, Salt Lake County, Utah

    Broader source: Energy.gov [DOE]

    The U.S. Department of Energy developed this statement to evaluate the environmental impacts of various scenarios associated with the cleanup of those residues remaining at the abandoned uranium mill tailings site located in South Salt Lake, Utah.

  5. LIFE Materails: Molten-Salt Fuels Volume 8

    SciTech Connect (OSTI)

    Moir, R; Brown, N; Caro, A; Farmer, J; Halsey, W; Kaufman, L; Kramer, K; Latkowski, J; Powers, J; Shaw, H; Turchi, P

    2008-12-11

    The goals of the Laser Inertial Fusion Fission Energy (LIFE) is to use fusion neutrons to fission materials with no enrichment and minimum processing and have greatly reduced wastes that are not of interest to making weapons. Fusion yields expected to be achieved in NIF a few times per day are called for with a high reliable shot rate of about 15 per second. We have found that the version of LIFE using TRISO fuel discussed in other volumes of this series can be modified by replacing the molten-flibe-cooled TRISO fuel zone with a molten salt in which the same actinides present in the TRISO particles are dissolved in the molten salt. Molten salts have the advantage that they are not subject to radiation damage, and hence overcome the radiation damage effects that may limit the lifetime of solid fuels such as TRISO-containing pebbles. This molten salt is pumped through the LIFE blanket, out to a heat exchanger and back into the blanket. To mitigate corrosion, steel structures in contact with the molten salt would be plated with tungsten or nickel. The salt will be processed during operation to remove certain fission products (volatile and noble and semi-noble fission products), impurities and corrosion products. In this way neutron absorbers (fission products) are removed and neutronics performance of the molten salt is somewhat better than that of the TRISO fuel case owing to the reduced parasitic absorption. In addition, the production of Pu and rare-earth elements (REE) causes these elements to build up in the salt, and leads to a requirement for a process to remove the REE during operation to insure that the solubility of a mixed (Pu,REE)F3 solid solution is not exceeded anywhere in the molten salt system. Removal of the REE will further enhance the neutronics performance. With molten salt fuels, the plant would need to be safeguarded because materials of interest for weapons are produced and could potentially be removed.

  6. A coarse-grained model with implicit salt for RNAs: Predicting 3D structure, stability and salt effect

    SciTech Connect (OSTI)

    Shi, Ya-Zhou; Wang, Feng-Hua; Wu, Yuan-Yan; Tan, Zhi-Jie

    2014-09-14

    To bridge the gap between the sequences and 3-dimensional (3D) structures of RNAs, some computational models have been proposed for predicting RNA 3D structures. However, the existed models seldom consider the conditions departing from the room/body temperature and high salt (1M NaCl), and thus generally hardly predict the thermodynamics and salt effect. In this study, we propose a coarse-grained model with implicit salt for RNAs to predict 3D structures, stability, and salt effect. Combined with Monte Carlo simulated annealing algorithm and a coarse-grained force field, the model folds 46 tested RNAs (?45 nt) including pseudoknots into their native-like structures from their sequences, with an overall mean RMSD of 3.5 and an overall minimum RMSD of 1.9 from the experimental structures. For 30 RNA hairpins, the present model also gives the reliable predictions for the stability and salt effect with the mean deviation ? 1.0 C of melting temperatures, as compared with the extensive experimental data. In addition, the model could provide the ensemble of possible 3D structures for a short RNA at a given temperature/salt condition.

  7. Assessment of the Use of Nitrogen Trifluoride for Purifying Coolant and Heat Transfer Salts in the Fluoride Salt-Cooled High-Temperature Reactor

    SciTech Connect (OSTI)

    Scheele, Randall D.; Casella, Andrew M.

    2010-09-28

    This report provides an assessment of the use of nitrogen trifluoride for removing oxide and water-caused contaminants in the fluoride salts that will be used as coolants in a molten salt cooled reactor.

  8. Alternative Fuels Data Center: Salt Lake City Fuels Vehicles With Natural

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

    Gas Salt Lake City Fuels Vehicles With Natural Gas to someone by E-mail Share Alternative Fuels Data Center: Salt Lake City Fuels Vehicles With Natural Gas on Facebook Tweet about Alternative Fuels Data Center: Salt Lake City Fuels Vehicles With Natural Gas on Twitter Bookmark Alternative Fuels Data Center: Salt Lake City Fuels Vehicles With Natural Gas on Google Bookmark Alternative Fuels Data Center: Salt Lake City Fuels Vehicles With Natural Gas on Delicious Rank Alternative Fuels Data

  9. In-Drift Precipitates/Salts Model

    SciTech Connect (OSTI)

    P. Mariner

    2003-10-21

    As directed by ''Technical Work Plan For: Engineered Barrier System Department Modeling and Testing FY03 Work Activities'' (BSC 2003 [165601]), the In-Drift Precipitates/Salts (IDPS) model is developed and refined to predict the aqueous geochemical effects of evaporation in the proposed repository. The purpose of this work is to provide a model for describing and predicting the postclosure effects of evaporation and deliquescence on the chemical composition of water within the proposed Engineered Barrier System (EBS). Application of this model is to be documented elsewhere for the Total System Performance Assessment License Application (TSPA-LA). The principal application of this model is to be documented in REV 02 of ''Engineered Barrier System: Physical and Chemical Environment Model'' (BSC 2003 [165601]). The scope of this document is to develop, describe, and validate the IDPS model. This model is a quasi-equilibrium model. All reactions proceed to equilibrium except for several suppressed minerals in the thermodynamic database not expected to form under the proposed repository conditions within the modeling timeframe. In this revision, upgrades to the EQ3/6 code (Version 8.0) and Pitzer thermodynamic database improve the applicable range of the model. These new additions allow equilibrium and reaction-path modeling of evaporation to highly concentrated brines for potential water compositions of the system Na-K-H-Mg-Ca-Al-Cl-F-NO{sub 3}-SO{sub 4}-Br-CO{sub 3}-SiO{sub 2}-CO{sub 2}-O{sub 2}-H{sub 2}O at temperatures in the range of 0 C to 125 C, pressures in the atmospheric range, and relative humidity in the range of 0 to 100 percent. This system applies to oxidizing conditions only, and therefore limits the model to applications involving oxidizing conditions. A number of thermodynamic parameters in the Pitzer database have values that have not been determined or verified for the entire temperature range. In these cases, the known values are used to approximate the values for the rest of the temperature range. Although such treatment contributes to uncertainty in model outputs, the model validation test cases indicate that the model, with its associated uncertainty, is valid for its intended use. The intended use of this model is to estimate and tabulate, within an appropriate level of confidence, the effects of evaporation, deliquescence, and potential environmental conditions on the pH, ionic strength, and chemical compositions of water and minerals on the drip shield or other location within the drift during the postclosure period.

  10. Molten Salts for High Temperature Reactors: University of Wisconsin Molten Salt Corrosion and Flow Loop Experiments -- Issues Identified and Path Forward

    SciTech Connect (OSTI)

    Piyush Sabharwall; Matt Ebner; Manohar Sohal; Phil Sharpe; Thermal Hydraulics Group

    2010-03-01

    Considerable amount of work is going on regarding the development of high temperature liquid salts technology to meet future process needs of Next Generation Nuclear Plant. This report identifies the important characteristics and concerns of high temperature molten salts (with lesson learned at University of Wisconsin-Madison, Molten Salt Program) and provides some possible recommendation for future work

  11. Vitrification of IFR and MSBR halide salt reprocessing wastes

    SciTech Connect (OSTI)

    Siemer, D.D.

    2013-07-01

    Both of the genuinely sustainable (breeder) nuclear fuel cycles (IFR - Integral Fast Reactor - and MSBR - Molten Salt Breeder Reactor -) studied by the USA's national laboratories would generate high level reprocessing waste (HLRW) streams consisting of a relatively small amount ( about 4 mole %) of fission product halide (chloride or fluoride) salts in a matrix comprised primarily (about 95 mole %) of non radioactive alkali metal halide salts. Because leach resistant glasses cannot accommodate much of any of the halides, most of the treatment scenarios previously envisioned for such HLRW have assumed a monolithic waste form comprised of a synthetic analog of an insoluble crystalline halide mineral. In practice, this translates to making a 'substituted' sodalite ('Ceramic Waste Form') of the IFR's chloride salt-based wastes and fluoroapatite of the MSBR's fluoride salt-based wastes. This paper discusses my experimental studies of an alternative waste management scenario for both fuel cycles that would separate/recycle the waste's halide and immobilize everything else in iron phosphate (Fe-P) glass. It will describe both how the work was done and what its results indicate about how a treatment process for both of those wastes should be implemented (fluoride and chloride behave differently). In either case, this scenario's primary advantages include much higher waste loadings, much lower overall cost, and the generation of a product (glass) that is more consistent with current waste management practices. (author)

  12. CRITICALITY SAFETY OF PROCESSING SALT SOLUTION AT SRS

    SciTech Connect (OSTI)

    Stephens, K; Davoud Eghbali, D; Michelle Abney, M

    2008-01-15

    High level radioactive liquid waste generated as a result of the production of nuclear material for the United States defense program at the Savannah River Site has been stored as 36 million gallons in underground tanks. About ten percent of the waste volume is sludge, composed of insoluble metal hydroxides primarily hydroxides of Mn, Fe, Al, Hg, and most radionuclides including fission products. The remaining ninety percent of the waste volume is saltcake, composed of primarily sodium (nitrites, nitrates, and aluminates) and hydroxides. Saltcakes account for 30% of the radioactivity while the sludge accounts for 70% of the radioactivity. A pilot plant salt disposition processing system has been designed at the Savannah River Site for interim processing of salt solution and is composed of two facilities: the Actinide Removal Process Facility (ARPF) and the Modular Caustic Side Solvent Extraction Unit (MCU). Data from the pilot plant salt processing system will be used for future processing salt at a much higher rate in a new salt processing facility. Saltcake contains significant amounts of actinides, and other long-lived radioactive nuclides such as strontium and cesium that must be extracted prior to disposal as low level waste. The extracted radioactive nuclides will be mixed with the sludge from waste tanks and vitrified in another facility. Because of the presence of highly enriched uranium in the saltcake, there is a criticality concern associated with concentration and/or accumulation of fissionable material in the ARP and MCU.

  13. Fuel salt and container material studies for MOSART transforming system

    SciTech Connect (OSTI)

    Ignatiev, V.; Feynberg, O.; Merzlyakov, A.; Surenkov, A.; Zagnitko, A.; Afonichkin, V.; Bovet, A.; Khokhlov, V.; Subbotin, V.; Gordeev, M.; Panov, A.; Toropov, A.

    2013-07-01

    A study is under progress to examine the feasibility of single stream Molten Salt Actinide Recycling and Transmuting system without and with Th support (MOSART) fuelled with different compositions of actinide tri-fluorides (AnF{sub 3}) from used LWR fuel. New fast-spectrum design options with homogeneous core and fuel salts with high enough solubility for AnF{sub 3} are being examined because of new goals. The flexibility of single fluid MOSART concept with Th support is underlined, particularly, possibility of its operation in self-sustainable mode (Conversion Ratio: CR=1) using different loadings and make up. The paper summarizes the most current status of fuel salt and container material data for the MOSART concept received within ISTC-3749 and ROSATOM-MARS projects. Key physical and chemical properties of various fluoride fuel salts are reported. The issues like salt purification, the electroreduction of U(IV) to U(III) in LiF-ThF{sub 4} and the electroreduction of Yb(III) to Yb(II) in LiF-NaF are detailed.

  14. Method for making a uranium chloride salt product

    DOE Patents [OSTI]

    Miller, William E.; Tomczuk, Zygmunt

    2004-10-05

    The subject apparatus provides a means to produce UCl.sub.3 in large quantities without incurring corrosion of the containment vessel or associated apparatus. Gaseous Cl is injected into a lower layer of Cd where CdCl.sub.2 is formed. Due to is lower density, the CdCl.sub.2 rises through the Cd layer into a layer of molten LiCl--KCL salt where a rotatable basket containing uranium ingots is suspended. The CdCl.sub.2 reacts with the uranium to form UCl.sub.3 and Cd. Due to density differences, the Cd sinks down to the liquid Cd layer and is reused. The UCl.sub.3 combines with the molten salt. During production the temperature is maintained at about 600.degree. C. while after the uranium has been depleted the salt temperature is lowered, the molten salt is pressure siphoned from the vessel, and the salt product LiCl--KCl-30 mol % UCl.sub.3 is solidified.

  15. Effect of water in salt repositories. Final report

    SciTech Connect (OSTI)

    Baes, C.F. Jr.; Gilpatrick, L.O.; Kitts, F.G.; Bronstein, H.R.; Shor, A.J.

    1983-09-01

    Additional results confirm that during most of the consolidation of polycrystalline salt in brine, the previously proposed rate expression applies. The final consolidation, however, proceeds at a lower rate than predicted. The presence of clay hastens the consolidation process but does not greatly affect the previously observed relationship between permeability and void fraction. Studies of the migration of brine within polycrystalline salt specimens under stress indicate that the principal effect is the exclusion of brine as a result of consolidation, a process that evidently can proceed to completion. No clear effect of a temperature gradient could be identified. A previously reported linear increase with time of the reciprocal permeability of salt-crystal interfaces to brine was confirmed, though the rate of increase appears more nearly proportional to the product of sigma ..delta..P rather than sigma ..delta..P/sup 2/ (sigma is the uniaxial stress normal to the interface and ..delta..P is the hydraulic pressure drop). The new results suggest that a limiting permeability may be reached. A model for the permeability of salt-crystal interfaces to brine is developed that is reasonably consistent with the present results and may be used to predict the permeability of bedded salt. More measurements are needed, however, to choose between two limiting forms of the model.

  16. In-Drift Precipitates/Salts Model

    SciTech Connect (OSTI)

    P. Mariner

    2004-11-09

    This report documents the development and validation of the in-drift precipitates/salts (IDPS) model. The IDPS model is a geochemical model designed to predict the postclosure effects of evaporation and deliquescence on the chemical composition of water within the Engineered Barrier System (EBS) in support of the Total System Performance Assessment for the License Application (TSPA-LA). Application of the model in support of TSPA-LA is documented in ''Engineered Barrier System: Physical and Chemical Environment Model'' (BSC 2004 [DIRS 169860]). Technical Work Plan for: Near-Field Environment and Transport In-Drift Geochemistry Model Report Integration (BSC 2004 [DIRS 171156]) is the technical work plan (TWP) for this report. It called for a revision of the previous version of the report (BSC 2004 [DIRS 167734]) to achieve greater transparency, readability, data traceability, and report integration. The intended use of the IDPS model is to estimate and tabulate, within an appropriate level of confidence, the effects of evaporation, deliquescence, and potential environmental conditions on the pH, ionic strength, and chemical compositions of water and minerals on the drip shield or other location within the drift during the postclosure period. Specifically, the intended use is as follows: (1) To estimate, within an appropriate level of confidence, the effects of evaporation and deliquescence on the presence and composition of water occurring within the repository during the postclosure period (i.e., effects on pH, ionic strength, deliquescence relative humidity, total concentrations of dissolved components in the system Na-K-H-Mg-Ca-Al-Cl-F-NO{sub 3}-SO{sub 4}-Br-CO{sub 3}-SiO{sub 2}-CO{sub 2}-O{sub 2}-H{sub 2}O, and concentrations of the following aqueous species that potentially affect acid neutralizing capacity: HCO{sub 3}{sup -}, CO{sub 3}{sup 2-}, OH{sup -}, H{sup +}, HSO{sub 4}{sup -}, Ca{sup 2+}, Mg{sup 2+}, CaHCO{sub 3}{sup +}, MgHCO{sub 3}{sup +}, HSiO{sub 3}{sup -}, and MgOH{sup +}); (2) To estimate, within an appropriate level of confidence, mineral precipitation resulting from the evaporation of water occurring within the repository during the postclosure period (specifically, minerals of the system Na-K-H-Mg-Ca-Al-Cl-F-NO{sub 3}-SO{sub 4}-Br-CO{sub 3}-SiO{sub 2}-CO{sub 2}-O{sub 2}-H{sub 2}O); (3) To provide a means for abstracting these effects into a set of lookup tables that provide input to downstream models used for performance assessment. The presence and composition of liquid water in the drift depend upon relative humidity, temperature, incoming water composition, in-drift gas composition, and relative rates of evaporation and seepage. In downstream applications of this model, intended input values for these parameters are abstracted results from thermal-hydrological-chemical models, water sample measurements, dust leachate samples, and values used in sensitivity and uncertainty analyses that encompass the expected ranges of these parameters.

  17. Development of high temperature transport technology for LiCl-KCl eutectic salt in pyroprocessing

    SciTech Connect (OSTI)

    Lee, Sung Ho; Lee, Hansoo; Kim, In Tae; Kim, Jeong-Guk

    2013-07-01

    The development of high-temperature transport technologies for molten salt is a prerequisite and a key issue in the industrialization of pyro-reprocessing for advanced fuel cycle scenarios. The solution of a molten salt centrifugal pump was discarded because of the high corrosion power of a high temperature molten salt, so the suction pump solution was selected. An apparatus for salt transport experiments by suction was designed and tested using LiC-KCl eutectic salt. The experimental results of lab-scale molten salt transport by suction showed a 99.5% transport rate (ratio of transported salt to total salt) under a vacuum range of 100 mtorr - 10 torr at 500 Celsius degrees. The suction system has been integrated to the PRIDE (pyroprocessing integrated inactive demonstration) facility that is a demonstrator using non-irradiated materials (natural uranium and surrogate materials). The performance of the suction pump for the transport of molten salts has been confirmed.

  18. Impacts of High Penetration of PV with Energy Storage at Flagstaff...

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

    OUTCOMES arizona photo.jpg Final Report Project Contact ALVIN RAZON Other Grid Performance & Reliability Projects Distributed Resource Energy Analysis and Management System ...

  19. Injector nozzle for molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, William A. (Livermore, CA); Upadhye, Ravindra S. (Pleasanton, CA)

    1996-01-01

    An injector nozzle has been designed for safely injecting energetic waste materials, such as high explosives, propellants, and rocket fuels, into a molten salt reactor in a molten salt destruction process without premature detonation or back burn in the injection system. The energetic waste material is typically diluted to form a fluid fuel mixture that is injected rapidly into the reactor. A carrier gas used in the nozzle serves as a carrier for the fuel mixture, and further dilutes the energetic material and increases its injection velocity into the reactor. The injector nozzle is cooled to keep the fuel mixture below the decomposition temperature to prevent spontaneous detonation of the explosive materials before contact with the high-temperature molten salt bath.

  20. Analytical methods for determining the reactivity of pyrochemical salts

    SciTech Connect (OSTI)

    Phillips, A.G.; Stakebake, J.L.

    1994-05-01

    Pyrochemical processes used for the purification of plutonium have generated quantities of residue that contain varying amounts of reactive metals such as potassium, sodium, calcium, and magnesium. These residues are currently considered hazardous and are being managed under RCRA because of the reactivity characteristic. This designation is based solely on process knowledge. Currently there is no approved procedure for determining the reactivity of a solid with water. A method is being developed to rapidly evaluate the reactivity of pyrochemical salts with water by measuring the rate of hydrogen generation. The method was initially tested with a magnesium containing pyrochemical salt. A detection limit of approximately 0.004 g of magnesium was established. A surrogate molten salt extraction residue was also tested. Extrapolation of test data resulted in a hydrogen generation rate of 4.4 mg/(g min).

  1. Injector nozzle for molten salt destruction of energetic waste materials

    DOE Patents [OSTI]

    Brummond, W.A.; Upadhye, R.S.

    1996-02-13

    An injector nozzle has been designed for safely injecting energetic waste materials, such as high explosives, propellants, and rocket fuels, into a molten salt reactor in a molten salt destruction process without premature detonation or back burn in the injection system. The energetic waste material is typically diluted to form a fluid fuel mixture that is injected rapidly into the reactor. A carrier gas used in the nozzle serves as a carrier for the fuel mixture, and further dilutes the energetic material and increases its injection velocity into the reactor. The injector nozzle is cooled to keep the fuel mixture below the decomposition temperature to prevent spontaneous detonation of the explosive materials before contact with the high-temperature molten salt bath. 2 figs.

  2. Current and proposed regulations for salt-water disposal wells

    SciTech Connect (OSTI)

    Moody, T.

    1994-12-31

    In recent years, all aspects of hydrocarbon exploration and production (E&P) activities have drawn closer scrutiny in terms of existing and potential impairment of the environment. In addition to drilling, production, and transportation activities, the United States Environmental Protection Agency (USEPA) has focused on the nature of E&P wastes. Approximately 98% of the volume of wastes generated by E&P activities is salt water associated with the recovery of hydrocarbons. By far the majority of this waste is reinjected in Class II wells as a nonhazardous waste. Due to the tremendous volume of salt water disposed of in Class II injection wells, the USEPA continues to reevaluate the Federal salt-water injection well program, offering comments, revising its interpretation of existing regulations, and promulgating new regulations. The purpose of this paper is to provide a review of existing Federal Class II injection well regulations and to provide an overview of potential of newly promulgated regulations.

  3. Salt transport extraction of transuranium elements from LWR fuel

    DOE Patents [OSTI]

    Pierce, R.D.; Ackerman, J.P.; Battles, J.E.; Johnson, T.R.; Miller, W.E.

    1992-11-03

    A process is described for separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl[sub 2] and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750 C to about 850 C to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl[sub 2] having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO[sub 2]. The Ca metal and CaCl[sub 2] is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including MgCl[sub 2] to transfer Mg values from the transport salt to the Cu--Mg alloy while transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy. 2 figs.

  4. Salt transport extraction of transuranium elements from lwr fuel

    DOE Patents [OSTI]

    Pierce, R. Dean; Ackerman, John P.; Battles, James E.; Johnson, Terry R.; Miller, William E.

    1992-01-01

    A process of separating transuranium actinide values from uranium values present in spent nuclear oxide fuels which contain rare earth and noble metal fission products. The oxide fuel is reduced with Ca metal in the presence of CaCl.sub.2 and a Cu--Mg alloy containing not less than about 25% by weight Mg at a temperature in the range of from about 750.degree. C. to about 850.degree. C. to precipitate uranium metal and some of the noble metal fission products leaving the Cu--Mg alloy having transuranium actinide metals and rare earth fission product metals and some of the noble metal fission products dissolved therein. The CaCl.sub.2 having CaO and fission products of alkali metals and the alkali earth metals and iodine dissolved therein is separated and electrolytically treated with a carbon electrode to reduce the CaO to Ca metal while converting the carbon electrode to CO and CO.sub.2. The Ca metal and CaCl.sub.2 is recycled to reduce additional oxide fuel. The Cu--Mg alloy having transuranium metals and rare earth fission product metals and the noble metal fission products dissolved therein is contacted with a transport salt including Mg Cl.sub.2 to transfer Mg values from the transport salt to the Cu--Mg alloy while transuranium actinide and rare earth fission product metals transfer from the Cu--Mg alloy to the transport salt. Then the transport salt is mixed with a Mg--Zn alloy to transfer Mg values from the alloy to the transport salt while the transuranium actinide and rare earth fission product values dissolved in the salt are reduced and transferred to the Mg--Zn alloy.

  5. Simulation of water transport in heated rock salt

    SciTech Connect (OSTI)

    Schlich, M.; Jockwer, N.

    1986-01-01

    This paper summarizes computer simulation studies on water transport in German rock salt. Based on JOCKWERS experimental investigations on water content and water liberation, the object of these studies was to select a water transport model, that matches the water inflow which was measured in some heater experiments in the Asse Salt Mine. The main result is, that an evaporation front model, with Knudsen-type vapor transport combined with fluid transport by thermal expansion of the adsorbed water layers in the non evaporated zone, showed the best agreement with experimental evidence.

  6. Materials and methods for stabilizing nanoparticles in salt solutions

    DOE Patents [OSTI]

    Robinson, David Bruce; Zuckermann, Ronald; Buffleben, George M.

    2013-06-11

    Sequence-specific polymers are proving to be a powerful approach to assembly and manipulation of matter on the nanometer scale. Ligands that are peptoids, or sequence-specific N-functional glycine oligomers, allow precise and flexible control over the arrangement of binding groups, steric spacers, charge, and other functionality. We have synthesized short peptoids that can prevent the aggregation of gold nanoparticles in high-salt environments including divalent salt, and allow co-adsorption of a single DNA molecule. This degree of precision and versatility is likely to prove essential in bottom-up assembly of nanostructures and in biomedical applications of nanomaterials.

  7. FINAL REPORT TESTS ON THE DURAMELTER 1200 HLW PILOT MELTER SYSTEM USING AZ-101 HLW SIMULANTS VSL-02R0100-2 REV 1 2/17/03

    SciTech Connect (OSTI)

    KRUGER AA; MATLACK KS; KOT WK; BARDAKCI T; GONG W; D'ANGELO NA; SCHATZ TR; PEGG IL

    2011-12-29

    This document provides the final report on data and results obtained from a series of nine tests performed on the one-third scale DuraMelter{trademark} 1200 (DM1200) HLW Pilot Melter system that has been installed at VSL with an integrated prototypical off-gas treatment system. That system has replaced the DM1000 system that was used for HLW throughput testing during Part B1 [1]. Both melters have similar melt surface areas (1.2 m{sup 2}) but the DM1200 is prototypical of the present RPP-WTP HLW melter design whereas the DM1000 was not. These tests were performed under a corresponding RPP-WTP Test Specification and associated Test Plans. The nine tests reported here were preceded by an initial series of short-duration tests conducted to support the start-up and commissioning of this system. This report is a followup to the previously issued Preliminary Data Summary Reports. The DM1200 system was deployed for testing and confirmation of basic design, operability, flow sheet, and process control assumptions as well as for support of waste form qualification and permitting. These tests include data on processing rates, off-gas treatment system performance, recycle stream compositions, as well as process operability and reliability. Consequently, this system is a key component of the overall HLW vitrification development strategy. The primary objective of the present series of tests was to determine the effects of a variety of parameters on the glass production rate in comparison to the RPP-WTP HL W design basis of 400 kg/m{sup 2}/d. Previous testing on the DMIOOO system [1] concluded that achievement of that rate with simulants of projected WTP melter feeds (AZ-101 and C-106/AY-102) was unlikely without the use of bubblers. As part of those tests, the same feed that was used during the cold-commissioning of the West Valley Demonstration Project (WVDP) HLW vitrification system was run on the DM1000 system. The DM1000 tests reproduced the rates that were obtained at the larger WVDP facility, lending confidence to the tests results [1]. Since the inclusion or exclusion of a bubbler has significant design implications, the Project commissioned further tests to address this issue. In an effort to identify factors that might increase the glass production rate for projected WTP melter feeds, a subsequent series of tests was performed on the DM100 system. Several tests variables led to glass production rate increases to values significantly above the 400 kg/m2/d requirement. However, while small-scale melter tests are useful for screening relative effects, they tend to overestimate absolute glass production rates, particularly for un-bubbled tests. Consequently, when scale-up effects were taken into account, it was not clear that any of the variables investigated would conclusively meet the 400 kg/m{sup 2}/d requirement without bubbling. The present series of tests was therefore performed on the DM1200 one-third scale HLW pilot melter system to provide the required basis for a final decision on whether bubblers would be included in the HLW melter. The present tests employed the same AZ-101 waste simulant and glass composition that was used for previous testing for consistency and comparability with the results from the earlier tests.

  8. Molten-Salt-Based Growth of Group III Nitrides

    DOE Patents [OSTI]

    Waldrip, Karen E.; Tsao, Jeffrey Y.; Kerley, Thomas M.

    2008-10-14

    A method for growing Group III nitride materials using a molten halide salt as a solvent to solubilize the Group-III ions and nitride ions that react to form the Group III nitride material. The concentration of at least one of the nitride ion or Group III cation is determined by electrochemical generation of the ions.

  9. Sealing of boreholes using natural, compatible materials: Granular salt

    SciTech Connect (OSTI)

    Finley, R.E.; Zeuch, D.H.; Stormont, J.C.; Daemen, J.J.K.

    1994-05-01

    Granular salt can be used to construct high performance permanent seals in boreholes which penetrate rock salt formations. These seals are described as seal systems comprised of the host rock, the seal material, and the seal rock interface. The performance of these seal systems is defined by the complex interactions between these seal system components through time. The interactions are largely driven by the creep of the host formation applying boundary stress on the seal forcing host rock permeability with time. The immediate permeability of these seals is dependent on the emplaced density. Laboratory test results suggest that careful emplacement techniques could results in immediate seal system permeability on the order of 10{sup {minus}16} m{sup 2} to 10{sup {minus}18} m{sup 2} (10{sup {minus}4} darcy to 10{sup {minus}6}). The visco-plastic behavior of the host rock coupled with the granular salts ability to ``heal`` or consolidate make granular salt an ideal sealing material for boreholes whose permanent sealing is required.

  10. Molten salt processing of mixed wastes with offgas condensation

    SciTech Connect (OSTI)

    Cooper, J.F.; Brummond, W.; Celeste, J.; Farmer, J.; Hoenig, C.; Krikorian, O.H.; Upadhye, R. ); Gay, R.L.; Stewart, A.; Yosim, S. . Energy Systems Group)

    1991-05-13

    We are developing an advanced process for treatment of mixed wastes in molten salt media at temperatures of 700--1000{degrees}C. Waste destruction has been demonstrated in a single stage oxidation process, with destruction efficiencies above 99.9999% for many waste categories. The molten salt provides a heat transfer medium, prevents thermal surges, and functions as an in situ scrubber to transform the acid-gas forming components of the waste into neutral salts and immobilizes potentially fugitive materials by a combination of particle wetting, encapsulation and chemical dissolution and solvation. Because the offgas is collected and assayed before release, and wastes containing toxic and radioactive materials are treated while immobilized in a condensed phase, the process avoids the problems sometimes associated with incineration processes. We are studying a potentially improved modification of this process, which treats oxidizable wastes in two stages: pyrolysis followed by catalyzed molten salt oxidation of the pyrolysis gases at ca. 700{degrees}C. 15 refs., 5 figs., 1 tab.

  11. TGS measurements of pyrochemical salts at Rocky Flats

    SciTech Connect (OSTI)

    Mercer, D. J.; Hansen, J. S.; Lestone, J. P.; Prettyman, T. H.

    2001-01-01

    A new skid-mounted tomographic gamma scanner (TGS) was designed to assist in the decommissioning of Rocky Flats Building 37 1, This instrument was used to assay pyrochemical salts as a prerequisite for disposal at the Waste Isolation Pilot Plant (WIPP). The following paper discusses measurement challenges and results from the first year of operation of the instrument.

  12. Salt Lake City, Utah: Solar in Action (Brochure)

    SciTech Connect (OSTI)

    Not Available

    2011-10-01

    This brochure provides an overview of the challenges and successes of Salt Lake City, UT, a 2007 Solar America City awardee, on the path toward becoming a solar-powered community. Accomplishments, case studies, key lessons learned, and local resource information are given.

  13. Project Profile: Long-Shafted Molten Salt Pump

    Broader source: Energy.gov [DOE]

    Pratt & Whitney Rocketdyne (PWR), under the CSP R&D FOA, is validating the manufacturability of a large-scale molten salt receiver panel and then confirming its operation in prototypic solar flux. This work is an important step in reducing the LCOE from a central receiver solar power plant.

  14. Decommissioning of the Molten Salt Reactor Experiment: A technical evaluation

    SciTech Connect (OSTI)

    Notz, K.J.

    1988-01-01

    This report completes a technical evaluation of decommissioning planning for the former Molten Salt Reactor Experiment, which was shut down in December, 1969. The key issues revolve around the treatment and disposal of some five tons of solid fuel salt which contains over 30 kg of fissionable uranium-233 plus fission products and higher actinides. The chemistry of this material is complicated by the formation of elemental fluorine via a radiolysis reaction under certain conditions. Supporting studies carried out as part of this evaluation include (a) a broad scope analysis of possible options for storage/disposal of the salts, (b) calculation of nuclide decay in future years, (c) technical evaluation of the containment facility and hot cell penetrations, (d) review and update of surveillance and maintenance procedures, (e) measurements of facility groundwater radioactivity and sump pump operation, (f) laboratory studies of the radiolysis reaction, and (g) laboratory studies which resulted in finding a suitable getter for elemental fluorine. In addition, geologic and hydrologic factors of the surrounding area were considered, and also the implications of entombment of the fuel in-place with concrete. The results of this evaluation show that the fuel salt cannot be left in its present form and location permanently. On the other hand, extended storage in its present form is quite acceptable for 20 to 30 years, or even longer. For continued storage in-place, some facility modifications are recommended. 30 refs., 5 figs., 9 tabs.

  15. 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.

  16. Methods of producing sulfate salts of cations from heteroatomic compounds and dialkyl sulfates and uses thereof

    DOE Patents [OSTI]

    Friesen, Cody A.; Wolfe, Derek; Johnson, Paul Bryan

    2015-09-29

    Methods of preparing sulfate salts of heteroatomic compounds using dialkyl sulfates as a primary reactant are disclosed. Also disclosed are methods of making ionic liquids from the sulfate salts of the heteroatomic compound, and electrochemical cells comprising the ionic liquids.

  17. Corrosion in Very High-Temperature Molten Salt for Next Generation...

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

    Corrosion in Very High-Temperature Molten Salt for Next Generation CSP Systems Corrosion in Very High-Temperature Molten Salt for Next Generation CSP Systems This presentation was ...

  18. Sample results from the interim salt disposition program macrobatch 9 tank 21H qualification samples

    SciTech Connect (OSTI)

    Peters, T. B.

    2015-11-01

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 9 for the Interim Salt Disposition Program (ISDP). This document reports characterization data on the samples of Tank 21H.

  19. Annular core liquid-salt cooled reactor with multiple fuel and...

    Office of Scientific and Technical Information (OSTI)

    Annular core liquid-salt cooled reactor with multiple fuel and blanket zones Citation Details In-Document Search Title: Annular core liquid-salt cooled reactor with multiple fuel ...

  20. Molten Salt Test Loop (MSTL) system customer interface document.

    SciTech Connect (OSTI)

    Gill, David Dennis; Kolb, William J.; Briggs, Ronald D.

    2013-09-01

    The National Solar Thermal Test Facility at Sandia National Laboratories has a unique test capability called the Molten Salt Test Loop (MSTL) system. MSTL is a test capability that allows customers and researchers to test components in flowing, molten nitrate salt. The components tested can range from materials samples, to individual components such as flex hoses, ball joints, and valves, up to full solar collecting systems such as central receiver panels, parabolic troughs, or linear Fresnel systems. MSTL provides realistic conditions similar to a portion of a concentrating solar power facility. The facility currently uses 60/40 nitrate %E2%80%9Csolar salt%E2%80%9D and can circulate the salt at pressure up to 40 bar (600psi), temperature to 585%C2%B0C, and flow rate of 44-50kg/s(400-600GPM) depending on temperature. The purpose of this document is to provide a basis for customers to evaluate the applicability to their testing needs, and to provide an outline of expectations for conducting testing on MSTL. The document can serve as the basis for testing agreements including Work for Others (WFO) and Cooperative Research and Development Agreements (CRADA). While this document provides the basis for these agreements and describes some of the requirements for testing using MSTL and on the site at Sandia, the document is not sufficient by itself as a test agreement. The document, however, does provide customers with a uniform set of information to begin the test planning process.

  1. Deep Eutectic Salt Formulations Suitable as Advanced Heat Transfer Fluids

    SciTech Connect (OSTI)

    Raade, Justin; Roark, Thomas; Vaughn, John; Bradshaw, Robert

    2013-07-22

    Concentrating solar power (CSP) facilities are comprised of many miles of fluid-filled pipes arranged in large grids with reflective mirrors used to capture radiation from the sun. Solar radiation heats the fluid which is used to produce steam necessary to power large electricity generation turbines. Currently, organic, oil-based fluid in the pipes has a maximum temperature threshold of 400 °C, allowing for the production of electricity at approximately 15 cents per kilowatt hour. The DOE hopes to foster the development of an advanced heat transfer fluid that can operate within higher temperature ranges. The new heat transfer fluid, when used with other advanced technologies, could significantly decrease solar electricity cost. Lower costs would make solar thermal electricity competitive with gas and coal and would offer a clean, renewable source of energy. Molten salts exhibit many desirable heat transfer qualities within the range of the project objectives. Halotechnics developed advanced heat transfer fluids (HTFs) for application in solar thermal power generation. This project focused on complex mixtures of inorganic salts that exhibited a high thermal stability, a low melting point, and other favorable characteristics. A high-throughput combinatorial research and development program was conducted in order to achieve the project objective. Over 19,000 candidate formulations were screened. The workflow developed to screen various chemical systems to discover salt formulations led to mixtures suitable for use as HTFs in both parabolic trough and heliostat CSP plants. Furthermore, salt mixtures which will not interfere with fertilizer based nitrates were discovered. In addition for use in CSP, the discovered salt mixtures can be applied to electricity storage, heat treatment of alloys and other industrial processes.

  2. BLENDING ANALYSIS FOR RADIOACTIVE SALT WASTE PROCESSING FACILITY

    SciTech Connect (OSTI)

    Lee, S.

    2012-05-10

    Savannah River National Laboratory (SRNL) evaluated methods to mix and blend the contents of the blend tanks to ensure the contents are properly blended before they are transferred from the blend tank such as Tank 21 and Tank 24 to the Salt Waste Processing Facility (SWPF) feed tank. The tank contents consist of three forms: dissolved salt solution, other waste salt solutions, and sludge containing settled solids. This paper focuses on developing the computational model and estimating the operation time of submersible slurry pump when the tank contents are adequately blended prior to their transfer to the SWPF facility. A three-dimensional computational fluid dynamics approach was taken by using the full scale configuration of SRS Type-IV tank, Tank 21H. Major solid obstructions such as the tank wall boundary, the transfer pump column, and three slurry pump housings including one active and two inactive pumps were included in the mixing performance model. Basic flow pattern results predicted by the computational model were benchmarked against the SRNL test results and literature data. Tank 21 is a waste tank that is used to prepare batches of salt feed for SWPF. The salt feed must be a homogeneous solution satisfying the acceptance criterion of the solids entrainment during transfer operation. The work scope described here consists of two modeling areas. They are the steady state flow pattern calculations before the addition of acid solution for tank blending operation and the transient mixing analysis during miscible liquid blending operation. The transient blending calculations were performed by using the 95% homogeneity criterion for the entire liquid domain of the tank. The initial conditions for the entire modeling domain were based on the steady-state flow pattern results with zero second phase concentration. The performance model was also benchmarked against the SRNL test results and literature data.

  3. Electrodialysis-based separation process for salt recovery and recycling from waste water

    DOE Patents [OSTI]

    Tsai, Shih-Perng

    1997-01-01

    A method for recovering salt from a process stream containing organic contaminants is provided, comprising directing the waste stream to a desalting electrodialysis unit so as to create a concentrated and purified salt permeate and an organic contaminants containing stream, and contacting said concentrated salt permeate to a water-splitting electrodialysis unit so as to convert the salt to its corresponding base and acid.

  4. Electrodialysis-based separation process for salt recovery and recycling from waste water

    DOE Patents [OSTI]

    Tsai, S.P.

    1997-07-08

    A method for recovering salt from a process stream containing organic contaminants is provided, comprising directing the waste stream to a desalting electrodialysis unit so as to create a concentrated and purified salt permeate and an organic contaminants-containing stream, and contacting said concentrated salt permeate to a water-splitting electrodialysis unit so as to convert the salt to its corresponding base and acid. 6 figs.

  5. Summary - Salt Waste Processing Facility Design at the Savannah River Site

    Office of Environmental Management (EM)

    Salt Waste Processing Facility ETR Report Date: November 2006 ETR-4 United States Department of Energy Office of Environmental Management (DOE-EM) External Technical Review of the Salt Waste Processing Facility Design at the Savannah River Site (SRS) Why DOE-EM Did This Review The Salt Waste Processing Facility (SWPF) is intended to remove and concentrate the radioactive strontium (Sr), actinides, and cesium (Cs) from the bulk salt waste solutions in the SRS high-level waste tanks. The sludge

  6. Synthesis of acid addition salt of delta-aminolevulinic acid from 5-bromo levulinic acid esters

    DOE Patents [OSTI]

    Moens, Luc

    2003-06-24

    A process of preparing an acid addition salt of delta-aminolevulinc acid comprising: a) dissolving a lower alkyl 5-bromolevulinate and hexamethylenetetramine in a solvent selected from the group consisting of water, ethyl acetate, chloroform, acetone, ethanol, tetrahydrofuran and acetonitrile, to form a quaternary ammonium salt of the lower alkyl 5-bromolevulinate; and b) hydrolyzing the quaternary ammonium salt with an inorganic acid to form an acid addition salt of delta-aminolevulinic acid.

  7. Bases, Assumptions, and Results of the Flowsheet Calculations for the Decision Phase Salt Disposition Alternatives

    SciTech Connect (OSTI)

    Elder, H.H.

    2001-07-11

    The HLW salt waste (salt cake and supernate) now stored at the SRS must be treated to remove insoluble sludge solids and reduce the soluble concentration of radioactive cesium radioactive strontium and transuranic contaminants (principally Pu and Np). These treatments will enable the salt solution to be processed for disposal as saltstone, a solid low-level waste.

  8. Sample Results from the Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-11

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  9. Sample Results From The Interim Salt Disposition Program Macrobatch 6 Tank 21H Qualification Samples

    SciTech Connect (OSTI)

    Peters, T. B.; Fink, S. D.

    2012-12-20

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 6 for the Interim Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 6 strategy are identified.

  10. FINAL REPORT INTEGRATED DM1200 MELTER TESTING OF BUBBLER CONFIGURATIONS USING HLW AZ-101 SIMULANTS VSL-04R4800-4 REV 0 10/5/04

    SciTech Connect (OSTI)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D'ANGELO NA; LUTZE W; CALLOW RA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of AZ-101 HLW simulants. The tests reported herein are a subset of six tests from a larger series of tests described in the Test Plan for the work; results from the other tests have been reported separately. The solids contents of the melter feeds were based on the WTP baseline value for the solids content of the feeds from pretreatment which changed during these tests from 20% to 15% undissolved solids resulting in tests conducted at two feed solids contents. Based on the results of earlier tests with single outlet 'J' bubblers, initial tests were performed with a total bubbling rate of 651 pm. The first set of tests (Tests 1A-1E) addressed the effects of skewing this total air flow rate back and forth between the two installed bubblers in comparison to a fixed equal division of flow between them. The second set of tests (2A-2D) addressed the effects of bubbler depth. Subsequently, as the location, type and number of bubbling outlets were varied, the optimum bubbling rate for each was determined. A third (3A-3C) and fourth (8A-8C) set of tests evaluated the effects of alternative bubbler designs with two gas outlets per bubbler instead of one by placing four bubblers in positions simulating multiple-outlet bubblers. Data from the simulated multiple outlet bubblers were used to design bubblers with two outlets for an additional set of tests (9A-9C). Test 9 was also used to determine the effect of small sugar additions to the feed on ruthenium volatility. Another set of tests (10A-10D) evaluated the effects on production rate of spiking the feed with chloride and sulfate. Variables held constant to the extent possible included melt temperature, plenum temperature, cold cap coverage, the waste simulant composition, and the target glass composition. The feed rate was increased to the point that a constant, essentially complete, cold cap was achieved, which was used as an indicator of a maximized feed rate for each test. The first day of each test was used to build the cold cap and decrease the plenum temperature. The remainder of each test was split into two- to six-day segments, each with a different bubbling rate, bubbler orientation, or feed concentration of chloride and sulfur.

  11. Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures

    SciTech Connect (OSTI)

    Rutqvist, Jonny; Blanco-Martin, Laura; Molins, Sergi; Trebotich, David; Birkholzer, Jens

    2015-09-01

    In this report, we present FY2015 progress by Lawrence Berkeley National Laboratory (LBNL) related to modeling of coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This is a combined milestone report related to milestone Salt R&D Milestone “Modeling Coupled THM Processes and Brine Migration in Salt at High Temperatures” (M3FT-15LB0818012) and the Salt Field Testing Milestone (M3FT-15LB0819022) to support the overall objectives of the salt field test planning.

  12. Domestic Material Content in Molten-Salt Concentrating Solar Power Plants

    SciTech Connect (OSTI)

    Turchi, Craig; Kurup, Parthiv; Akar, Sertac; Flores, Francisco

    2015-08-26

    This study lists material composition data for two concentrating solar power (CSP) plant designs: a molten-salt power tower and a hypothetical parabolic trough plant, both of which employ a molten salt for the heat transfer fluid (HTF) and thermal storage media. The two designs have equivalent generating and thermal energy storage capacities. The material content of the saltHTF trough plant was approximately 25% lower than a comparably sized conventional oil-HTF parabolic trough plant. The significant reduction in oil, salt, metal, and insulation mass by switching to a salt-HTF design is expected to reduce the capital cost and LCOE for the parabolic trough system.

  13. Process for the preparation of protected dihydroxypropyl trialkylammonium salts and derivatives thereof

    DOE Patents [OSTI]

    Hollingsworth, Rawle I.; Wang, Guijun

    2000-01-01

    A process for the preparation of protected dihydroxypropyl trialkylammonium salts, particularly in chiral form is described. In particular, a process for the preparation of (2,2-dimethyl-1,3-dioxolan-4-ylmethyl)trialkylammonium salts, particularly in chiral form is described. Furthermore, a process is described wherein the (2,2-dimethyl-1,3-dioxolan-4ylmethyl)trialkylammonium salts is a 2,2-dimethyl-1,3-dioxolan-4-ylmethyl trimethylammonium salt, preferably in chiral form. The protected dihydroxypropyl trialkylammonium salts lead to L-carnitine (9) when in chiral form (5).

  14. Salt South Central Region Natural Gas Working Underground Storage (Billion

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

    Cubic Feet) Salt South Central Region Natural Gas Working Underground Storage (Billion Cubic Feet) Salt South Central Region Natural Gas Working Underground Storage (Billion Cubic Feet) Year-Month Week 1 Week 2 Week 3 Week 4 Week 5 End Date Value End Date Value End Date Value End Date Value End Date Value 2010-Jan 01/01 159 01/08 123 01/15 91 01/22 102 01/29 108 2010-Feb 02/05 95 02/12 85 02/19 71 02/26 70 2010-Mar 03/05 63 03/12 71 03/19 80 03/26 89 2010-Apr 04/02 101 04/09 112 04/16 120

  15. Nuclear Hybrid Energy Systems: Molten Salt Energy Storage

    SciTech Connect (OSTI)

    P. Sabharwall; M. Green; S.J. Yoon; S.M. Bragg-Sitton; C. Stoots

    2014-07-01

    With growing concerns in the production of reliable energy sources, the next generation in reliable power generation, hybrid energy systems, are being developed to stabilize these growing energy needs. The hybrid energy system incorporates multiple inputs and multiple outputs. The vitality and efficiency of these systems resides in the energy storage application. Energy storage is necessary for grid stabilizing and storing the overproduction of energy to meet peak demands of energy at the time of need. With high thermal energy production of the primary nuclear heat generation source, molten salt energy storage is an intriguing option because of its distinct properties. This paper will discuss the different energy storage options with the criteria for efficient energy storage set forth, and will primarily focus on different molten salt energy storage system options through a thermodynamic analysis

  16. Heat Transfer Salts for Nuclear Reactor Systems - Chemistry

    Office of Scientific and Technical Information (OSTI)

    0-905 Heat Transfer Salts for Nuclear Reactor Systems - Chemistry Control, Corrosion Mitigation, and Modeling Reactor Concepts RD&D Dr. M ark Anderson U n iv e r s it y o f W i s c o n s i n , M a d i s o n In collaboration with: Pacific N o r t h w e s t N a t i o n a l La b o ra t o r y U n iv e r s it y o f California, B e r k e l e y Brian R o b i n s o n , Fede ra l POC M i c h a e l McKellar, Tec hnical POC Heat Transfer Salts for Nuclear Reactor Systems - chemistry control, corrosion

  17. Cooling molten salt reactors using “gas-lift”

    SciTech Connect (OSTI)

    Zitek, Pavel E-mail: klimko@kke.zcu.cz; Valenta, Vaclav E-mail: klimko@kke.zcu.cz; Klimko, Marek E-mail: klimko@kke.zcu.cz

    2014-08-06

    This study briefly describes the selection of a type of two-phase flow, suitable for intensifying the natural flow of nuclear reactors with liquid fuel - cooling mixture molten salts and the description of a “Two-phase flow demonstrator” (TFD) used for experimental study of the “gas-lift” system and its influence on the support of natural convection. The measuring device and the application of the TDF device is described. The work serves as a model system for “gas-lift” (replacing the classic pump in the primary circuit) for high temperature MSR planned for hydrogen production. An experimental facility was proposed on the basis of which is currently being built an experimental loop containing the generator, separator bubbles and necessary accessories. This loop will model the removal of gaseous fission products and tritium. The cleaning of the fuel mixture of fluoride salts eliminates problems from Xenon poisoning in classical reactors.

  18. Structural Interactions within Lithium Salt Solvates: Acyclic Carbonates and Esters

    SciTech Connect (OSTI)

    Afroz, Taliman; Seo, D. M.; Han, Sang D.; Boyle, Paul D.; Henderson, Wesley A.

    2015-03-06

    Solvate crystal structures serve as useful models for the molecular-level interactions within the diverse solvates present in liquid electrolytes. Although acyclic carbonate solvents are widely used for Li-ion battery electrolytes, only three solvate crystal structures with lithium salts are known for these and related solvents. The present work, therefore, reports six lithium salt solvate structures with dimethyl and diethyl carbonate: (DMC)2:LiPF6, (DMC)1:LiCF3SO3, (DMC)1/4:LiBF4, (DEC)2:LiClO4, (DEC)1:LiClO4 and (DEC)1:LiCF3SO3 and four with the structurally related methyl and ethyl acetate: (MA)2:LiClO4, (MA)1:LiBF4, (EA)1:LiClO4 and (EA)1:LiBF4.

  19. Photosensitive dissolution inhibitors and resists based on onium salt carboxylates

    DOE Patents [OSTI]

    Dentinger, Paul M.; Simison, Kelby L.

    2005-11-29

    A photoresist composition that employs onium salt carboxylates as thermally stable dissolution inhibitors. The photoresist composition can be either an onium carboxylate salt with a phenolic photoresist, such as novolac, or an onium cation protected carboxylate-containing resin such as an acrylic/acrylic acid copolymer. The onium carboxylate can be an onium cholate, wherein the onium cholate is an iodonium cholate. Particularly preferred iodonium cholates are alkyloxyphenylphenyl iodonium cholates and most particularly preferred is octyloxyphenyphenyl iodonium cholate. The photoresist composition will not create nitrogen or other gaseous byproducts upon exposure to radiation, does not require water for photoactivation, has acceptable UV radiation transmission characteristics, and is thermally stable at temperatures required for solvent removal.

  20. Engineering Options Assessment Report. Nitrate Salt Waste Stream Processing

    SciTech Connect (OSTI)

    Anast, Kurt Roy

    2015-11-13

    This report examines and assesses the available systems and facilities considered for carrying out remediation activities on remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The assessment includes a review of the waste streams consisting of 60 RNS, 29 above-ground UNS, and 79 candidate below-ground UNS containers that may need remediation. The waste stream characteristics were examined along with the proposed treatment options identified in the Options Assessment Report . Two primary approaches were identified in the five candidate treatment options discussed in the Options Assessment Report: zeolite blending and cementation. Systems that could be used at LANL were examined for housing processing operations to remediate the RNS and UNS containers and for their viability to provide repackaging support for remaining LANL legacy waste.

  1. Engineering Options Assessment Report: Nitrate Salt Waste Stream Processing

    SciTech Connect (OSTI)

    Anast, Kurt Roy

    2015-11-18

    This report examines and assesses the available systems and facilities considered for carrying out remediation activities on remediated nitrate salt (RNS) and unremediated nitrate salt (UNS) waste containers at Los Alamos National Laboratory (LANL). The assessment includes a review of the waste streams consisting of 60 RNS, 29 aboveground UNS, and 79 candidate belowground UNS containers that may need remediation. The waste stream characteristics were examined along with the proposed treatment options identified in the Options Assessment Report . Two primary approaches were identified in the five candidate treatment options discussed in the Options Assessment Report: zeolite blending and cementation. Systems that could be used at LANL were examined for housing processing operations to remediate the RNS and UNS containers and for their viability to provide repackaging support for remaining LANL legacy waste.

  2. Process Heat Exchanger Options for Fluoride Salt High Temperature Reactor

    SciTech Connect (OSTI)

    Piyush Sabharwall; Eung Soo Kim; Michael McKellar; Nolan Anderson

    2011-04-01

    The work reported herein is a significant intermediate step in reaching the final goal of commercial-scale deployment and usage of molten salt as the heat transport medium for process heat applications. The primary purpose of this study is to aid in the development and selection of the required heat exchanger for power production and process heat application, which would support large-scale deployment.

  3. Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties

    SciTech Connect (OSTI)

    Manohar S. Sohal; Matthias A. Ebner; Piyush Sabharwall; Phil Sharpe

    2010-03-01

    The purpose of this report is to provide a review of thermodynamic and thermophysical properties of candidate molten salt coolants, which may be used as a primary coolant within a nuclear reactor or heat transport medium from the Next Generation Nuclear Plant (NGNP) to a processing plant, for example, a hydrogen-production plant. Thermodynamic properties of four types of molten salts, including LiF-BeF2 (67 and 33 mol%, respectively; also known as FLiBe), LiF-NaF-KF (46.5, 11.5, and 52 mol%, also known as FLiNaK), and KCl-MgCl2 (67 and 33 mol%), and sodium nitrate-sodium nitrite-potassium nitrate (NaNO3–NaNO2–KNO3, (7-49-44 or 7-40-53 mol%) have been investigated. Limitations of existing correlations to predict density, viscosity, specific heat capacity, surface tension, and thermal conductivity, were identified. The impact of thermodynamic properties on the heat transfer, especially Nusselt number was also discussed. Stability of the molten salts with structural alloys and their compatibility with the structural alloys was studied. Nickel and alloys with dense Ni coatings are effectively inert to corrosion in fluorides but not so in chlorides. Of the chromium containing alloys, Hastelloy N appears to have the best corrosion resistance in fluorides, while Haynes 230 was most resistant in chloride. In general, alloys with increasing carbon and chromium content are increasingly subject to corrosion by the fluoride salts FLiBe and FLiNaK, due to attack and dissolution of the intergranular chromium carbide. Future research to obtain needed information was identified.

  4. Fluorination utilizing thermodynamically unstable fluorides and fluoride salts thereof

    DOE Patents [OSTI]

    Bartlett, Neil; Whalen, J. Marc; Chacon, Lisa

    2000-12-12

    A method for fluorinating a carbon compound or cationic carbon compound utilizes a fluorination agent selected from thermodynamically unstable nickel fluorides and salts thereof in liquid anhydrous hydrogen fluoride. The desired carbon compound or cationic organic compound to undergo fluorination is selected and reacted with the fluorination agent by contacting the selected organic or cationic organic compound and the chosen fluorination agent in a reaction vessel for a desired reaction time period at room temperature or less.

  5. Salt Waste Processing Facility (SWPF) System Turnover from Construction to

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

    Commissioning | Department of Energy Facility (SWPF) System Turnover from Construction to Commissioning Salt Waste Processing Facility (SWPF) System Turnover from Construction to Commissioning The SWPF Project Procedure establishes requirements and responsibilities that ensure the safe and orderly transition of jurisdictional control from Construction to Commissioning and Testing (C&T) for the system identified in Appendix A, SWPF Startup System Turnover Package List. Procedure

  6. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container

    Office of Environmental Management (EM)

    Nitrate Salt Bearing Waste Container Isolation Plan Prepared in Response to New Mexico Environment Department Administrative Order 05-20001 Issued May 20, 2014 1.0 INTRODUCTION The purpose of this document is to provide the Plan required by the New Mexico Environment Department (NMED) Administrative Order 05-20001 (Order) issued on May 20, 2014 to the U. S. Department of Energy (DOE) and Nuclear Waste Partnership LLC (NWP), collectively referred to as the Permittees. The Order, at paragraph 22,

  7. WIPP Nitrate Salt Bearing Waste Container Isolation Plan Implementation Update

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

    Nitrate Salt Bearing Waste Container Isolation Plan Implementation Update May 12, 2015 Panel 6 and Panel 7, Room 7 a. Rollback * Contamination Assessment-This prerequisite is complete and therefore status updates are no longer required. * Fixing/Decontamination Activities-Decontaminated equipment has been removed from Room 7 of Panel 7 to prepare for Room 7 closure activities. Remaining items in Panel 7, Room 7 include thirteen empty magnesium oxide racks, about 200 roof bolts, nine messenger

  8. Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory

    Office of Environmental Management (EM)

    Remediated Nitrate Salt Drums Storage at Los Alamos National Laboratory Background Technical Area (TA) 54 is Los Alamos National Laboratory's transuranic (TRU) and low-level waste storage, characterization, and remediation area. The 63-acre site is located one mile from the community of White Rock and approximately one-eighth mile from the boundary be- tween Pueblo de San Ildefonso and the Laboratory. As a part of its national security mission, the Laboratory conducts research that generates

  9. Generic effluent monitoring system certification for salt well portable exhauster

    SciTech Connect (OSTI)

    Glissmeyer, J.A.; Maughan, A.D.

    1997-09-01

    Tests were conducted to verify that the Generic Effluent Monitoring System (GEMS), as it is applied to the Salt Well Portable Exhauster, meets all applicable regulatory performance criteria for air sampling systems at nuclear facilities. These performance criteria address both the suitability of the air sampling probe location and the transport of the sample to the collection devices. The criteria covering air sampling probe location ensure that the contaminants in the stack are well mixed with the airflow at the probe location such that the extracted sample represents the whole. The sample transport criteria ensure that the sampled contaminants are quantitatively delivered to the collection device. The specific performance criteria are described in detail in the report. The tests demonstrated that the GEMS/Salt Well Exhauster system meets all applicable performance criteria. Pacific Northwest National Laboratory conducted the testing using a mockup of the Salt Well Portable Exhauster stack at the Numatec Hanford Company`s 305 Building. The stack/sampling system configuration tested was designed to provide airborne effluent control for the Salt Well pumping operation at some U.S. Department of Energy (DOE) radioactive waste storage tanks at the Hanford Site, Washington. The portable design of the exhauster allows it to be used in other applications and over a range of exhaust air flowrates (approximately 200 - 1100 cubic feet per minute). The unit includes a stack section containing the sampling probe and another stack section containing the airflow, temperature and humidity sensors. The GEMS design features a probe with a single shrouded sampling nozzle, a sample delivery line, and sample collection system. The collection system includes a filter holder to collect the sample of record and an in-line detector head and filter for monitoring beta radiation-emitting particles.

  10. Transpiring wall supercritical water oxidation reactor salt deposition studies

    SciTech Connect (OSTI)

    Haroldsen, B.L.; Mills, B.E.; Ariizumi, D.Y.; Brown, B.G.

    1996-09-01

    Sandia National Laboratories has teamed with Foster Wheeler Development Corp. and GenCorp, Aerojet to develop and evaluate a new supercritical water oxidation reactor design using a transpiring wall liner. In the design, pure water is injected through small pores in the liner wall to form a protective boundary layer that inhibits salt deposition and corrosion, effects that interfere with system performance. The concept was tested at Sandia on a laboratory-scale transpiring wall reactor that is a 1/4 scale model of a prototype plant being designed for the Army to destroy colored smoke and dye at Pine Bluff Arsenal in Arkansas. During the tests, a single-phase pressurized solution of sodium sulfate (Na{sub 2}SO{sub 4}) was heated to supercritical conditions, causing the salt to precipitate out as a fine solid. On-line diagnostics and post-test observation allowed us to characterize reactor performance at different flow and temperature conditions. Tests with and without the protective boundary layer demonstrated that wall transpiration provides significant protection against salt deposition. Confirmation tests were run with one of the dyes that will be processed in the Pine Bluff facility. The experimental techniques, results, and conclusions are discussed.

  11. Sensitivity of storage field performance to geologic and cavern design parameters in salt domes.

    SciTech Connect (OSTI)

    Ehgartner, Brian L.; Park, Byoung Yoon

    2009-03-01

    A sensitivity study was performed utilizing a three dimensional finite element model to assess allowable cavern field sizes for strategic petroleum reserve salt domes. A potential exists for tensile fracturing and dilatancy damage to salt that can compromise the integrity of a cavern field in situations where high extraction ratios exist. The effects of salt creep rate, depth of salt dome top, dome size, caprock thickness, elastic moduli of caprock and surrounding rock, lateral stress ratio of surrounding rock, cavern size, depth of cavern, and number of caverns are examined numerically. As a result, a correlation table between the parameters and the impact on the performance of storage field was established. In general, slower salt creep rates, deeper depth of salt dome top, larger elastic moduli of caprock and surrounding rock, and a smaller radius of cavern are better for structural performance of the salt dome.

  12. Intrinsic Bioprobes, Inc. (Tempe, AZ)

    DOE Patents [OSTI]

    Nelson, Randall W.; Williams, Peter; Krone, Jennifer Reeve

    2008-07-15

    Rapid mass spectrometric immunoassay methods for detecting and/or quantifying antibody and antigen analytes utilizing affinity capture to isolate the analytes and internal reference species (for quantification) followed by mass spectrometric analysis of the isolated analyte/internal reference species. Quantification is obtained by normalizing and calibrating obtained mass spectrum against the mass spectrum obtained for an antibody/antigen of known concentration.

  13. Diffusion Welding of Alloys for Molten Salt Service - Status Report

    SciTech Connect (OSTI)

    Denis Clark; Ronald Mizia; Piyush Sabharwall

    2012-09-01

    The present work is concerned with heat exchanger development for molten salt service, including the proposed molten salt reactor (MSR), a homogeneous reactor in which the fuel is dissolved in a circulating fluid of molten salt. It is an outgrowth of recent work done under the Next Generation Nuclear Plant (NGNP) program; what the two reactor systems have in common is an inherently safe nuclear plant with a high outlet temperature that is useful for process heat as well as more conventional generation The NGNP program was tasked with investigating the application of a new generation of nuclear power plants to a variety of energy needs. One baseline reactor design for this program is a high temperature, gas-cooled reactor (HTGR), which provides many options for energy use. These might include the conventional Rankine cycle (steam turbine) generation of electricity, but also other methods: for example, Brayton cycle (gas turbine) electrical generation, and the direct use of the high temperatures characteristic of HTGR output for process heat in the chemical industry. Such process heat is currently generated by burning fossil fuels, and is a major contributor to the carbon footprint of the chemical and petrochemical industries. The HTGR, based on graphite fuel elements, can produce very high output temperatures; ideally, temperatures of 900 °C or even greater, which has significant energy advantages. Such temperatures are, of course, at the frontiers of materials limitations, at the upper end of the performance envelope of the metallic materials for which robust construction codes exist, and within the realm of ceramic materials, the fabrication and joining of which, on the scale of large energy systems, are at an earlier stage of development. A considerable amount of work was done in the diffusion welding of materials of interest for HTGR service with alloys such as 617 and 800H. The MSR output temperature is also materials limited, and is projected at about 700 °C. (RR E) A different set of alloys, such as Alloy N and 242, are needed to handle molten salts at this temperature. The diffusion welding development work described here builds on techniques developed during the NGNP work, as applied to these alloys. There is also the matter of dissimilar metal welding, since alloys suitable for salt service are generally not suited for service in gaseous oxidizing environments, and vice versa, and welding is required for the Class I boundaries in these systems, as identified in the relevant ASME codes.

  14. Diffusion Welding of Alloys for Molten Salt Service - Status Report

    SciTech Connect (OSTI)

    Denis Clark; Ronald Mizia

    2012-05-01

    The present work is concerned with heat exchanger development for molten salt service, including the proposed molten salt reactor (MSR), a homogeneous reactor in which the fuel is dissolved in a circulating fluid of molten salt. It is an outgrowth of recent work done under the Next Generation Nuclear Plant (NGNP) program; what the two reactor systems have in common is an inherently safe nuclear plant with a high outlet temperature that is useful for process heat as well as more conventional generation The NGNP program was tasked with investigating the application of a new generation of nuclear power plants to a variety of energy needs. One baseline reactor design for this program is a high temperature, gas-cooled reactor (HTGR), which provides many options for energy use. These might include the conventional Rankine cycle (steam turbine) generation of electricity, but also other methods: for example, Brayton cycle (gas turbine) electrical generation, and the direct use of the high temperatures characteristic of HTGR output for process heat in the chemical industry. Such process heat is currently generated by burning fossil fuels, and is a major contributor to the carbon footprint of the chemical and petrochemical industries. The HTGR, based on graphite fuel elements, can produce very high output temperatures; ideally, temperatures of 900 C or even greater, which has significant energy advantages. Such temperatures are, of course, at the frontiers of materials limitations, at the upper end of the performance envelope of the metallic materials for which robust construction codes exist, and within the realm of ceramic materials, the fabrication and joining of which, on the scale of large energy systems, are at an earlier stage of development. A considerable amount of work was done in the diffusion welding of materials of interest for HTGR service with alloys such as 617 and 800H. The MSR output temperature is also materials limited, and is projected at about 700 C. (RR E) A different set of alloys, such as Alloy N and 242, are needed to handle molten salts at this temperature. The diffusion welding development work described here builds on techniques developed during the NGNP work, as applied to these alloys. There is also the matter of dissimilar metal welding, since alloys suitable for salt service are generally not suited for service in gaseous oxidizing environments, and vice versa, and welding is required for the Class I boundaries in these systems, as identified in the relevant ASME codes.

  15. Salt effects on isotope partitioning and their geochemical implications: An overview

    SciTech Connect (OSTI)

    Horita, J.; Cole, D.R.; Fortier, S.M.

    1996-01-01

    Essential to the use of stable isotopes as natural tracers and geothermometers is the knowledge of equilibrium isotope partitioning between different phases and species, which is usually a function of temperature only. The one exception known to date is oxygen and hydrogen isotope fractionation between liquid water and other phases (steam, gases, minerals), which changes upon the addition of salts to water, i.e., the isotope salt salt effect. Our knowledge of this effect, the difference between activity and composition (a-X) of isotopic water molecules in salt solutions, is very limited and controversial, especially at elevated temperatures. For the last several years, we have been conducting a detailed, systematic experimental study at Oak Ridge National Laboratory to determine the isotope salt effects from room temperature to elevated temperatures (currently to 500{degree}C). From this effort, a simple, coherent picture of the isotope salt effect is emerging, that differs markedly from the complex results reported in the literature. In this communication, we present an overview on the isotope salt effect, obtained chiefly from our study. Observed isotope salt effects in salt solutions are significant even at elevated temperatures. The importance and implications of the isotope salt effect for isotopic studies of brine-dominated systems are also discussed in general terms.

  16. Novel Molten Salts Thermal Energy Storage for Concentrating Solar Power Generation

    SciTech Connect (OSTI)

    Reddy, Ramana G.

    2013-10-23

    The explicit UA program objective is to develop low melting point (LMP) molten salt thermal energy storage media with high thermal energy storage density for sensible heat storage systems. The novel Low Melting Point (LMP) molten salts are targeted to have the following characteristics: 1. Lower melting point (MP) compared to current salts (<222ºC) 2. Higher energy density compared to current salts (>300 MJ/m3) 3. Lower power generation cost compared to current salt In terms of lower power costs, the program target the DOE's Solar Energy Technologies Program year 2020 goal to create systems that have the potential to reduce the cost of Thermal Energy Storage (TES) to less than $15/kWh-th and achieve round trip efficiencies greater than 93%. The project has completed the experimental investigations to determine the thermo-physical, long term thermal stability properties of the LMP molten salts and also corrosion studies of stainless steel in the candidate LMP molten salts. Heat transfer and fluid dynamics modeling have been conducted to identify heat transfer geometry and relative costs for TES systems that would utilize the primary LMP molten salt candidates. The project also proposes heat transfer geometry with relevant modifications to suit the usage of our molten salts as thermal energy storage and heat transfer fluids. The essential properties of the down-selected novel LMP molten salts to be considered for thermal storage in solar energy applications were experimentally determined, including melting point, heat capacity, thermal stability, density, viscosity, thermal conductivity, vapor pressure, and corrosion resistance of SS 316. The thermodynamic modeling was conducted to determine potential high temperature stable molten salt mixtures that have thermal stability up to 1000 °C. The thermo-physical properties of select potential high temperature stable (HMP) molten salt mixtures were also experimentally determined. All the salt mixtures align with the go/no-go goals stipulated by the DOE for this project. Energy densities of all salt mixtures were higher than that of the current solar salt. The salt mixtures costs have been estimated and TES system costs for a 2 tank, direct approach have been estimated for each of these materials. All estimated costs are significantly below the baseline system that used solar salt. These lower melt point salts offer significantly higher energy density per volume than solar salt – and therefore attractively smaller inventory and equipment costs. Moreover, a new TES system geometry has been recommended A variety of approaches were evaluated to use the low melting point molten salt. Two novel changes are recommended that 1) use the salt as a HTF through the solar trough field, and 2) use the salt to not only create steam but also to preheat the condensed feedwater for Rankine cycle. The two changes enable the powerblock to operate at 500°C, rather than the current 400°C obtainable using oil as the HTF. Secondly, the use of salt to preheat the feedwater eliminates the need to extract steam from the low pressure turbine for that purpose. Together, these changes result in a dramatic 63% reduction required for 6 hour salt inventory, a 72% reduction in storage volume, and a 24% reduction in steam flow rate in the power block. Round trip efficiency for the Case 5 - 2 tank “direct” system is estimated at >97%, with only small losses from time under storage and heat exchange, and meeting RFP goals. This attractive efficiency is available because the major heat loss experienced in a 2 tank “indirect” system - losses by transferring the thermal energy from oil HTF to the salt storage material and back to oil to run the steam generator at night - is not present for the 2 tank direct system. The higher heat capacity values for both LMP and HMP systems enable larger storage capacities for concentrating solar power.

  17. Baseload Nitrate Salt Central Receiver Power Plant Design Final Report

    SciTech Connect (OSTI)

    Tilley, Drake; Kelly, Bruce; Burkholder, Frank

    2014-12-12

    The objectives of the work were to demonstrate that a 100 MWe central receiver plant, using nitrate salt as the receiver coolant, thermal storage medium, and heat transport fluid in the steam generator, can 1) operate, at full load, for 6,400 hours each year using only solar energy, and 2) satisfy the DOE levelized energy cost goal of $0.09/kWhe (real 2009 $). To achieve these objectives the work incorporated a large range of tasks relating to many different aspects of a molten salt tower plant. The first Phase of the project focused on developing a baseline design for a Molten Salt Tower and validating areas for improvement. Tasks included a market study, receiver design, heat exchanger design, preliminary heliostat design, solar field optimization, baseline system design including PFDs and P&IDs and detailed cost estimate. The baseline plant met the initial goal of less than $0.14/kWhe, and reinforced the need to reduce costs in several key areas to reach the overall $0.09/kWhe goal. The major improvements identified from Phase I were: 1) higher temperature salt to improve cycle efficiency and reduce storage requirements, 2) an improved receiver coating to increase the efficiency of the receiver, 3) a large receiver design to maximize storage and meet the baseload hours objective, and 4) lower cost heliostat field. The second Phase of the project looked at advancing the baseline tower with the identified improvements and included key prototypes. To validate increasing the standard solar salt temperature to 600 °C a dynamic test was conducted at Sandia. The results ultimately proved the hypothesis incorrect and showed high oxide production and corrosion rates. The results lead to further testing of systems to mitigate the oxide production to be able to increase the salt temperature for a commercial plant. Foster Wheeler worked on the receiver design in both Phase I and Phase II looking at both design and lowering costs utilizing commercial fossil boiler manufacturing. The cost and design goals for the project were met with this task, but the most interesting results had to do with defining the failure modes and looking at a “shakedown analysis” of the combined creep-fatigue failure. A separate task also looked at improving the absorber coatings on the receiver tubes that would improve the efficiency of the receiver. Significant progress was made on developing a novel paint with a high absorptivity that was on par with the current Pyromark, but shows additional potential to be optimized further. Although the coating did not meet the emissivity goals, preliminary testing the new paint shows potential to be much more durable, and potential to improve the receiver efficiency through a higher average absorptivity over the lifetime. Additional coatings were also designed and modeled results meet the project goals, but were not tested. Testing for low cycle fatigue of the full length receiver tubes was designed and constructed, but is still currently undergoing testing. A novel small heliostat was developed through an extensive brainstorming and down select. The concept was then detailed further with inputs from component testing and eventually a full prototype was built and tested. This task met or exceeded the accuracy and structure goals and also beat the cost goal. This provides a significant solar field costs savings for Abengoa that will be developed further to be used in future commercial plants. Ultimately the $0.09/kWhe (real 2009 $) and 6,400 hours goals of the project were met.

  18. FINAL REPORT INTEGRATED DM1200 MELTER TESTING OF REDOX EFFECTS USING HLW AZ-101 AND C-106/AY-102 SIMULANTS VSL-04R4800-1 REV 0 5/6/

    SciTech Connect (OSTI)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D'ANGELO NA; LUTZE W; BIZOT PM; CALLOW RA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    This report documents melter and off-gas performance results obtained on the DM1200 HLW Pilot Melter during processing of AZ-101 and C-106/AY-102 HLW simulants. The tests reported herein are a subset of three tests from a larger series of tests described in the Test Plan for the work; results from the remaining tests will be reported separately. Three nine day tests, one with AZ-101 and two with C-106/AY-102 feeds were conducted with variable amounts of added sugar to address the effects of redox. The test with AZ-101 included ruthenium spikes to also address the effects of redox on ruthenium volatility. One of tests addressed the effects of increased flow-sheet nitrate levels using C-106/AY-102 feeds. With high nitrate/nitrite feeds (such as WTP LAW feeds), reductants are required to prevent melt foaming and deleterious effects on glass production rates. Sugar is the baseline WTP reductant for this purpose. WTP HLW feeds typically have relatively low nitrate/nitrite content in comparison to the organic carbon content and, therefore, have typically not required sugar additions. However, HLW feed variability, particularly with respect to nitrate levels, may necessitate the use of sugar in some instances. The tests reported here investigate the effects of variable sugar additions to the melter feed as well as elevated nitrate levels in the waste. Variables held constant to the extent possible included melt temperature, bubbling rate, plenum temperature, cold cap coverage, the waste simulant composition, and the target glass composition. The principal objectives of the DM1200 melter testing were to determine the achievable glass production rates for simulated HLW feeds with variable amounts of added sugar and increased nitrate levels; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table.

  19. Blending of Radioactive Salt Solutions in Million Gallon Tanks - 13002

    SciTech Connect (OSTI)

    Leishear, Robert A.; Lee, Si Y.; Fowley, Mark D.; Poirier, Michael R. [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)] [Savannah River National Laboratory, Aiken. S.C., 29808 (United States)

    2013-07-01

    Research was completed at Savannah River National Laboratory (SRNL) to investigate processes related to the blending of radioactive, liquid waste, salt solutions in 4920 cubic meter, 25.9 meter diameter storage tanks. One process was the blending of large salt solution batches (up to 1135 - 3028 cubic meters), using submerged centrifugal pumps. A second process was the disturbance of a settled layer of solids, or sludge, on the tank bottom. And a third investigated process was the settling rate of sludge solids if suspended into slurries by the blending pump. To investigate these processes, experiments, CFD models (computational fluid dynamics), and theory were applied. Experiments were performed using simulated, non-radioactive, salt solutions referred to as supernates, and a layer of settled solids referred to as sludge. Blending experiments were performed in a 2.44 meter diameter pilot scale tank, and flow rate measurements and settling tests were performed at both pilot scale and full scale. A summary of the research is presented here to demonstrate the adage that, 'One good experiment fixes a lot of good theory'. Experimental testing was required to benchmark CFD models, or the models would have been incorrectly used. In fact, CFD safety factors were established by this research to predict full-scale blending performance. CFD models were used to determine pump design requirements, predict blending times, and cut costs several million dollars by reducing the number of required blending pumps. This research contributed to DOE missions to permanently close the remaining 47 of 51 SRS waste storage tanks. (authors)

  20. Transportation of pyrochemical salts from Rocky Flats to Los Alamos

    SciTech Connect (OSTI)

    Schreiber, S.B.

    1997-02-01

    Radioactive legacy wastes or residues are currently being stored on numerous Sites around the former Department of Energy`s (DOE) Nuclear Weapons Complex. Since most of the operating facilities were shut down and have not operated since before the declared end to the Cold War in 1993, the historical method for treating these residues no longer exists. The risk associated with continued storage of these residues will dramatically increase with time. Thus, the DOE was directed by the Defense Nuclear Facility Safety Board in its Recommendation 94-1 to address and stabilize these residues and established an eight year time frame for doing so. There are only two options available to respond to this requirement: (1) restart existing facilities to treat and package the residues for disposal or (2) transport the residues to another operating facility within the Complex where they can be treated and packaged for disposal. This paper focuses on one such residue type, pyrochemical salts, produced at one Complex site, the Rocky Flats Plant located northwest of Denver, Colorado. One option for treating the salts is their shipment to Los Alamos, New Mexico, for handling at the Plutonium Facility. The safe transportation of these salts can be accomplished at present with several shipping containers including a DOT 6M, a DOE 9968, Type A or Type B quantity 55-gallon drum overpacks, or even the TRUPACT II. The tradeoffs between each container is examined with the conclusion that none of the available shipping containers is fully satisfactory. Thus, the advantageous aspects of each container must be utilized in an integrated and efficient way to effectively manage the risk involved. 1 fig.

  1. Blending Of Radioactive Salt Solutions In Million Gallon Tanks

    SciTech Connect (OSTI)

    Leishear, Robert A.; Lee, Si Y.; Fowley, Mark D.; Poirier, Michael R.

    2012-12-10

    Research was completed at Savannah River National Laboratory (SRNL) to investigate processes related to the blending of radioactive, liquid waste, salt solutions in 4920 cubic meter, 25.9 meter diameter storage tanks. One process was the blending of large salt solution batches (up to 1135 ? 3028 cubic meters), using submerged centrifugal pumps. A second process was the disturbance of a settled layer of solids, or sludge, on the tank bottom. And a third investigated process was the settling rate of sludge solids if suspended into slurries by the blending pump. To investigate these processes, experiments, CFD models (computational fluid dynamics), and theory were applied. Experiments were performed using simulated, non-radioactive, salt solutions referred to as supernates, and a layer of settled solids referred to as sludge. Blending experiments were performed in a 2.44 meter diameter pilot scale tank, and flow rate measurements and settling tests were performed at both pilot scale and full scale. A summary of the research is presented here to demonstrate the adage that, ?One good experiment fixes a lot of good theory?. Experimental testing was required to benchmark CFD models, or the models would have been incorrectly used. In fact, CFD safety factors were established by this research to predict full-scale blending performance. CFD models were used to determine pump design requirements, predict blending times, and cut costs several million dollars by reducing the number of required blending pumps. This research contributed to DOE missions to permanently close the remaining 47 of 51 SRS waste storage tanks.

  2. Identifying suitable "piercement" salt domes for nuclear waste storage sites

    SciTech Connect (OSTI)

    Kehle, R.

    1980-08-01

    Piercement salt domes of the northern interior salt basins of the Gulf of Mexico are being considered as permanent storage sites for both nuclear and chemically toxic wastes. The suitable domes are stable and inactive, having reached their final evolutionary configuration at least 30 million years ago. They are buried to depths far below the level to which erosion will penetrate during the prescribed storage period and are not subject to possible future reactivation. The salt cores of these domes are themselves impermeable, permitting neither the entry nor exit of ground water or other unwanted materials. In part, a stable dome may be recognized by its present geometric configuration, but conclusive proof depends on establishing its evolutionary state. The evolutionary state of a dome is obtained by reconstructing the growth history of the dome as revealed by the configuration of sedimentary strata in a large area (commonly 3,000 square miles or more) surrounding the dome. A high quality, multifold CDP reflection seismic profile across a candidate dome will provide much of the necessary information when integrated with available subsurface control. Additional seismic profiles may be required to confirm an apparent configuration of the surrounding strata and an interpreted evolutionary history. High frequency seismic data collected in the near vicinity of a dome are also needed as a supplement to the CDP data to permit accurate depiction of the configuration of shallow strata. Such data must be tied to shallow drill hole control to confirm the geologic age at which dome growth ceased. If it is determined that a dome reached a terminal configuration many millions of years ago, such a dome is incapable of reactivation and thus constitutes a stable storage site for nuclear wastes.

  3. Low-melting point inorganic nitrate salt heat transfer fluid

    DOE Patents [OSTI]

    Bradshaw, Robert W.; Brosseau, Douglas A.

    2009-09-15

    A low-melting point, heat transfer fluid made of a mixture of four inorganic nitrate salts: 9-18 wt % NaNO.sub.3, 40-52 wt % KNO.sub.3, 13-21 wt % LiNO.sub.3, and 20-27 wt % Ca(NO.sub.3).sub.2. These compositions can have liquidus temperatures less than 100 C; thermal stability limits greater than 500 C; and viscosity in the range of 5-6 cP at 300 C; and 2-3 cP at 400 C.

  4. SODIUM ALUMINOSILICATE FOULING AND CLEANING OF DECONTAMINATED SALT SOLUTION COALESCERS

    SciTech Connect (OSTI)

    Poirier, M; Thomas Peters, T; Fernando Fondeur, F; Samuel Fink, S

    2008-10-28

    During initial non-radioactive operations at the Modular Caustic Side Solvent Extraction Unit (MCU), the pressure drop across the decontaminated salt solution coalescer reached {approx}10 psi while processing {approx}1250 gallons of salt solution, indicating possible fouling or plugging of the coalescer. An analysis of the feed solution and the 'plugged coalescer' concluded that the plugging was due to sodium aluminosilicate solids. MCU personnel requested Savannah River National Laboratory (SRNL) to investigate the formation of the sodium aluminosilicate solids (NAS) and the impact of the solids on the decontaminated salt solution coalescer. Researchers performed developmental testing of the cleaning protocols with a bench-scale coalescer container 1-inch long segments of a new coalescer element fouled using simulant solution. In addition, the authors obtained a 'plugged' Decontaminated Salt Solution coalescer from non-radioactive testing in the MCU and cleaned it according to the proposed cleaning procedure. Conclusions from this testing include the following: (1) Testing with the bench-scale coalescer showed an increase in pressure drop from solid particles, but the increase was not as large as observed at MCU. (2) Cleaning the bench-scale coalescer with nitric acid reduced the pressure drop and removed a large amount of solid particles (11 g of bayerite if all aluminum is present in that form or 23 g of sodium aluminosilicate if all silicon is present in that form). (3) Based on analysis of the cleaning solutions from bench-scale test, the 'dirt capacity' of a 40 inch coalescer for the NAS solids tested is calculated as 450-950 grams. (4) Cleaning the full-scale coalescer with nitric acid reduced the pressure drop and removed a large amount of solid particles (60 g of aluminum and 5 g of silicon). (5) Piping holdup in the full-scale coalescer system caused the pH to differ from the target value. Comparable hold-up in the facility could lead to less effective cleaning and precipitation of bayerite solid particles. (6) Based on analysis of the cleaning solutions from the full-scale test, the 'dirt capacity' of a 40 inch coalescer for these NAS solids was calculated to be 40-170 grams.

  5. Method for removing semiconductor layers from salt substrates

    DOE Patents [OSTI]

    Shuskus, Alexander J.; Cowher, Melvyn E.

    1985-08-27

    A method is described for removing a CVD semiconductor layer from an alkali halide salt substrate following the deposition of the semiconductor layer. The semiconductor-substrate combination is supported on a material such as tungsten which is readily wet by the molten alkali halide. The temperature of the semiconductor-substrate combination is raised to a temperature greater than the melting temperature of the substrate but less than the temperature of the semiconductor and the substrate is melted and removed from the semiconductor by capillary action of the wettable support.

  6. Melting of Uranium Metal Powders with Residual Salts

    SciTech Connect (OSTI)

    Jin-Mok Hur; Dae-Seung Kang; Chung-Seok Seo

    2007-07-01

    The Advanced Spent Fuel Conditioning Process (ACP) of the Korea Atomic Energy Research Institute focuses on the conditioning of Pressurized Water Reactor spent oxide nuclear fuel. After the oxide reduction step of the ACP, the resultant metal powders containing {approx} 30 wt% residual LiCl-Li{sub 2}O should be melted for a consolidation of the fine metal powders. In this study, we investigated the melting behaviors of uranium metal powders considering the effects of a LiCl-Li{sub 2}O residual salt. (authors)

  7. Dilute acid/metal salt hydrolysis of lignocellulosics

    DOE Patents [OSTI]

    Nguyen, Quang A.; Tucker, Melvin P.

    2002-01-01

    A modified dilute acid method of hydrolyzing the cellulose and hemicellulose in lignocellulosic material under conditions to obtain higher overall fermentable sugar yields than is obtainable using dilute acid alone, comprising: impregnating a lignocellulosic feedstock with a mixture of an amount of aqueous solution of a dilute acid catalyst and a metal salt catalyst sufficient to provide higher overall fermentable sugar yields than is obtainable when hydrolyzing with dilute acid alone; loading the impregnated lignocellulosic feedstock into a reactor and heating for a sufficient period of time to hydrolyze substantially all of the hemicellulose and greater than 45% of the cellulose to water soluble sugars; and recovering the water soluble sugars.

  8. Tanzania wildcats to evaluate Jurassic Mandawa salt basin

    SciTech Connect (OSTI)

    Nagati, M.

    1996-10-07

    After 5 years of stagnant exploration in East Africa, Canadian independent Tanganyika Oil Co. of Vancouver, B.C., will drill two wildcats in Tanzania to evaluate the hydrocarbon potential of the coastal Jurassic Mandawa salt basin. Mita-1, spudded around Oct. 1, will be drilled to about 7,000 ft, East Lika-1 will be drilled in early December 1996 to approximately 6,000 ft. The two wells will test different structures and play concepts. The paper describes the exploration history, source rock potential, hydrocarbon shows, potential reservoir, and the prospects.

  9. Method of preparing sodalite from chloride salt occluded zeolite

    DOE Patents [OSTI]

    Lewis, Michele A.; Pereira, Candido

    1997-01-01

    A method for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistant sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1000.degree. K. to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density.

  10. Method of preparing sodalite from chloride salt occluded zeolite

    DOE Patents [OSTI]

    Lewis, M.A.; Pereira, C.

    1997-03-18

    A method is described for immobilizing waste chloride salts containing radionuclides and hazardous nuclear material for permanent disposal starting with a substantially dry zeolite and sufficient glass to form leach resistant sodalite with occluded radionuclides and hazardous nuclear material. The zeolite and glass are heated to a temperature up to about 1000 K to convert the zeolite to sodalite and thereafter maintained at a pressure and temperature sufficient to form a sodalite product near theoretical density. Pressure is used on the formed sodalite to produce the required density.

  11. Characterization of bedded salt for storage caverns -- A case study from the Midland Basin, Texas

    SciTech Connect (OSTI)

    Hovorka, Susan D.; Nava, Robin

    2000-06-13

    The geometry of Permian bedding salt in the Midland Basin is a product of interaction between depositional facies and postdepositional modification by salt dissolution. Mapping high-frequency cycle patterns in cross section and map view using wireline logs documents the salt geometry. Geologically based interpretation of depositional and dissolution processes provides a powerful tool for mapping and geometry of salt to assess the suitability of sites for development of solution-mined storage caverns. In addition, this process-based description of salt geometry complements existing data about the evolution of one of the best-known sedimentary basins in the world, and can serve as a genetic model to assist in interpreting other salts.

  12. Advanced Thermal Storage System with Novel Molten Salt: December 8, 2011 - April 30, 2013

    SciTech Connect (OSTI)

    Jonemann, M.

    2013-05-01

    Final technical progress report of Halotechnics Subcontract No. NEU-2-11979-01. Halotechnics has demonstrated an advanced thermal energy storage system with a novel molten salt operating at 700 degrees C. The molten salt and storage system will enable the use of advanced power cycles such as supercritical steam and supercritical carbon dioxide in next generation CSP plants. The salt consists of low cost, earth abundant materials.

  13. Accident Investigation of the February 5, 2014, Underground Salt Haul Truck

    Energy Savers [EERE]

    Fire at the Waste Isolation Pilot Plant, Carlsbad NM | Department of Energy 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM March 26, 2014 Accident Investigation of the February 5, 2014, Underground Salt Haul Truck Fire at the Waste Isolation Pilot Plant, Carlsbad NM The U.S. Department of Energy (DOE) Accident Prevention

  14. Accelerator-driven subcritical fission in molten salt core: Closing the

    Office of Scientific and Technical Information (OSTI)

    nuclear fuel cycle for green nuclear energy (Journal Article) | SciTech Connect Accelerator-driven subcritical fission in molten salt core: Closing the nuclear fuel cycle for green nuclear energy Citation Details In-Document Search Title: Accelerator-driven subcritical fission in molten salt core: Closing the nuclear fuel cycle for green nuclear energy A technology for accelerator-driven subcritical fission in a molten salt core (ADSMS) is being developed as a basis for the destruction of

  15. Salt Waste Disposal at the Savannah River Site | Department of Energy

    Energy Savers [EERE]

    Salt Waste Disposal at the Savannah River Site Salt Waste Disposal at the Savannah River Site Section 3116 of the Ronald W. Reagan National Defense Authorization Act for Fiscal Year 2005 authorizes the Secretary of Energy, in consultation with the Nuclear Regulatory Commission, to reclassify certain waste from reprocessing spent nuclear fuel from high-level waste to low-level waste if it meets the criteria set forth in Section 3116. Currently, DOE SRS has prepared one final (salt waste) and is

  16. Effect of hydrotropic salts on phase relationships involving hydrocarbons, water, and alcohols

    SciTech Connect (OSTI)

    Ho, P.C.; Kraus, K.A.

    1980-01-01

    Hydrotropic salts, which can increase the solubility of organic materials in aqueous solutions, are useful to tertiary oil recovery. We have examined effects on solubility of hydrocarbons in water (with and without alcohols) through addition of inorganic hydrotropic salts, such as perchlorates, thiocyanates, and iodides - high in the usual Hofmeister series - and of organic salts such as short chain alkyl benzene sulfonates and other salts based on substituted benzene derivatives. Although the inorganic salts are relatively ineffective in increasing solubility of hydrocarbons in water, many of the organic salts are excellent hydrotropic agents for hydrocarbons. We have examined the phase relationships for several series of aromatic salts such as sulfonates, carboxylates and hydroxycarboxylates, as a function of alkyl-carbon substitution in three-component (hydrocarbon, salt, water) and in four-component (hydrocarbon, salt, alcohol, water) systems. We have also examined miscibility relationships for a given hydrotropic salt as the chain length of alkanes and alkyl benzenes is systematically varied. While miscibilities decrease with increase in chain length of the hydrocarbon, the hydrotropic properties in these systems increase rapidly with the number of alkyl carbons on the benzene ring of the salts and they are relatively insensitive to the type of charged group (sulfonate vs carboxylate) attached to the benzene ring. However, there were significant increases in hydrotropy as one goes from equally substituted sulfonates or carboxylates to salicylates. A number of salts have been identified which have much greater hydrotropic properties for hydrocarbons than such well-known hydrotropic materials as toluene and xylene sulfonates.

  17. Method for immobilizing mixed waste chloride salts containing radionuclides and other hazardous wastes

    DOE Patents [OSTI]

    Lewis, Michele A.; Johnson, Terry R.

    1993-09-07

    The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.

  18. Maintaining molten salt electrolyte concentration in aluminum-producing electrolytic cell

    DOE Patents [OSTI]

    Barnett, Robert J.; Mezner, Michael B.; Bradford, Donald R

    2005-01-04

    A method of maintaining molten salt concentration in a low temperature electrolytic cell used for production of aluminum from alumina dissolved in a molten salt electrolyte contained in a cell free of frozen crust wherein volatile material is vented from the cell and contacted and captured on alumina being added to the cell. The captured volatile material is returned with alumina to cell to maintain the concentration of the molten salt.

  19. Method for immobilizing mixed waste chloride salts containing radionuclides and other hazardous wastes

    DOE Patents [OSTI]

    Lewis, Michele A. (Naperville, IL); Johnson, Terry R. (Wheaton, IL)

    1993-01-01

    The invention is a method for the encapsulation of soluble radioactive waste chloride salts containing radionuclides such as strontium, cesium and hazardous wastes such as barium so that they may be permanently stored without future threat to the environment. The process consists of contacting the salts containing the radionuclides and hazardous wastes with certain zeolites which have been found to ion exchange with the radionuclides and to occlude the chloride salts so that the resulting product is leach resistant.

  20. Biochemical solubilization of toxic salts from residual geothermal brines and waste waters

    DOE Patents [OSTI]

    Premuzic, Eugene T.; Lin, Mow S.

    1994-11-22

    A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed, The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts, For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates.

  1. Biochemical solubilization of toxic salts from residual geothermal brines and waste waters

    DOE Patents [OSTI]

    Premuzic, E.T.; Lin, M.S.

    1994-11-22

    A method of solubilizing metal salts such as metal sulfides in a geothermal sludge using mutant Thiobacilli selected for their ability to metabolize metal salts at high temperature is disclosed. The method includes the introduction of mutated Thiobacillus ferrooxidans and Thiobacillus thiooxidans to a geothermal sludge or brine. The microorganisms catalyze the solubilization of metal salts. For instance, in the case of metal sulfides, the microorganisms catalyze the solubilization to form soluble metal sulfates. 54 figs.

  2. Pebble Fuel Handling and Reactivity Control for Salt-Cooled High

    Office of Scientific and Technical Information (OSTI)

    Temperature Reactors (Technical Report) | SciTech Connect Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors Citation Details In-Document Search Title: Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors This report documents the work completed on the X-PREX facility under NEUP Project 11- 3172. This project seeks to demonstrate the viability of pebble fuel handling and reactivity control for fluoride salt-cooled

  3. Memo - Legacy Technical Area (TA)-55 Nitrate Salt Wastes at TA...

    Office of Environmental Management (EM)

    on February 14, 2014, report in Attachment F. Bibliography and References, are available on various public websites. PDF icon Memo - Legacy Technical Area (TA)-55 Nitrate Salt ...

  4. US/German Workshop on Salt Repository Research, Design and Operation...

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

    following information: We have obtained the necessary DOE and Sandia approvals to start planning the 7 th USGerman Workshop on Salt Repository Research, Design, and Operation to...

  5. Hazard evaluation for cutting tank 241-A-101 salt well casing

    SciTech Connect (OSTI)

    Board, B.D.

    1997-01-10

    This document identifies the hazards of using an abrasive water jet to add perforations to the salt well screen in tank 241-A-101.

  6. Case studies of sealing methods and materials used in the salt...

    Office of Scientific and Technical Information (OSTI)

    Industrial experience, as determined from site visits and literature reviews, provides few examples of bulkheads built in salt and potash mines for control of water. Sealing ...

  7. Process for improving the energy density of feedstocks using formate salts

    DOE Patents [OSTI]

    Wheeler, Marshall Clayton; van Heiningen, Adriaan R.P.; Case, Paige A.

    2015-09-01

    Methods of forming liquid hydrocarbons through thermal deoxygenation of cellulosic compounds are disclosed. Aspects cover methods including the steps of mixing a levulinic acid salt-containing feedstock with a formic acid salt, exposing the mixture to a high temperature condition to form hydrocarbon vapor, and condensing the hydrocarbon vapor to form liquid hydrocarbons, where both the formic acid salt and the levulinic acid salt-containing feedstock decompose at the high temperature condition and wherein one or more of the mixing, exposing, and condensing steps is carried out a pressure between about vacuum and about 10 bar.

  8. ,"U.S. Natural Gas Salt Underground Storage Activity-Withdraw...

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

    ...dnavnghistn5450us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Withdraw (MMcf)" ...

  9. ,"U.S. Natural Gas Salt Underground Storage Activity-Net (MMcf...

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

    ...dnavnghistn5460us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Net (MMcf)" ...

  10. ,"U.S. Natural Gas Salt Underground Storage Activity-Injects...

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

    ...dnavnghistn5440us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Injects (MMcf)" ...

  11. ,"U.S. Natural Gas Non-Salt Underground Storage - Working Gas...

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

    Natural Gas Non-Salt Underground Storage - Working Gas (MMcf)",1,"Monthly","2...dnavnghistn5510us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ...

  12. ,"U.S. Natural Gas Salt Underground Storage Activity-Net (MMcf...

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

    ...dnavnghistn5460us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Net (MMcf)" ...

  13. ,"U.S. Natural Gas Salt Underground Storage Activity-Injects...

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

    ...dnavnghistn5440us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Injects (MMcf)" ...

  14. ,"U.S. Natural Gas Non-Salt Underground Storage - Base Gas ...

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

    Natural Gas Non-Salt Underground Storage - Base Gas (MMcf)",1,"Monthly","22016" ...dnavnghistn5500us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ...

  15. ,"U.S. Natural Gas Salt Underground Storage Activity-Withdraw...

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

    ...dnavnghistn5450us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Salt Underground Storage Activity-Withdraw (MMcf)" ...

  16. Project Profile: Deep Eutectic Salt Formulations Suitable as Advanced Heat Transfer Fluids

    Broader source: Energy.gov [DOE]

    Halotechnics, under the Thermal Storage FOA, is conducting high-throughput, combinatorial research and development of salt formulations for use as highly efficient heat transfer fluids (HTFs).

  17. Proceedings of 3rd US/German Workshop on Salt Repository Research, Design, and Operation

    Broader source: Energy.gov [DOE]

    The report provides summary and materials from the third U.S./German Workshop on Salt Repository Research, Design and Operation (held in New Mexico, October 2012).

  18. Single-Well and Cross-Well Seismic At Salt Wells Area (Bureau...

    Open Energy Info (EERE)

    Seismic At Salt Wells Area (Bureau of Land Management, 2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Single-Well and Cross-Well Seismic...

  19. Method of removal of heavy metal from molten salt in IFR fuel pyroprocessing

    DOE Patents [OSTI]

    Gay, Eddie C.

    1995-01-01

    An electrochemical method of separating heavy metal values from a radioactive molten salt including Li halide at temperatures of about 500.degree. C. The method comprises positioning a solid Li--Cd alloy anode in the molten salt containing the heavy metal values, positioning a Cd-containing cathode or a solid cathode positioned above a catch crucible in the molten salt to recover the heavy metal values, establishing a voltage drop between the anode and the cathode to deposit material at the cathode to reduce the concentration of heavy metals in the salt, and controlling the deposition rate at the cathode by controlling the current between the anode and cathode.

  20. Coupled Model for Heat and Water Transport in a High Level Waste Repository in Salt

    Broader source: Energy.gov [DOE]

    This report summarizes efforts to simulate coupled thermal-hydrological-chemical (THC) processes occurring within a generic hypothetical high-level waste (HLW) repository in bedded salt.

  1. Microsoft Word - DisposalInSaltDifferentThanDisposalInWIPP.doc

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

    that have atomic numbers greater than uranium. An article in the August 2009 issue of Scientific American contained discussion about the use of salt formations for disposal of...

  2. 2-M Probe At Columbus Salt Marsh Area (Kratt, Et Al., 2010) ...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: 2-M Probe At Columbus Salt Marsh Area (Kratt, Et Al., 2010) Exploration Activity Details...

  3. Ground Gravity Survey At Salt Wells Area (Bureau of Land Management...

    Open Energy Info (EERE)

    2009) Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Ground Gravity Survey At Salt Wells Area (Bureau of Land Management, 2009) Exploration...

  4. Neutrinoless Double Beta Decay in Light of SNO Salt Data (Journal...

    Office of Scientific and Technical Information (OSTI)

    In the SNO data from its salt run, probably the most significant result is the consistency ... Country of Publication: United States Language: English Subject: 72; BETA DECAY; ...

  5. Water Sampling At Salt Wells Area (Henkle, Et Al., 2005) | Open...

    Open Energy Info (EERE)

    Jump to: navigation, search GEOTHERMAL ENERGYGeothermal Home Exploration Activity: Water Sampling At Salt Wells Area (Henkle, Et Al., 2005) Exploration Activity Details...

  6. QER SECOND INSTALLMENT REGIONAL MEETING--SALT LAKE CITY, UT | Department of

    Office of Environmental Management (EM)

    Energy SALT LAKE CITY, UT QER SECOND INSTALLMENT REGIONAL MEETING--SALT LAKE CITY, UT MEETING DATE AND LOCATION Monday, April 25, 2016 Doors open: 8:00 AM; Program begins: 8:30 AM Western Electricity Coordinating Council 155 North 400 West, Suite 200 Salt Lake City, UT 84103 Watch the April 25th Salt Lake City regional meeting here. MEETING INFORMATION The Quadrennial Energy Review Task Force will host a public stakeholder meeting on the second installment of the Quadrennial Energy Review

  7. Pebble Fuel Handling and Reactivity Control for Salt-Cooled High...

    Office of Scientific and Technical Information (OSTI)

    Pebble Fuel Handling and Reactivity Control for Salt-Cooled High Temperature Reactors Citation Details In-Document Search Title: Pebble Fuel Handling and Reactivity Control for ...

  8. Salt Repository Project shaft design guide: Revision 0

    SciTech Connect (OSTI)

    Not Available

    1987-12-01

    The Salt Repository Project (SRP) Shaft Design Guide (SDG) and the accompanying SRP Input to Seismic Design define the basic approach for developing appropriate shaft designs for a high-level nuclear waste repository in salt at a proposed site in Deaf Smith County, Texas. The SDG is based on current mining industry standards and practices enhanced to meet the special needs of an underground nuclear waste repository. It provides a common approach for design of both the exploratory and repository shafts. The SDG defines shaft lining and material concepts and presents methods for calculating the loads and displacements that will be imposed on lining structures. It also presents the methodology and formulae for sizing lining components. The SDG directs the shaft designer to sources of geoscience and seismic design data for the Deaf Smith County, Texas repository site. In addition, the SDG describes methods for confirming shaft lining design by means of computer analysis, and it discusses performance monitoring needs that must be considered in the design. 113 refs., 18 figs., 14 tabs.

  9. Subsidence at Boling salt dome: results of multiple resource production

    SciTech Connect (OSTI)

    Mullican, W.F. III

    1988-02-01

    Boling dome (Wharton and Fort Bend Counties) has experienced more overall subsidence and collapse than any other dome in Texas. These processes are directly related to production of sulfur and hydrocarbons from the southeastern quadrant of the dome. Greatest vertical movement due to subsidence and collapse is 35 ft (based on the Boling 7.5 min topographic map, last surveyed in 1953). Most of the subsidence (83%) is attributed to sulfur production, whereas only 11 to 12% can be linked to hydrocarbon production. Reservoir compaction is the dominant mechanism of land subsidence in areas of hydrocarbon production at Boling dome. Trough subsidence, chimneying, plug caving, and piping are the characteristic mechanisms over sulfur fields developed at the salt dome. The structural and hydrologic stability of the surface and subsurface at Boling dome is compromised by these active deformation processes. Damage to pipelines and well-casing strings may result in costly leaks which have the potential of being uncontrollable and catastrophic. Reduction in hydrologic stability may result if natural aquitards are breached and fresh water mixes with saline water or if hydrologic conduits to the diapir are opened, allowing unrestricted dissolution of the salt stock.

  10. Radiolytic gas generation in salt cake technical task plan

    SciTech Connect (OSTI)

    Walker, D.D.; Crawford, C.L.; Bibler, N.E.

    1993-08-29

    High-level radioactive wastes are stored in large, steel tanks in the Savannah River Site Tank Farms. The liquid levels in these tanks are monitored to detect leakage of waste out of tanks or leakage of liquids into the tanks. Recent unexplained level fluctuations in high-level waste (HLW) tanks have caused High Level Waste Engineering (HLWE) to develop a program to better understand tank level behavior. Interim Waste Technology (IWT) has been requested by HLWE to obtain data which will lead to a better understanding of the radiolytic generations of gases in salt cake. The task described below will provide data from laboratory experiments with simulated wastes which can be used in tank level fluctuation modeling. The following experimental programs have been formulated to meet the task requirements of the customer: (A) determine whether radiolytically generated gas bubbles can be trapped in salt cake; (B) determine the composition of gases produced by radiolysis; (C) determine the yield of radiolysis gases as a function of radiation dose; (D) determine bubble distribution.

  11. Recent advances in the molten salt destruction of energetic materials

    SciTech Connect (OSTI)

    Pruneda, C. O., LLNL

    1996-09-01

    We have demonstrated the use of the Molten Salt Destruction (MSD) Process for destroying explosives, liquid gun propellant, and explosives-contaminated materials on a 1.5 kg of explosive/hr bench- scale unit (1, 2, 3, 4, 5). In our recently constructed 5 kg/hr pilot- scale unit we have also demonstrated the destruction of a liquid gun propellant and simulated wastes containing HMX (octogen). MSD converts the organic constituents of the waste into non-hazardous substances such as carbon dioxide, nitrogen, and water. Any inorganic constituents of the waste, such as metallic particles, are retained in the molten salt. The destruction of energetic materials waste is accomplished by introducing it, together with air, into a vessel containing molten salt (a eutectic mixture of sodium, potassium, and lithium carbonates). The following pure explosives have been destroyed in our bench-scale experimental unit located at Lawrence Livermore National Laboratory`s (LLNL) High Explosives Applications Facility (HEAF): ammonium picrate, HMX, K- 6 (keto-RDX), NQ, NTO, PETN, RDX, TATB, and TNT. In addition, the following compositions were also destroyed: Comp B, LX- IO, LX- 1 6, LX- 17, PBX-9404, and XM46 (liquid gun propellant). In this 1.5 kg/hr bench-scale unit, the fractions of carbon converted to CO and of chemically bound nitrogen converted to NO{sub x} were found to be well below 1%. In addition to destroying explosive powders and compositions we have also destroyed materials that are typical of residues which result from explosives operations. These include shavings from machined pressed parts of plastic-bonded explosives and sump waste containing both explosives and non-explosive debris. Based on the process data obtained on the bench-scale unit we designed and constructed a next-generation 5 kg/hr pilot-scale unit, incorporating LLNL`s advanced chimney design. The pilot unit has completed process implementation operations and explosives safety reviews. To date, in this pilot unit we have successfully destroyed liquid gun propellant and dimethylsulfoxide containing HMX in continuous, long-duration runs.

  12. Salt Lake Community College | OSTI, US Dept of Energy, Office of Scientific

    Office of Scientific and Technical Information (OSTI)

    and Technical Information Salt Lake Community College Spotlights Home DOE Applauds SLCC Science and Technical Programs Salt Lake City, Utah Architectural Technology Biology Biotechnology Biomanufacturing Chemistry Computer Science Electric Sector Training Energy Management Engineering Geographic Information Sciences Geosciences InnovaBio Manufacturing & Mechanical Engineering Technology Mathematics Physics SLCC Partners with DOE's Rocky Mountain Solar Training Program This program is a

  13. Management of Salt Waste from Electrochemical Processing of Used Nuclear Fuel

    SciTech Connect (OSTI)

    Michael F. Simpson; Michael N. Patterson; Joon Lee; Yifeng Wang; Joshua Versey; Ammon Williams; Supathorn Phongikaroon; James Allensworth; Man-Sung Yim

    2013-10-01

    Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electrorefiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form.

  14. Management of salt waste from electrochemical processing of used nuclear fuel

    SciTech Connect (OSTI)

    Simpson, M.F.; Patterson, M.N.; Lee, J.; Wang, Y.; Versey, J.; Phongikaroon, S.

    2013-07-01

    Electrochemical processing of used nuclear fuel involves operation of one or more cells containing molten salt electrolyte. Processing of the fuel results in contamination of the salt via accumulation of fission products and transuranic (TRU) actinides. Upon reaching contamination limits, the salt must be removed and either disposed or treated to remove the contaminants and recycled back to the process. During development of the Experimental Breeder Reactor-II spent fuel treatment process, waste salt from the electro-refiner was to be stabilized in a ceramic waste form and disposed of in a high-level waste repository. With the cancellation of the Yucca Mountain high-level waste repository, other options are now being considered. One approach that involves direct disposal of the salt in a geologic salt formation has been evaluated. While waste forms such as the ceramic provide near-term resistance to corrosion, they may not be necessary to ensure adequate performance of the repository. To improve the feasibility of direct disposal, recycling a substantial fraction of the useful salt back to the process equipment could minimize the volume of the waste. Experiments have been run in which a cold finger is used for this purpose to crystallize LiCl from LiCl/CsCl. If it is found to be unsuitable for transportation, the salt waste could also be immobilized in zeolite without conversion to the ceramic waste form. (authors)

  15. Novel, electrolyte solutions comprising fully inorganic salts with high anodic stability for rechargeable magnesium batteries

    SciTech Connect (OSTI)

    Doe, RE; Han, R; Hwang, J; Gmitter, AJ; Shterenberg, I; Yoo, HD; Pour, N; Aurbach, D

    2014-01-01

    Herein the first inorganic magnesium salt solution capable of highly reversible magnesium electrodeposition is presented. Synthesized by acid-base reaction of MgCl2 and Lewis acidic compounds such as AlCl3, this salt class demonstrates upwards of 99% Coulombic efficiency, deposition overpotential of <200 mV, and anodic stability of 3.1 V.

  16. Overexpression of Late Embryogenesis Abundant 14 enhances Arabidopsis salt stress tolerance

    SciTech Connect (OSTI)

    Jia, Fengjuan Qi, Shengdong Li, Hui Liu, Pu Li, Pengcheng Wu, Changai Zheng, Chengchao Huang, Jinguang

    2014-11-28

    Highlights: It is the first time to investigate the biological function of AtLEA14 in salt stress response. AtLEA14 enhances the salt stress tolerance both in Arabidopsis and yeast. AtLEA14 responses to salt stress by stabilizing AtPP2-B11, an E3 ligase, under normal or salt stress conditions. - Abstract: Late embryogenesis abundant (LEA) proteins are implicated in various abiotic stresses in higher plants. In this study, we identified a LEA protein from Arabidopsis thaliana, AtLEA14, which was ubiquitously expressed in different tissues and remarkably induced with increased duration of salt treatment. Subcellular distribution analysis demonstrated that AtLEA14 was mainly localized in the cytoplasm. Transgenic Arabidopsis and yeast overexpressing AtLEA14 all exhibited enhanced tolerance to high salinity. The transcripts of salt stress-responsive marker genes (COR15a, KIN1, RD29B and ERD10) were overactivated in AtLEA14 overexpressing lines compared with those in wild type plants under normal or salt stress conditions. In vivo and in vitro analysis showed that AtLEA14 could effectively stabilize AtPP2-B11, an important E3 ligase. These results suggested that AtLEA14 had important protective functions under salt stress conditions in Arabidopsis.

  17. Molecular dynamics simulations of the effects of salts on the aggregation properties of benzene in water.

    SciTech Connect (OSTI)

    Smith, P. E.

    2003-07-16

    The specific aims of the project were: to provide an atomic level description of the interactions between benzene, water and ions in solutions. To determine the degree of association between two benzene molecules in aqueous and salt solutions. To investigate the structure and dynamics of the interface between benzene and water or salt solution.

  18. Project Profile: Modular and Scalable Baseload Molten Salt Plant Conceptual Design and Feasibility

    Broader source: Energy.gov [DOE]

    eSolar, under the Baseload CSP FOA, is designing a 100-MW, 75% capacity factor, molten salt power tower plant, based around a molten salt receiver and heliostat field module with a nominal thermal rating of 50 MWth. They are taking a modular approach, which can be scaled through replication of the receiver/field module to meet output and capacity factor requirements.

  19. Pyrolytic conversion of plastic and rubber waste to hydrocarbons with basic salt catalysts

    DOE Patents [OSTI]

    Wingfield, Jr., Robert C.; Braslaw, Jacob; Gealer, Roy L.

    1985-01-01

    The invention relates to a process for improving the pyrolytic conversion of waste selected from rubber and plastic to low molecular weight olefinic materials by employing basis salt catalysts in the waste mixture. The salts comprise alkali or alkaline earth compounds, particularly sodium carbonate, in an amount of greater than about 1 weight percent based on the waste feed.

  20. STORAGE OF CHILLED NATURAL GAS IN BEDDED SALT STORAGE CAVERNS

    SciTech Connect (OSTI)

    JOel D. Dieland; Kirby D. Mellegard

    2001-11-01

    This report provides the results of a two-phase study that examines the economic and technical feasibility of converting a conventional natural gas storage facility in bedded salt into a refrigerated natural gas storage facility for the purpose of increasing the working gas capacity of the facility. The conceptual design used to evaluate this conversion is based on the design that was developed for the planned Avoca facility in Steuben County, New York. By decreasing the cavern storage temperature from 43 C to -29 C (110 F to -20 F), the working gas capacity of the facility can be increased by about 70 percent (from 1.2 x 10{sup 8} Nm{sup 3} or 4.4 billion cubic feet (Bcf) to 2.0 x 10{sup 8} Nm{sup 3} or 7.5 Bcf) while maintaining the original design minimum and maximum cavern pressures. In Phase I of the study, laboratory tests were conducted to determine the thermal conductivity of salt at low temperatures. Finite element heat transfer calculations were then made to determine the refrigeration loads required to maintain the caverns at a temperature of -29 C (-20 F). This was followed by a preliminary equipment design and a cost analysis for the converted facility. The capital cost of additional equipment and its installation required for refrigerated storage is estimated to be about $13,310,000 or $160 per thousand Nm{sup 3} ($4.29 per thousand cubic feet (Mcf)) of additional working gas capacity. The additional operating costs include maintenance refrigeration costs to maintain the cavern at -29 C (-20 F) and processing costs to condition the gas during injection and withdrawal. The maintenance refrigeration cost, based on the current energy cost of about $13.65 per megawatt-hour (MW-hr) ($4 per million British thermal units (MMBtu)), is expected to be about $316,000 after the first year and to decrease as the rock surrounding the cavern is cooled. After 10 years, the cost of maintenance refrigeration based on the $13.65 per MW-hr ($4 per MMBtu) energy cost is estimated to be $132,000. The gas processing costs are estimated to be $2.05 per thousand Nm{sup 3} ($0.055 per Mcf) of gas injected into and withdrawn from the facility based on the $13.65 per MW-hr ($4 per MMBtu) energy cost. In Phase II of the study, laboratory tests were conducted to determine mechanical properties of salt at low temperature. This was followed by thermomechanical finite element simulations to evaluate the structural stability of the cavern during refrigerated storage. The high thermal expansion coefficient of salt is expected to result in tensile stresses leading to tensile failure in the roof, walls, and floor of the cavern as it is cooled. Tensile fracturing of the cavern roof may result in loss of containment of the gas and/or loss of integrity of the casing shoe, deeming the conversion of this facility not technically feasible.

  1. Expedited demonstration of molten salt mixed waste treatment technology. Final report

    SciTech Connect (OSTI)

    1995-02-02

    This final report discusses the molten salt mixed waste project in terms of the various subtasks established. Subtask 1: Carbon monoxide emissions; Establish a salt recycle schedule and/or a strategy for off-gas control for MWMF that keeps carbon monoxide emission below 100 ppm on an hourly averaged basis. Subtask 2: Salt melt viscosity; Experiments are conducted to determine salt viscosity as a function of ash composition, ash concentration, temperature, and time. Subtask 3: Determine that the amount of sodium carbonate entrained in the off-gas is minimal, and that any deposited salt can easily be removed form the piping using a soot blower or other means. Subtask 4: The provision of at least one final waste form that meets the waste acceptance criteria of a landfill that will take the waste. This report discusses the progress made in each of these areas.

  2. Disposal of oil field wastes into salt caverns: Feasibility, legality, risk, and costs

    SciTech Connect (OSTI)

    Veil, J.A.

    1997-10-01

    Salt caverns can be formed through solution mining in the bedded or domal salt formations that are found in many states. Salt caverns have traditionally been used for hydrocarbon storage, but caverns have also been used to dispose of some types of wastes. This paper provides an overview of several years of research by Argonne National Laboratory on the feasibility and legality of using salt caverns for disposing of oil field wastes, the risks to human populations from this disposal method, and the cost of cavern disposal. Costs are compared between the four operating US disposal caverns and other commercial disposal options located in the same geographic area as the caverns. Argonne`s research indicates that disposal of oil field wastes into salt caverns is feasible and legal. The risk from cavern disposal of oil field wastes appears to be below accepted safe risk thresholds. Disposal caverns are economically competitive with other disposal options.

  3. Preliminary analyses of scenarios for potential human interference for repositories in three salt formations

    SciTech Connect (OSTI)

    Not Available

    1985-10-01

    Preliminary analyses of scenarios for human interference with the performance of a radioactive waste repository in a deep salt formation are presented. The following scenarios are analyzed: (1) the U-Tube Connection Scenario involving multiple connections between the repository and the overlying aquifer system; (2) the Single Borehole Intrusion Scenario involving penetration of the repository by an exploratory borehole that simultaneously connects the repository with overlying and underlying aquifers; and (3) the Pressure Release Scenario involving inflow of water to saturate any void space in the repository prior to creep closure with subsequent release under near lithostatic pressures following creep closure. The methodology to evaluate repository performance in these scenarios is described and this methodology is applied to reference systems in three candidate formations: bedded salt in the Palo Duro Basin, Texas; bedded salt in the Paradox Basin, Utah; and the Richton Salt Dome, Mississippi, of the Gulf Coast Salt Dome Basin.

  4. Method to synthesize dense crystallized sodalite pellet for immobilizing halide salt radioactive waste

    DOE Patents [OSTI]

    Koyama, Tadafumi

    1994-01-01

    A method for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities.

  5. Method to synthesize dense crystallized sodalite pellet for immobilizing halide salt radioactive waste

    DOE Patents [OSTI]

    Koyama, T.

    1992-01-01

    This report describes a method for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities.

  6. Method to synthesize dense crystallized sodalite pellet for immobilizing halide salt radioactive waste

    DOE Patents [OSTI]

    Koyama, Tadafumi.

    1994-08-23

    A method is described for immobilizing waste chloride salts containing radionuclides such as cesium and strontium and hazardous materials such as barium. A sodalite intermediate is prepared by mixing appropriate amounts of silica, alumina and sodium hydroxide with respect to sodalite and heating the mixture to form the sodalite intermediate and water. Heating is continued to drive off the water to form a water-free intermediate. The water-free intermediate is mixed with either waste salt or waste salt which has been contacted with zeolite to concentrate the radionuclides and hazardous material. The waste salt-intermediate mixture is then compacted and heated under conditions of heat and pressure to form sodalite with the waste salt, radionuclides and hazardous material trapped within the sodalite cage structure. This provides a final product having excellent leach resistant capabilities.

  7. A method for making dendritic metal nanostructures using a surfactant structure template, a metal salt, and electron donor species.

    DOE Patents [OSTI]

    Shelnutt, John A.; Song, Yujiang; Pereira, Eulalia F.; Medforth, Craig J.

    2008-05-20

    A method for making dendritic metal nanostructures using a surfactant structure template, a metal salt, and electron donor species.

  8. Geomechanical Analysis and Design Considerations for Thin-Bedded Salt Caverns

    SciTech Connect (OSTI)

    Michael S. Bruno

    2005-06-15

    The bedded salt formations located throughout the United States are layered and interspersed with non-salt materials such as anhydrite, shale, dolomite and limestone. The salt layers often contain significant impurities. GRI and DOE have initialized this research proposal in order to increase the gas storage capabilities by providing operators with improved geotechnical design and operating guidelines for thin bedded salt caverns. Terralog has summarized the geologic conditions, pressure conditions, and critical design factors that may lead to: (1) Fracture in heterogeneous materials; (2) Differential deformation and bedding plane slip; (3) Propagation of damage around single and multiple cavern; and (4) Improved design recommendations for single and multiple cavern configurations in various bedded salt environments. The existing caverns within both the Permian Basin Complex and the Michigan and Appalachian Basins are normally found between 300 m to 1,000 m (1,000 ft to 3,300 ft) depth depending on local geology and salt dissolution depth. Currently, active cavern operations are found in the Midland and Anadarko Basins within the Permian Basin Complex and in the Appalachian and Michigan Basins. The Palo Duro and Delaware Basins within the Permian Basin Complex also offer salt cavern development potential. Terralog developed a number of numerical models for caverns located in thin bedded salt. A modified creep viscoplastic model has been developed and implemented in Flac3D to simulate the response of salt at the Permian, Michigan and Appalachian Basins. The formulation of the viscoplastic salt model, which is based on an empirical creep law developed for Waste Isolation Pilot Plant (WIPP) Program, is combined with the Drucker-Prager model to include the formation of damage and failure. The Permian salt lab test data provided by Pfeifle et al. 1983, are used to validate the assumptions made in the material model development. For the actual cavern simulations two baseline models are developed for single and multiple caverns, respectively. Different parameters that affect damage propagation and deformation of salt cavern, such as cavern pressure, operating conditions, cavern height/diameter ratio, overburden stiffness and roof thickness are analyzed and the respective results summarized. For multiple horizontal caverns numerical models are developed to determine the cavern interaction and the minimum safe center to center distance. A step by step methodology for operators to assess critical cavern design parameters for thin bedded salt formations is also presented.

  9. Nuclear Hybrid Energy System: Molten Salt Energy Storage (Summer Report 2013)

    SciTech Connect (OSTI)

    Piyush Sabharwall; Michael George mckellar; Su-Jong Yoon

    2013-11-01

    Effective energy use is a main focus and concern in the world today because of the growing demand for energy. The nuclear hybrid energy system (NHES) is a valuable technical concept that can potentially diversify and leverage existing energy technologies. This report considers a particular NHES design that combines multiple energy systems including a nuclear reactor, energy storage system (ESS), variable renewable generator (VRG), and additional process heat applications. Energy storage is an essential component of this particular NHES because its design allows the system to produce peak power while the nuclear reactor operates at constant power output. Many energy storage options are available, but this study mainly focuses on a molten salt ESS. The primary purpose of the molten salt ESS is to enable the nuclear reactor to be a purely constant heat source by acting as a heat storage component for the reactor during times of low demand, and providing additional capacity for thermo-electric power generation during times of peak electricity demand. This report will describe the rationale behind using a molten salt ESS and identify an efficient molten salt ESS configuration that may be used in load following power applications. Several criteria are considered for effective energy storage and are used to identify the most effective ESS within the NHES. Different types of energy storage are briefly described with their advantages and disadvantages. The general analysis to determine the most efficient molten salt ESS involves two parts: thermodynamic, in which energetic and exergetic efficiencies are considered; and economic. Within the molten salt ESS, the two-part analysis covers three major system elements: molten salt ESS designs (two tank direct and thermocline), the molten salt choice, and the different power cycles coupled with the molten salt ESS. Analysis models are formulated and analyzed to determine the most effective ESS. The results show that the most efficient idealized energy storage system is the two tank direct molten salt ESS with an Air Brayton combined cycle using LiF-NaF-KF as the molten salt, and the most economical is the same design with KCl MgCl2 as the molten salt. With energy production being a major worldwide industry, understanding the most efficient molten salt ESS boosts development of an effective NHES with cheap, clean, and steady power.

  10. Physiological and molecular characterization of the enhanced salt tolerance induced by low-dose gamma irradiation in Arabidopsis seedlings

    SciTech Connect (OSTI)

    Qi, Wencai; Zhang, Liang; Xu, Hangbo; Wang, Lin; Jiao, Zhen

    2014-07-25

    Highlights: 50-Gy gamma irradiation markedly promotes the seedling growth under salt stress in Arabidopsis. The contents of H{sub 2}O{sub 2} and MDA are obviously reduced by low-dose gamma irradiation under salt stress. Low-dose gamma irradiation stimulates the activities of antioxidant enzymes under salt stress. Proline accumulation is required for the low-gamma-ray-induced salt tolerance. Low gamma rays differentially regulate the expression of genes related to salt stress. - Abstract: It has been established that gamma rays at low doses stimulate the tolerance to salt stress in plants. However, our knowledge regarding the molecular mechanism underlying the enhanced salt tolerance remains limited. In this study, we found that 50-Gy gamma irradiation presented maximal beneficial effects on germination index and root length in response to salt stress in Arabidopsis seedlings. The contents of H{sub 2}O{sub 2} and MDA in irradiated seedlings under salt stress were significantly lower than those of controls. The activities of antioxidant enzymes and proline levels in the irradiated seedlings were markedly increased compared with the controls. Furthermore, transcriptional expression analysis of selected genes revealed that some components of salt stress signaling pathways were stimulated by low-dose gamma irradiation under salt stress. Our results suggest that gamma irradiation at low doses alleviates the salt stress probably by modulating the physiological responses as well as stimulating the stress signal transduction in Arabidopsis seedlings.

  11. ANALYSIS OF THE SALT FEED TANK CORE SAMPLE

    SciTech Connect (OSTI)

    Reigel, M.; Cheng, W.

    2012-01-26

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

  12. FINAL REPORT INTEGRATED DM1200 MELTER TESTING USING AZ 102 AND C 106/AY-102 HLW SIMULANTS: HLW SIMULANT VERIFICATION VSL-05R5800-1 REV 0 6/27/05

    SciTech Connect (OSTI)

    KRUGER AA; MATLACK KS; GONG W; BARDAKCI T; D'ANGELO NA; BRANDYS M; KOT WK; PEGG IL

    2011-12-29

    The principal objectives of the DM1200 melter tests were to determine the effects of feed rheology, feed solid content, and bubbler configuration on glass production rate and off-gas system performance while processing the HLW AZ-101 and C-106/AY-102 feed compositions; characterize melter off-gas emissions; characterize the performance of the prototypical off-gas system components, as well as their integrated performance; characterize the feed, glass product, and off-gas effluents; and perform pre- and post test inspections of system components. The specific objectives (including test success criteria) of this testing, along with how each objective was met, are outlined in a table. The data provided in this Final Report address the impacts of HLW melter feed rheology on melter throughput and validation of the simulated HLW melter feeds. The primary purpose of this testing is to further validate/verify the HLW melter simulants that have been used for previous melter testing and to support their continued use in developing melter and off-gas related processing information for the Project. The primary simulant property in question is rheology. Simulants and melter feeds used in all previous melter tests were produced by direct addition of chemicals; these feed tend to be less viscous than rheological the upper-bound feeds made from actual wastes. Data provided here compare melter processing for the melter feed used in all previous DM100 and DM1200 tests (nominal melter feed) with feed adjusted by the feed vendor (NOAH Technologies) to be more viscous, thereby simulating more closely the upperbounding feed produced from actual waste. This report provides results of tests that are described in the Test Plan for this work. The Test Plan is responsive to one of several test objectives covered in the WTP Test Specification for this work; consequently, only part of the scope described in the Test Specification was addressed in this particular Test Plan. For the purpose of comparison, the tests reported here were performed with AZ-102 and C-106/AY-102 HLW simulants and glass compositions that are essentially the same as those used for recent DM1200 tests. One exception was the use of an alternate, higher-waste-loading C-106/AY-102 glass composition that was used in previous DM100 tests to further evaluate the performance of the optimized bubbler configuration.

  13. AN EXPERIMENT TO STUDY PEBBLE BED LIQUID-FLUORIDE-SALT HEAT TRANSFER

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L; Aaron, Adam M; Heatherly, Dennis Wayne; Holcomb, David Eugene; Kisner, Roger A; McCarthy, Mike; Peretz, Fred J; Wilgen, John B; Wilson, Dane F

    2011-01-01

    A forced-convection liquid-fluoride-salt loop is being constructed at Oak Ridge National Laboratory (ORNL). This loop was designed as a versatile experimental facility capable of supporting general thermal/fluid/corrosion testing of liquid fluoride salts. The initial test configuration is designed to support the Pebble Bed Advanced High-Temperature Reactor and incorporates a test section designed to examine the heat transfer behavior of FLiNaK salt in a heated pebble bed. The loop is constructed of Inconel 600 and is capable of operating at up to 700oC. It contains a total of 72 kg of FLiNaK salt and uses an overhung impeller centrifugal sump pump that can provide FLiNaK flow at 4.5 kg/s with a head of 0.125 MPa. The test section is made of silicon carbide (SiC) and contains approximately 600 graphite spheres, 3 cm in diameter. The pebble bed is heated using a unique inductive technique. A forced induction air cooler removes the heat added to the pebble bed. The salt level within the loop is maintained by controlling an argon cover gas pressure. Salt purification is performed in batch mode by transferring the salt from the loop into a specially made nickel crucible system designed to remove oxygen, moisture and other salt impurities. Materials selection for the loop and test section material was informed by 3 months of Inconel 600 and SiC corrosion testing as well as tests examining subcomponent performance in the salt. Several SiC-to-Inconel 600 mechanical joint designs were considered before final salt and gas seals were chosen. Structural calculations of the SiC test section were performed to arrive at a satisfactory test section configuration. Several pump vendors provided potential loop pump designs; however, because of cost, the pump was designed and fabricated in-house. The pump includes a commercial rotating dry gas shaft seal to maintain loop cover gas inventory. The primary instrumentation on the loop includes temperature, pressure, and loop flow rate measurement. Although techniques for all these measurements have improved, no commercial instrumentation was available for flow and pressure measurement that had been tested under these conditions. Instrumentation was tested and modified to meet both corrosion and temperature requirements. This paper discusses the issues encountered during the design and construction of the ORNL Liquid Salt Loop and should prove useful to those contemplating construction of similar high-temperature liquid-fluoride-salt facilities.

  14. Annular core liquid-salt cooled reactor with multiple fuel and blanket

    Office of Scientific and Technical Information (OSTI)

    zones (Patent) | SciTech Connect Patent: Annular core liquid-salt cooled reactor with multiple fuel and blanket zones Citation Details In-Document Search Title: Annular core liquid-salt cooled reactor with multiple fuel and blanket zones A liquid fluoride salt cooled, high temperature reactor having a reactor vessel with a pebble-bed reactor core. The reactor core comprises a pebble injection inlet located at a bottom end of the reactor core and a pebble defueling outlet located at a top end

  15. 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.

  16. 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.

  17. Magneto-hydrodynamic detection of vortex shedding for molten salt flow sensing.

    SciTech Connect (OSTI)

    Kruizenga, Alan Michael; Crocker, Robert W.

    2012-09-01

    High temperature flow sensors must be developed for use with molten salts systems at temperatures in excess of 600%C2%B0C. A novel magneto-hydrodynamic sensing approach was investigated. A prototype sensor was developed and tested in an aqueous sodium chloride solution as a surrogate for molten salt. Despite that the electrical conductivity was a factor of three less than molten salts, it was found that the electrical conductivity of an electrolyte was too low to adequately resolve the signal amidst surrounding noise. This sensor concept is expected to work well with any liquid metal application, as the generated magnetic field scales proportionately with electrical conductivity.

  18. SAMPLE RESULTS FROM THE INTEGRATED SALT DISPOSITION PROGRAM MACROBATCH 5 TANK 21H QUALIFICATION SAMPLES

    SciTech Connect (OSTI)

    Peters, T.; Fink, S.

    2012-03-26

    Savannah River National Laboratory (SRNL) analyzed samples from Tank 21H in support of qualification of Macrobatch (Salt Batch) 5 for the Integrated Salt Disposition Project (ISDP). This document reports partial results of the analyses of samples of Tank 21H. No issues with the projected Salt Batch 5 strategy are identified. Results of the analyses of the Tank 21H samples from this report in conjunction with the findings of the previous report, indicates that the material does not display any unusual characteristics.

  19. Gradient zone-boundary control in salt-gradient solar ponds

    DOE Patents [OSTI]

    Hull, J.R.

    1982-09-29

    A method and apparatus for suppressing zone boundary migration in a salt gradient solar pond includes extending perforated membranes across the pond at the boundaries, between the convective and non-convective zones, the perforations being small enough in size to prevent individual turbulence disturbances from penetrating the hole, but being large enough to allow easy molecular diffusion of salt thereby preventing the formation of convective zones in the gradient layer. The total area of the perforations is a sizeable fraction of the membrane area to allow sufficient salt diffusion while preventing turbulent entrainment into the gradient zone.

  20. Turbidity study of solar ponds utilizing seawater as salt source

    SciTech Connect (OSTI)

    Li, Nan; Sun, Wence; Shi, Yufeng; Yin, Fang; Zhang, Caihong

    2010-02-15

    A series of experiments were conducted to study the turbidity reduction in solar ponds utilizing seawater as salt source. The experiment on the turbidity reduction efficiency with chemicals indicates that alum (KAl(SO{sub 4}){sub 2}.12H{sub 2}O) has a better turbidity control property because of its strongly flocculating and also well depressing the growing of algae and bacteria in the seawater. In comparison with bittern and seawater, our experiment shows that the residual brine after desalination can keep limpidity for a long time even without any chemical in it. Experiments were also conducted on the diffusion of turbidity and salinity, which show that the turbidity did not diffuse upwards in the solution. In the experiment on subsidence of soil in the bittern and saline with the same salinity, it was found that soil subsided quite quickly in the pure saline water, but very slowly in the bittern. In this paper we also proposed an economical method to protect the solar pond from the damage of rain. Finally, thermal performance of a solar pond was simulated in the conditions of different turbidities using a thermal diffusion model. (author)

  1. Respiratory effects of diesel exhaust in salt miners

    SciTech Connect (OSTI)

    Gamble, J.F.; Jones, W.G.

    1983-09-01

    The respiratory health of 259 white males working at 5 salt (NaCl) mines was assessed by questionnaire, chest radiographs, and air and He-O/sup 2/ spirometry. Response variables were symptoms, pneumoconiosis, and spirometry. Predictor variables included age, height, smoking, mine, and tenure in diesel-exposed jobs. The purpose was to assess the association of response measures of respiratory health with exposure to diesel exhaust. There were only 2 cases of Grade 1 pneumoconiosis, so no further analysis was done. Comparisons within the study population showed a statistically significant dose-related association of phlegm and diesel exposure. There was a nonsignificant trend for cough and dyspnea, and no association with spirometry. Age- and smoking-adjusted rates of cough, phlegm, and dyspnea were 145, 159, and 93% of an external comparison population. Percent predicted flow rates showed statistically significant reductions, but the reductions were small and there were no dose-response relations. Percent predicted FEV1 and FVC were about 96% of predicted.

  2. Dessicant materials screening for backfill in a salt repository

    SciTech Connect (OSTI)

    Simpson, D.R.

    1980-10-01

    Maintaining an anhydrous environment around nuclear waste stored in a salt repository is a concern which can be alleviated by using a desiccant material for backfilling. Such a desiccant should desiccate a brine yet be non deliquescent, the hydrated product should have moderate thermal stability, and the desiccant should have a high capacity and be readily available. From a literature search MgO and CaO were identified for detailed study. These oxides, and an intimate mixture of the two obtained by calcining dolomite, were used in experiments to further determine their suitability. They proved to be excellent desiccants with a high water capacity. The hydrates of both have moderate thermal stability and a high water content. Both MgO and CaO react in an alkaline chloride brine forming oxychloride compounds with different waters of crystallization. Some of these compounds are the Sorel Cements. CaO hydrates to Ca(OH)/sub 2/ which carbonates with CO/sub 2/ in air to form CaCO/sub 3/ and release the hydrated water. Thus the intimate mixture of CaO and MgO from calcined dolomite may serve as a desiccant and remove CO/sub 2/ from the repository atmosphere.

  3. EP-AREAG-PLAN-1248, R.0 TA-54 Area G Nitrate-Salt Waste Container...

    Office of Environmental Management (EM)

    EP-AREAG-PLAN-1248, R.0 TA-54 Area G Nitrate-Salt Waste Container Response Instructions Effective Date: 5282014 The Responsible Manager has determined that the following...

  4. Transient Analyses for a Molten Salt Transmutation Reactor Using the Extended SIMMER-III Code

    SciTech Connect (OSTI)

    Wang, Shisheng; Rineiski, Andrei; Maschek, Werner; Ignatiev, Victor

    2006-07-01

    Recent developments extending the capabilities of the SIMMER-III code for the dealing with transient and accidents in Molten Salt Reactors (MSRs) are presented. These extensions refer to the movable precursor modeling within the space-time dependent neutronics framework of SIMMER-III, to the molten salt flow modeling, and to new equations of state for various salts. An important new SIMMER-III feature is that the space-time distribution of the various precursor families with different decay constants can be computed and took into account in neutron/reactivity balance calculations and, if necessary, visualized. The system is coded and tested for a molten salt transmuter. This new feature is also of interest in core disruptive accidents of fast reactors when the core melts and the molten fuel is redistributed. (authors)

  5. Molten Salt Heat Transport Loop: Materials Corrosion and Heat Transfer Phenomena

    SciTech Connect (OSTI)

    Dr. Kumar Sridharan; Dr. Mark Anderson; Dr. Michael Corradini; Dr. Todd Allen; Luke Olson; James Ambrosek; Daniel Ludwig

    2008-07-09

    An experimental system for corrosion testing of candidate materials in molten FLiNaK salt at 850 degree C has been designed and constructed. While molten FLiNaK salt was the focus of this study, the system can be utilized for evaluation of materials in other molten salts that may be of interest in the future. Using this system, the corrosion performance of a number of code-certified alloys of interest to NGNP as well as the efficacy of Ni-electroplating have been investigated. The mechanisums underlying corrosion processes have been elucidated using scanning electron microscopy, x-ray diffraction, and x-ray photoelectron spectroscopy of the materials after the corrosion tests, as well as by the post-corrosion analysis of the salts using inductively coupled plasma (ICP) and neutron activation analysis (NAA) techniques.

  6. Savannah River Site Basis for Section 3116 Determination for Salt Waste Disposal

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) published in the Federal Register (January 24, 2006), a Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site.

  7. ,"U.S. Natural Gas Non-Salt Underground Storage Activity-Net...

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

    ...dnavnghistn5560us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Activity-Net (MMcf)" ...

  8. ,"U.S. Natural Gas Non-Salt Underground Storage Activity-Withdraw...

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

    ...dnavnghistn5550us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Activity-Withdraw (MMcf)" ...

  9. ,"U.S. Natural Gas Non-Salt Underground Storage Activity-Net...

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

    ...dnavnghistn5560us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Activity-Net (MMcf)" ...

  10. ,"U.S. Natural Gas Non-Salt Underground Storage Injections (MMcf...

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

    ...dnavnghistn5540us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Injections (MMcf)" "Sourcekey","N5540US2" ...

  11. ,"U.S. Natural Gas Non-Salt Underground Storage Activity-Withdraw...

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

    ...dnavnghistn5550us2a.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Activity-Withdraw (MMcf)" ...

  12. ,"U.S. Natural Gas Non-Salt Underground Storage Injections (MMcf...

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

    ...dnavnghistn5540us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ... 1: U.S. Natural Gas Non-Salt Underground Storage Injections (MMcf)" "Sourcekey","N5540US2" ...

  13. ,"U.S. Natural Gas Salt Underground Storage - Working Gas (MMcf...

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

    1","U.S. Natural Gas Salt Underground Storage - Working Gas (MMcf)",1,"Monthly","2...dnavnghistn5410us2m.htm" ,"Source:","Energy Information Administration" ,"For Help, ...

  14. Viscosity of multi-component molten nitrate salts : liquidus to 200 degrees C.

    SciTech Connect (OSTI)

    Bradshaw, Robert W.

    2010-03-01

    The viscosity of molten salts comprising ternary and quaternary mixtures of the nitrates of sodium, potassium, lithium and calcium was determined experimentally. Viscosity was measured over the temperature range from near the relatively low liquidus temperatures of he individual mixtures to 200C. Molten salt mixtures that do not contain calcium nitrate exhibited relatively low viscosity and an Arrhenius temperature dependence. Molten salt mixtures that contained calcium nitrate were relatively more viscous and viscosity increased as the roportion of calcium nitrate increased. The temperature dependence of viscosity of molten salts containing calcium nitrate displayed curvature, rather than linearity, when plotted in Arrhenius format. Viscosity data for these mixtures were correlated by the Vogel-Fulcher- ammann-Hesse equation.

  15. Effect of composition on the density of multi-component molten nitrate salts.

    SciTech Connect (OSTI)

    Bradshaw, Robert W.

    2009-12-01

    The density of molten nitrate salts was measured to determine the effects of the constituents on the density of multi-component mixtures. The molten salts consisted of various proportions of the nitrates of potassium, sodium, lithium and calcium. Density measurements ere performed using an Archimedean method and the results were compared to data reported in the literature for the individual constituent salts or simple combinations, such as the binary Solar Salt mixture of NaNO3 and KNO3. The addition of calcium nitrate generally ncreased density, relative to potassium nitrate or sodium nitrate, while lithium nitrate decreased density. The temperature dependence of density is described by a linear equation regardless of composition. The molar volume, and thereby, density of multi-component mixtures an be calculated as a function of temperature using a linear additivity rule based on the properties of the individual constituents.

  16. To bolster lithium battery life, add a little salt > EMC2 News...

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

    'Genius Award' In This Section EMC2 News Archived News Stories To bolster lithium battery life, add a little salt August 13th, 2014 By Blaine Friedlander Archer Lu...

  17. Model Development and Analysis of the Fate and Transport of Water in a Salt Based Repository

    Broader source: Energy.gov [DOE]

    The study summarizes the initial work on numerical modeling, simulations, and experimental results related to nuclear waste storage in a salt repository.  The study reflects the project's...

  18. Molten salt extraction of transuranic and reactive fission products from used uranium oxide fuel

    DOE Patents [OSTI]

    Herrmann, Steven Douglas

    2014-05-27

    Used uranium oxide fuel is detoxified by extracting transuranic and reactive fission products into molten salt. By contacting declad and crushed used uranium oxide fuel with a molten halide salt containing a minor fraction of the respective uranium trihalide, transuranic and reactive fission products partition from the fuel to the molten salt phase, while uranium oxide and non-reactive, or noble metal, fission products remain in an insoluble solid phase. The salt is then separated from the fuel via draining and distillation. By this method, the bulk of the decay heat, fission poisoning capacity, and radiotoxicity are removed from the used fuel. The remaining radioactivity from the noble metal fission products in the detoxified fuel is primarily limited to soft beta emitters. The extracted transuranic and reactive fission products are amenable to existing technologies for group uranium/transuranic product recovery and fission product immobilization in engineered waste forms.

  19. Method of removal of heavy metal from molten salt in IFR fuel pyroprocessing

    DOE Patents [OSTI]

    Gay, E.C.

    1995-10-03

    An electrochemical method is described for separating heavy metal values from a radioactive molten salt including Li halide at temperatures of about 500 C. The method comprises positioning a solid Li--Cd alloy anode in the molten salt containing the heavy metal values, positioning a Cd-containing cathode or a solid cathode positioned above a catch crucible in the molten salt to recover the heavy metal values, establishing a voltage drop between the anode and the cathode to deposit material at the cathode to reduce the concentration of heavy metals in the salt, and controlling the deposition rate at the cathode by controlling the current between the anode and cathode. 3 figs.

  20. Method for converting UF5 to UF4 in a molten fluoride salt

    DOE Patents [OSTI]

    Bennett, Melvin R.; Bamberger, Carlos E.; Kelmers, A. Donald

    1977-01-01

    The reduction of UF.sub.5 to UF.sub.4 in a molten fluoride salt by sparging with hydrogen is catalyzed by metallic platinum. The reaction is also catalyzed by platinum alloyed with gold reaction equipment.

  1. Proceedings of 3rd US/German Workshop on Salt Repository Research...

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

    New Mexico on October 8-11, 2012. Approximately 60 salt research scientists from Germany and the United States met to discuss repository science state of the art. Workshop...

  2. Electrical double layers and differential capacitance in molten salts from density functional theory

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

    Frischknecht, Amalie L.; Halligan, Deaglan O.; Parks, Michael L.

    2014-08-05

    Classical density functional theory (DFT) is used to calculate the structure of the electrical double layer and the differential capacitance of model molten salts. The DFT is shown to give good qualitative agreement with Monte Carlo simulations in the molten salt regime. The DFT is then applied to three common molten salts, KCl, LiCl, and LiKCl, modeled as charged hard spheres near a planar charged surface. The DFT predicts strong layering of the ions near the surface, with the oscillatory density profiles extending to larger distances for larger electrostatic interactions resulting from either lower temperature or lower dielectric constant. Inmore » conclusion, overall the differential capacitance is found to be bell-shaped, in agreement with recent theories and simulations for ionic liquids and molten salts, but contrary to the results of the classical Gouy-Chapman theory.« less

  3. EIS-0082-S2: Savannah River Site Salt Processing, Savannah River Site, Aiken, South Carolina

    Broader source: Energy.gov [DOE]

    This SEIS evaluates the potential environmental impacts of alternatives for separating the high-activity fraction from the low-activity fraction of the high-level radioactive waste salt solutions...

  4. A New Approach for Modeling and Analysis of Molten Salt Reactors...

    Office of Scientific and Technical Information (OSTI)

    Title: A New Approach for Modeling and Analysis of Molten Salt Reactors Using SCALE Authors: Powers, Jeffrey J 1 ; Harrison, Thomas J 1 ; Gehin, Jess C 1 + Show Author ...

  5. Project Profile: Novel Molten Salts Thermal Energy Storage for Concentrating Solar Power Generation

    Broader source: Energy.gov [DOE]

    The University of Alabama, under the Thermal Storage FOA, is developing thermal energy storage (TES) media consisting of low melting point (LMP) molten salt with high TES density for sensible heat storage systems.

  6. EIS-0010: Strategic Petroleum Reserves, Sulphur Mines Salt Dome, Calcasieu Parish, Louisiana

    Broader source: Energy.gov [DOE]

    The Strategic Petroleum Reserves prepared this EIS to assess the environmental impacts of the proposed storage of 24 million barrels of crude oil at the Sulphur Mines salt dome located in Calcasieu Parish, Louisiana, including construction and operation impacts.

  7. 6th US/German Workshop on Salt Repository Research, Design and...

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

    LIST of Participants 6th USGerman Workshop on Salt Repository Research, Design and Operations LAST NAME FIRST NAME COMPANY EMAIL Vlzke Holger BAM Holger.Voelzke@bam.de Mauke...

  8. Notice of Availability of Section 3116 Determination for Salt Waste Disposal at the Savannah River Site

    Broader source: Energy.gov [DOE]

    The Department of Energy (DOE) announces the availability of a section 3116 determination for the disposal of separated, solidified, low-activity salt waste at the Savannah River Site (SRS) near...

  9. Parametric Analyses of Single-zone Thorium-fueled Molten Salt...

    Office of Scientific and Technical Information (OSTI)

    Title: Parametric Analyses of Single-zone Thorium-fueled Molten Salt Reactor Fuel Cycle Options Authors: Powers, Jeffrey J 1 ; Worrall, Andrew 1 ; Gehin, Jess C 1 ; Harrison, ...

  10. An Inventory Analysis of Thermal-spectrum Thorium-fueled Molten Salt

    Office of Scientific and Technical Information (OSTI)

    Reactor Concepts: Supporting U.S. Fuel Cycle Assessment (Conference) | SciTech Connect Conference: An Inventory Analysis of Thermal-spectrum Thorium-fueled Molten Salt Reactor Concepts: Supporting U.S. Fuel Cycle Assessment Citation Details In-Document Search Title: An Inventory Analysis of Thermal-spectrum Thorium-fueled Molten Salt Reactor Concepts: Supporting U.S. Fuel Cycle Assessment Authors: Powers, Jeffrey J [1] ; Gehin, Jess C [1] ; Worrall, Andrew [1] ; Harrison, Thomas J [1] ;

  11. Incorporating supercritical steam turbines into molten-salt power tower plants : feasibility and performance.

    SciTech Connect (OSTI)

    Pacheco, James Edward; Wolf, Thorsten; Muley, Nishant

    2013-03-01

    Sandia National Laboratories and Siemens Energy, Inc., examined 14 different subcritical and supercritical steam cycles to determine if it is feasible to configure a molten-salt supercritical steam plant that has a capacity in the range of 150 to 200 MWe. The effects of main steam pressure and temperature, final feedwater temperature, and hot salt and cold salt return temperatures were determined on gross and half-net efficiencies. The main steam pressures ranged from 120 bar-a (subcritical) to 260 bar-a (supercritical). Hot salt temperatures of 566 and 600%C2%B0C were evaluated, which resulted in main steam temperatures of 553 and 580%C2%B0C, respectively. Also, the effects of final feedwater temperature (between 260 and 320%C2%B0C) were evaluated, which impacted the cold salt return temperature. The annual energy production and levelized cost of energy (LCOE) were calculated using the System Advisory Model on 165 MWe subcritical plants (baseline and advanced) and the most promising supercritical plants. It was concluded that the supercritical steam plants produced more annual energy than the baseline subcritical steam plant for the same-size heliostat field, receiver, and thermal storage system. Two supercritical steam plants had the highest annual performance and had nearly the same LCOE. Both operated at 230 bar-a main steam pressure. One was designed for a hot salt temperature of 600%C2%B0C and the other 565%C2%B0C. The LCOEs for these plants were about 10% lower than the baseline subcritical plant operating at 120 bar-a main steam pressure and a hot salt temperature of 565%C2%B0C. Based on the results of this study, it appears economically and technically feasible to incorporate supercritical steam turbines in molten-salt power tower plants.

  12. Waste Isolation Pilot Plant Nitrate Salt Bearing Waste Container Isolation Plan

    Broader source: Energy.gov [DOE]

    The purpose of this document is to provide the Plan required by the New Mexico Environment Department Administrative Order 05-20001 issued on May 20, 2014 to the U. S. Department of Energy and Nuclear Waste Partnership LLC. The Order, at paragraph 22, requires the Permittees to submit a WIPP Nitrate Salt Bearing Waste Container Isolation Plan for identified nitrate salt bearing waste disposed in the Waste Isolation Pilot Plant underground disposal facility.

  13. A new approach for modeling and analysis of molten salt reactors using

    Office of Scientific and Technical Information (OSTI)

    SCALE (Conference) | SciTech Connect Conference: A new approach for modeling and analysis of molten salt reactors using SCALE Citation Details In-Document Search Title: A new approach for modeling and analysis of molten salt reactors using SCALE The Office of Fuel Cycle Technologies (FCT) of the DOE Office of Nuclear Energy is performing an evaluation and screening of potential fuel cycle options to provide information that can support future research and development decisions based on the

  14. Radio Signals From Photon Beams in Sand And Salt (Journal Article) |

    Office of Scientific and Technical Information (OSTI)

    SciTech Connect Radio Signals From Photon Beams in Sand And Salt Citation Details In-Document Search Title: Radio Signals From Photon Beams in Sand And Salt No abstract prepared. Authors: Williams, D. ; /Pennsylvania U. ; Gorham, P. ; Guillian, E. ; Milincic, R. ; Miocinovic, P. ; /Hawaii U. ; Saltzberg, D. ; Williams, D. ; /UCLA ; Field, R.C. ; Iverson, R. ; Odian, A. ; Walz, D. ; /SLAC ; Resch, G. ; /Caltech, JPL ; Schoessow, P. ; /Argonne Publication Date: 2006-09-22 OSTI Identifier:

  15. An Experimental Test Facility to Support Development of the Fluoride Salt Cooled High Temperature Reactor

    SciTech Connect (OSTI)

    Yoder Jr, Graydon L; Aaron, Adam M; Cunningham, Richard Burns; Fugate, David L; Holcomb, David Eugene; Kisner, Roger A; Peretz, Fred J; Robb, Kevin R; Wilgen, John B; Wilson, Dane F

    2014-01-01

    The need for high-temperature (greater than 600 C) energy exchange and delivery systems is significantly increasing as the world strives to improve energy efficiency and develop alternatives to petroleum-based fuels. Liquid fluoride salts are one of the few energy transport fluids that have the capability of operating at high temperatures in combination with low system pressures. The Fluoride Salt-Cooled High-Temperature Reactor design uses fluoride salt to remove core heat and interface with a power conversion system. Although a significant amount of experimentation has been performed with these salts, specific aspects of this reactor concept will require experimental confirmation during the development process. The experimental facility described here has been constructed to support the development of the Fluoride Salt Cooled High Temperature Reactor concept. The facility is capable of operating at up to 700 C and incorporates a centrifugal pump to circulate FLiNaK salt through a removable test section. A unique inductive heating technique is used to apply heat to the test section, allowing heat transfer testing to be performed. An air-cooled heat exchanger removes added heat. Supporting loop infrastructure includes a pressure control system; trace heating system; and a complement of instrumentation to measure salt flow, temperatures, and pressures around the loop. The initial experiment is aimed at measuring fluoride salt heat transfer inside a heated pebble bed similar to that used for the core of the pebble bed advanced high-temperature reactor. This document describes the details of the loop design, auxiliary systems used to support the facility, the inductive heating system, and facility capabilities.

  16. EVIDENCE OF CORROSIVE GAS FORMED BY RADIOLYSIS OF CHLORIDE SALTS IN PLUTONIUM-BEARING MATERIALS

    SciTech Connect (OSTI)

    Dunn, K.; Louthan, M.

    2010-02-01

    Corrosion and pitting have been observed in headspace regions of stainless steel containers enclosing plutonium oxide/salt mixtures. These observations are consistent with the formation of a corrosive gas, probably HCl, and transport of that gas to the headspace regions of sealed containers. The NH{sub 4}Cl films found on the walls of the sealed containers is also indicative of the presence of HCl gas. Radiolysis of hydrated alkaline earth salts is the probable source of HCl.

  17. Development of fluoride reprocessing technologies devoted to molten-salt reactor systems

    SciTech Connect (OSTI)

    Uhlir, Jan; Marecek, Martin; Tulackova, Radka; Chuchvalcova Bimova, Karolina

    2007-07-01

    Main fuel processing and reprocessing technologies proposed for Molten Salt Reactor fuel cycle are pyrochemical or pyrometallurgical, majority of them are fluoride technologies. It is based on the fact that Molten Salt Reactor fuel is in the chemical form of molten fluorides and the reprocessing technology is needed to be an 'on-line' process. The corresponding pyrochemical separation processes proposed for MSR fuel processing and reprocessing are mainly fluoride volatilization processes, molten salt / liquid metal extraction processes, electrochemical separation processes from the molten salt media and gas extraction from the molten salt medium. Techniques based on fluoride volatilization and on electrochemical separation from fluoride molten salt media are under development in the Czech Republic. Whereas the Fluoride Volatility Method is proposed to be the main 'Front-end' technology of the MSR used as the actinide burner (transmuter), the electro-separation methods should be dedicated to the 'on-line' reprocessing of the circulating MSR fuel and should be used as for MSR incinerating transuranium fuel as for MSR working within the {sup 232}Th - {sup 233}U fuel cycle. (authors)

  18. Preliminary technical and legal evaluation of disposing of nonhazardous oil field waste into salt caverns

    SciTech Connect (OSTI)

    Veil, J.; Elcock, D.; Raivel, M.; Caudle, D.; Ayers, R.C. Jr.; Grunewald, B.

    1996-06-01

    Caverns can be readily formed in salt formations through solution mining. The caverns may be formed incidentally, as a result of salt recovery, or intentionally to create an underground chamber that can be used for storing hydrocarbon products or compressed air or disposing of wastes. The purpose of this report is to evaluate the feasibility, suitability, and legality of disposing of nonhazardous oil and gas exploration, development, and production wastes (hereafter referred to as oil field wastes, unless otherwise noted) in salt caverns. Chapter 2 provides background information on: types and locations of US subsurface salt deposits; basic solution mining techniques used to create caverns; and ways in which salt caverns are used. Later chapters provide discussion of: federal and state regulatory requirements concerning disposal of oil field waste, including which wastes are considered eligible for cavern disposal; waste streams that are considered to be oil field waste; and an evaluation of technical issues concerning the suitability of using salt caverns for disposing of oil field waste. Separate chapters present: types of oil field wastes suitable for cavern disposal; cavern design and location; disposal operations; and closure and remediation. This report does not suggest specific numerical limits for such factors or variables as distance to neighboring activities, depths for casings, pressure testing, or size and shape of cavern. The intent is to raise issues and general approaches that will contribute to the growing body of information on this subject.

  19. Measurement of the Melting Point Temperature of Several Lithium-Sodium-Beryllium Fluoride Salt (Flinabe) Mixtures

    SciTech Connect (OSTI)

    McDonald, J.M; Nygren, R.E.; Lutz, T.J.; Tanaka, T.J; Ulrickson, M.A.; Boyle, T.J.; Troncosa, K.P.

    2005-04-15

    The molten salt Flibe, a combination of lithium and beryllium fluorides studied for molten salt fission reactors, has been proposed as a breeder and coolant for fusion applications. The melting points of 2LiF-BeF{sub 2} and LiF-BeF{sub 2} are 460 deg. C and 363 deg. C, but LiF-BeF{sub 2} is rather viscous and has less lithium for breeding. In the Advanced Power Extraction (APEX) Program, concepts with a free flowing liquid for the first wall and blanket were investigated. Flinabe (a mixture of LiF, BeF{sub 2} and NaF) was selected for a molten salt design because a melting temperature below 350 deg. C appeared possible and this provided an attractive operating temperature window for a reactor. To confirm that a ternary salt with a low melting temperature existed, several combinations of the fluoride salts, LiF, NaF and BeF{sub 2}, were melted in a stainless steel crucible under vacuum. One had an apparent melting temperature of 305 deg. C. The test system, preparation of the mixtures, melting procedures and temperature curves for the melting and cooling are presented along with the apparent melting points. Thermal modeling of the salt pool and crucible is reported in an accompanying paper.

  20. PILOT-SCALE REMOVAL OF FLUORIDE FROM LEGACY PLUTONIUM MATERIALS USING VACUUM SALT DISTILLATION

    SciTech Connect (OSTI)

    Pierce, R. A.; Pak, D. J.

    2012-09-11

    Between September 2009 and January 2011, the Savannah River National Laboratory (SRNL) and HB-Line designed, developed, tested, and successfully deployed a system for the distillation of chloride salts. In 2011, SRNL adapted the technology for the removal of fluoride from fluoride-bearing salts. The method involved an in situ reaction between potassium hydroxide (KOH) and the fluoride salt to yield potassium fluoride (KF) and the corresponding oxide. The KF and excess KOH can be distilled below 1000{deg}C using vacuum salt distillation (VSD). The apparatus for vacuum distillation contains a zone heated by a furnace and a zone actively cooled using either recirculated water or compressed air. During a vacuum distillation operation, a sample boat containing the feed material is placed into the apparatus while it is cool, and the system is sealed. The system is evacuated using a vacuum pump. Once a sufficient vacuum is attaned, heating begins. Volatile salts distill from the heated zone to the cooled zone where they condense, leaving behind the non-volatile material in the feed boat. Studies discussed in this report were performed involving the use of non-radioactive simulants in small-scale and pilot-scale systems as well as radioactive testing of a small-scale system with plutonium-bearing materials. Aspects of interest include removable liner design considerations, boat materials, in-line moisture absorption, and salt deposition.