DOCSLIB.ORG

Development of a Prototypic Tie-Tube for a Low Enriched Uranium (LEU) Nuclear Thermal Rocket (NTR)

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Development of a Prototypic Tie-Tube for a Low Enriched Uranium (LEU) Nuclear Thermal Rocket (NTR) Development of a Prototypic Tie-Tube for a Low Enriched Uranium (LEU) Nuclear Thermal Rocket (NTR) Team Members: Kelsa Benensky, Jacob Harry, and Jeffrey Clemens NASA Propulsion Academy Principal Investigator: Omar Mireles NASA Marshall Space Flight Center ER-24 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 Presentation Overview 1. Background and Project Overview 2. Tie-Tube Mechanical Design 3. Neutronic Studies 4. Moderator Production Experiments 5. Tie-Tube Test Rig (T3R) Setup 6. Conclusions and Recommendations 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 2 Nuclear thermal propulsion (NTP) systems use the energy from fission to provide high power levels for long periods of time Liquid hydrogen stored in the propellant tank first cools the reactor Thrust provided to the rocket via expansion of the propellant through the nozzle NTP is considered by many to be the preferred form of propulsion for manned missions to Mars 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 3 NTP is a proven technology with 20 reactors ground tested in the Rover/NERVA Programs Tie-tubes played an important role in the past to provide in-core cooling and neutronic moderation for fuel test reactors during the later Rover/NERVA tests 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 4 A LEU NTR has the potential to greatly decrease the cost of developing NTP One of the major costs associated with developing NTP is the specific facilities needed to produce, handle, and test highly enriched uranium for nuclear fuel forms 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 5 In the LEU Reactor, tie-tubes function as in-core reactor components to provide core cooling and house the neutron moderator System Specifications Moderator Element/Tie-Tube Reactor System Performance Core power (MW) 519.2 Core average fuel power density (MW/l) 17.21 1.8 cm Max Fuel Temp. (K) 2849.9 84 cm U-235 Enrichment (a%) 19.75 U-235 inventory (kg) 34.14 Engine System Interface Points Flow Rate Pressure Temp. Interface Point (lbm/s) (psia) (R) Tie Tube Inlet 14.6 1059 49.3 Tie Tube Outlet 14.6 698 900 There are expected to be 680 tie-tube elements within a 25,000 lbf thrust NTR 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 6 The team was tasked to develop a feasible mechanical tie-tube design by testing the material and thermo-mechanical response of the system Mechanical Design and Moderator Production / Tie-Tube Test Rig Computational Analysis Materials Fabrication Design & Assembly This task was split into three sub-tasks that were pursued in parallel by each team member 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 7 Tie-tubes are oriented axially along the length of the core and play an important role in satisfying the system power balance and providing neutron moderation 1 • Tie-tubes surround 12 21 17 8 the fuel elements 63 5 6 8 15 • Tie-tubes connect 25 3 2 1424 16 into the injectifold 15 10 to provide power 2616 9 11 for the turbo 14 13 pumps 5 4 7 4 • Tie-tubes provide 2717 22 18 1323 structural support 19 to the reactor 30 20 2112 31 32 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 8 The design of the tie-tube assembly requires the successful integration of many components to ensure safe reactor operation Moderator Radial Support Injectifold Support Piece Spacer Connector Piece Axial Compression Turning Vane Inner Tie-Tube Spring Neutron Outer Tie-Tube Inlet Hydrogen Moderator Flow A 13 inch tie-tube prototype was also modelled for sub-scale testing 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 9 The neutronics of the core was investigated to determine power profiles and the impact of mechanical design / material selection on reactivity Reactivity vs. Spacer Placement 80 0 0 2 4 6 -0.1 70 -0.2 60 Reactivity ($) Reactivity -0.3 50 -0.4 Spacer Number 40 Reactivity vs. Hydrogen Concentration 4 LENGTH (CM) LENGTH 2 30 0 1.5 1.6 1.7 1.8 1.9 2 20 -2 -4 Reactivity ($) Reactivity 10 -6 -8 Hydride fraction ZrHx 0 It was found that core reactivity is strongly affected by number of spacers and placement, as well as the hydride content of the moderator A zirconium hydride (ZrHx) was chosen to best moderate neutrons within the reactor core – this ensures that the fuel is used more efficiently Effect of hydrogen to uranium ratio on neutron multiplication factor for different moderators of interest Moderator elements surround the fuel to ensure the fuel is used efficiently Unfortunately at high temperatures ZrH can become very brittle, therefore it is desirable for ZrH to be in ε-phase which is the most malleable phase at high temperatures and has the lowest Young’s Modulus 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 11 Three processes were investigated through a literature search as potential methods to produce ZrH1.8 1. Sintering of ZrH2 2. Direct Hydride of 3. Direct Hydride of Zirconium Powder Zirconium Sponge Tube / Round Bar Ultimately, direct hydride of zirconium tube was chosen because of its capability to provide a better grain structure and a hydride closest to theoretical density (advantageous for neutronic analysis) 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 12 Zirconium hydride was produced using the Enclosed Hydrogen Tube Furnace (EHTF) in the Materials Building (4602) 1. Zirconium Samples were machined, measured, and cleaned pre-hydride 2. EHTF operation consists of 7 steps Sample Loading Argon Purge This system was designed by a previous intern but built and tested by the NTP core components team Zirconium hydride was produced using the Enclosed Hydrogen Tube Furnace (EHTF) in the Materials Building (4602) 1. Zirconium Samples were machined, measured, and cleaned pre-hydride 2. EHTF operation consists of 7 steps Sample Loading Argon Purge Zirconium hydride was produced using the Enclosed Hydrogen Tube Furnace (EHTF) in the Materials Building (4602) 1. Zirconium Samples were machined, measured, and cleaned pre-hydride 2. EHTF operation consists of 7 steps Sample Loading Argon Purge Hydrogen Initiation Furnace Operation Zirconium hydride was produced using the Enclosed Hydrogen Tube Furnace (EHTF) in the Materials Building (4602) 1. Zirconium samples were machined, measured, and cleaned pre-hydride 2. EHTF operation consists of 7 steps Sample Loading Argon Purge Hydrogen Initiation Furnace Operation System Cool Down System Shutdown Sample Removal 3. Post Hydride Samples were qualified using X-Ray Diffraction (XRD) Zirconium hydride was produced using the Enclosed Hydrogen Tube Furnace (EHTF) in the Materials Building (4602) 1. Zirconium samples were machined, measured, and cleaned pre-hydride 2. EHTF operation consists of 7 steps Sample Loading Argon Purge Hydrogen Initiation Furnace Operation System Cool Down System Shutdown Sample Removal 3. Post Hydride Samples were measured and qualified using X-Ray Diffraction (XRD) Four samples were hydrided in order to find the best method to produce the neutron moderator Sample Test Matrix to Create Zirconium Hydride Samples Time Temperature Pressure Flow Rate Run Gas Mixture (min) (⁰C) (psi) (SCCM) 1 45 600 10 5 H2 2 120 600 10 5 H2 3 45 600 10 50 5% H2/ 95% Ar 4 120 600 10 50 5% H2/ 95% Ar Experimental parameters for interest were duration of test and partial hydrogen pressure (controlled by gas mixture and flow rate) 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 18 Zirconium hydride production was proven qualitatively through XRD Sample ∆W Sample ∆L Run Sample (g) (mm) 1 1 0.00 0.01 1 2 0.00 0.07 2 1 0.01 0.00 2 2 0.01 0.00 3 1 0.02 0.03 3 2 0.04 0.01 4 1 0.01 0.06 4 2 0.00 0.02 Change in axial length and mass was observed and attributed to hydrogen pick up – since hydrogen has such a low atomic mass it is recommended more precise measuring instruments should be used 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 19 XRD results show evidence of hydrogen pickup within the zirconium metal The blue plot corresponds to Zr-702 while the black plot corresponds to the hydride sample 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 20 XRD results show evidence of hydrogen pickup within the zirconium metal The major peak shown in the sample XRD corresponds to a hydrogen peak at 2θ = 28⁰ 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 21 The Tie-tube Test Rig (T3R) was constructed to flow test a subscale tie-tube prototype Design Construction Preliminary Testing Over a ten week period, three major milestones were achieved to create a working system 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 22 The team was able to design both the mechanical and electrical system of the T3R Full-Scale T3R Parameters Parameters • The subscale tie-tube can Maximum 2850 1300 meet similar conditions to Temperature (K) the full length tie-tube Minimum 27 77 • The system can also be used Temperature (K) as a materials testing furnace • Moderator and spacer Maximum Pressure 1059 100 assemblies can be quickly (psi) tested with this system Mass Flow Rate 0.021 0.021 • The system is limited by the (lbm/s) capabilities of the Length (cm) 84 33 mechanical components it is comprised of 2015 Nuclear and Emerging Technologies for Space Conference Albuquerque, NM February 23 - 25 23 Procedures 1.
Load more

Recommended publications
  • Fuel Geometry Options for a Moderated Low-Enriched Uranium Kilowatt-Class Space Nuclear Reactor T ⁎ Leonardo De Holanda Mencarinia,B,Jeffrey C
    Nuclear Engineering and Design 340 (2018) 122–132 Contents lists available at ScienceDirect Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor T ⁎ Leonardo de Holanda Mencarinia,b,Jeffrey C. Kinga, a Nuclear Science and Engineering Program, Colorado School of Mines (CSM), 1500 Illinois St, Hill Hall, 80401 Golden, CO, USA b Subdivisão de Dados Nucleares - Instituto de Estudos Avançados (IEAv), Trevo Coronel Aviador José Alberto Albano do Amarante, n 1, 12228-001 São José dos Campos, SP, Brazil ABSTRACT A LEU-fueled space reactor would avoid the security concerns inherent with Highly Enriched Uranium (HEU) fuel and could be attractive to signatory countries of the Non-Proliferation Treaty (NPT) or commercial interests. The HEU-fueled Kilowatt Reactor Using Stirling Technology (KRUSTY) serves as a basis for a similar reactor fueled with LEU fuel. Based on MCNP6™ neutronics performance estimates, the size of a 5 kWe reactor fueled with 19.75 wt% enriched uranium-10 wt% molybdenum alloy fuel is adjusted to match the excess reactivity of KRUSTY. Then, zirconium hydride moderator is added to the core in four different configurations (a homogeneous fuel/moderator mixture and spherical, disc, and helical fuel geometries) to reduce the mass of uranium required to produce the same excess reactivity, decreasing the size of the reactor. The lowest mass reactor with a given moderator represents a balance between the reflector thickness and core diameter needed to maintain the multiplication factor equal to 1.035, with a H/D ratio of 1.81.
    [Show full text]
  • Delayed Hydride Cracking in Zirconium Alloys in Pressure Tube Nuclear Reactors
    IAEA-TECDOC-1410 Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors Final report of a coordinated research project 1998–2002 October 2004 IAEA-TECDOC-1410 Delayed hydride cracking in zirconium alloys in pressure tube nuclear reactors Final report of a coordinated research project 1998–2002 October 2004 The originating Section of this publication in the IAEA was: Nuclear Power Technology Development Section International Atomic Energy Agency Wagramer Strasse 5 P.O. Box 100 A-1400 Vienna, Austria DELAYED HYDRIDE CRACKING IN ZIRCONIUM ALLOYS IN PRESSURE TUBE NUCLEAR REACTORS IAEA, VIENNA, 2004 IAEA-TECDOC-1410 ISBN 92–0–110504–5 ISSN 1011–4289 © IAEA, 2004 Printed by the IAEA in Austria October 2004 FOREWORD This report documents the work performed in the Coordinated Research Project (CRP) on Hydrogen and Hydride Degradation of the Mechanical and Physical Properties of Zirconium Alloys. The Project consisted of hydriding samples of Zr-2.5 Nb pressure tube materials used in CANDU-type and RBMK reactors, the measurement of delayed hydride cracking (DHC) rates under specified conditions, and analysis of hydrogen concentrations. The project was overseen by a supervisory group of experts in the field who provided advice and assistance to the participants as required. All of the research work undertaken as part of the CRP is described in this report, which includes a review of the state of the art in understanding crack propagation by DHC and details of the experimental procedures that produced the most consistent set of DHC rates reported in an international round-robin exercise to this date. All of the participants and many of their co-workers in the laboratories involved in the CRP contributed results and material used in the drafting of this report, which contains compilations of all of the results, their analysis, discussions of their interpretation and conclusions and recommendations for further work.
    [Show full text]
  • NETS 2020 Template
    بÀƵƧǘȁǞƧƊǶ §ȲȌǐȲƊǿ ƊƧDzɈȌɈǘƵwȌȌȁƊȁƮȌȁ ɈȌwƊȲȺɈǘȲȌɐǐǘƊƮɨƊȁƧǞȁǐ خȁɐƧǶƵƊȲɈƵƧǘȁȌǶȌǐǞƵȺƊȁƮ ǞȁȁȌɨƊɈǞȌȁ ǞȺ ȺȯȌȁȺȌȲƵƮ Ʀɯ ɈǘƵ ƊDz ªǞƮǐƵ yƊɈǞȌȁƊǶ ׁׂ׀ׂ y0À² ÀǘǞȺ ƧȌȁǏƵȲƵȁƧƵ خׁׂ׀ׂ ةɈǘ׀׃ƊȁƮ ɩǞǶǶƦƵ ǘƵǶƮ ǏȲȌǿȯȲǞǶ ׂ׆ɈǘٌةmƊƦȌȲƊɈȌȲɯ ɩǞǶǶ ƦƵ ǘƵǶƮ ɨǞȲɈɐƊǶǶɯ ȺȌ ɈǘƊɈ ɈǘƵ ƵȁɈǞȲƵ y0À² خƧȌǿǿɐȁǞɈɯǿƊɯȯƊȲɈǞƧǞȯƊɈƵǞȁɈǘǞȺƵɮƧǞɈǞȁǐǿƵƵɈǞȁǐ ǐȌɨخȌȲȁǶخخׁׂ׀ȁƵɈȺׂششبǘɈɈȯȺ Nuclear and Emerging Technologies for Space Sponsored by Oak Ridge National Laboratory, April 26th-30th, 2021. Available online at https://nets2021.ornl.gov Table of Contents Table of Contents .................................................................................................................................................... 1 Thanks to the NETS2021 Sponsors! ...................................................................................................................... 2 Nuclear and Emerging Technologies for Space 2021 – Schedule at a Glance ................................................. 3 Nuclear and Emerging Technologies for Space 2021 – Technical Sessions and Panels By Track ............... 6 Nuclear and Emerging Technologies for Space 2021 – Lightning Talk Final Program ................................... 8 Nuclear and Emerging Technologies for Space 2021 – Track 1 Final Program ............................................. 11 Nuclear and Emerging Technologies for Space 2021 – Track 2 Final Program ............................................. 14 Nuclear and Emerging Technologies for Space 2021 – Track 3 Final Program ............................................. 18
    [Show full text]
  • Catalytic Systems Based on Cp2zrx2 (X = Cl, H), Organoaluminum
    catalysts Article Catalytic Systems Based on Cp2ZrX2 (X = Cl, H), Organoaluminum Compounds and Perfluorophenylboranes: Role of Zr,Zr- and Zr,Al-Hydride Intermediates in Alkene Dimerization and Oligomerization Lyudmila V. Parfenova 1,* , Pavel V. Kovyazin 1, Almira Kh. Bikmeeva 1 and Eldar R. Palatov 2 1 Institute of Petrochemistry and Catalysis of Russian Academy of Sciences, Prospekt Oktyabrya, 141, 450075 Ufa, Russia; [email protected] (P.V.K.); [email protected] (A.K.B.) 2 Bashkir State University, st. Zaki Validi, 32, 450076 Ufa, Russia; [email protected] * Correspondence: [email protected]; Tel.: +7-347-284-3527 i i Abstract: The activity and chemoselectivity of the Cp2ZrCl2-XAlBu 2 (X = H, Bu ) and [Cp2ZrH2]2- ClAlEt2 catalytic systems activated by (Ph3C)[B(C6F5)4] or B(C6F5)3 were studied in reactions with 1-hexene. The activation of the systems by B(C6F5)3 resulted in the selective formation of head- to-tail alkene dimers in up to 93% yields. NMR studies of the reactions of Zr complexes with organoaluminum compounds (OACs) and boron activators showed the formation of Zr,Zr- and Zr,Al-hydride intermediates, for which diffusion coefficients, hydrodynamic radii, and volumes were estimated using the diffusion ordered spectroscopy DOSY. Bis-zirconium hydride clusters of type x[Cp ZrH ·Cp ZrHCl·ClAlR ]·yRnAl(C F ) − were found to be the key intermediates of alkene 2 2 2 2 6 5 3 n dimerization, whereas cationic Zr,Al-hydrides led to the formation of oligomers. Citation: Parfenova, L.V.; Kovyazin, P.V.; Bikmeeva, A.K.; Palatov, E.R.
    [Show full text]
  • 2013 Book Modernorganoalum
    41 Topics in Organometallic Chemistry Editorial Board: M. Beller l J. M. Brown l P. H. Dixneuf A. Fu¨rstner l L. J. Gooßen l L. S. Hegedus P. Hofmann l T. Ikariya l L. A. Oro l Q.-L. Zhou Topics in Organometallic Chemistry Recently Published Volumes Organometallic Pincer Chemistry Photophysics of Organometallics Volume Editors: Gerard van Koten, Volume Editor: A. J. Lees David Milstein Vol. 29, 2010 Vol. 40, 2013 Molecular Organometallic Materials Organometallics and Renewables for Optics Volume Editors: Michael A. R. Meier, Volume Editors: H. Le Bozec, V. Guerchais Bert M. Weckhuysen, Pieter C. A. Bruijnincx Vol. 28, 2010 Vol. 39, 2012 Transition Metal Catalyzed Enantioselective Conducting and Magnetic Organometallic Allylic Substitution in Organic Synthesis Molecular Materials Volume Editor: Uli Kazmaier Volume Editors: M. Fourmigue´, L. Ouahab Vol. 38, 2011 Vol. 27, 2009 Bifunctional Molecular Catalysis Metal Catalysts in Olefin Polymerization Volume Editors: T. Ikariya, M. Shibasaki Volume Editor: Z. Guan Vol. 37, 2011 Vol. 26, 2009 Asymmetric Catalysis from a Chinese Perspective Bio-inspired Catalysts Volume Editor: Shengming Ma Volume Editor: T. R. Ward Vol. 36, 2011 Vol. 25, 2009 Higher Oxidation State Organopalladium Directed Metallation and Platinum Chemistry Volume Editor: N. Chatani Volume Editor: A. J. Canty Vol. 24, 2007 Vol. 35, 2011 Regulated Systems for Multiphase Catalysis Iridium Catalysis Volume Editors: W. Leitner, M. Ho¨lscher Volume Editor: P. G. Andersson Vol. 23, 2008 Vol. 34, 2011 Iron Catalysis – Fundamentals and Organometallic Oxidation Catalysis Applications Volume Editors: F. Meyer, C. Limberg Volume Editor: B. Plietker Vol. 22, 2007 Vol. 33, 2011 N-Heterocyclic Carbenes in Transition Medicinal Organometallic Chemistry Metal Catalysis Volume Editors: G.
    [Show full text]
  • 中文名稱英文名稱CAS.NO. 二乙縮醛acetal 105-57-7 乙醛
    中文名稱 英文名稱 CAS.NO.
    [Show full text]
  • 2020 Emergency Response Guidebook
    2020 A guidebook intended for use by first responders A guidebook intended for use by first responders during the initial phase of a transportation incident during the initial phase of a transportation incident involving hazardous materials/dangerous goods involving hazardous materials/dangerous goods EMERGENCY RESPONSE GUIDEBOOK THIS DOCUMENT SHOULD NOT BE USED TO DETERMINE COMPLIANCE WITH THE HAZARDOUS MATERIALS/ DANGEROUS GOODS REGULATIONS OR 2020 TO CREATE WORKER SAFETY DOCUMENTS EMERGENCY RESPONSE FOR SPECIFIC CHEMICALS GUIDEBOOK NOT FOR SALE This document is intended for distribution free of charge to Public Safety Organizations by the US Department of Transportation and Transport Canada. This copy may not be resold by commercial distributors. https://www.phmsa.dot.gov/hazmat https://www.tc.gc.ca/TDG http://www.sct.gob.mx SHIPPING PAPERS (DOCUMENTS) 24-HOUR EMERGENCY RESPONSE TELEPHONE NUMBERS For the purpose of this guidebook, shipping documents and shipping papers are synonymous. CANADA Shipping papers provide vital information regarding the hazardous materials/dangerous goods to 1. CANUTEC initiate protective actions. A consolidated version of the information found on shipping papers may 1-888-CANUTEC (226-8832) or 613-996-6666 * be found as follows: *666 (STAR 666) cellular (in Canada only) • Road – kept in the cab of a motor vehicle • Rail – kept in possession of a crew member UNITED STATES • Aviation – kept in possession of the pilot or aircraft employees • Marine – kept in a holder on the bridge of a vessel 1. CHEMTREC 1-800-424-9300 Information provided: (in the U.S., Canada and the U.S. Virgin Islands) • 4-digit identification number, UN or NA (go to yellow pages) For calls originating elsewhere: 703-527-3887 * • Proper shipping name (go to blue pages) • Hazard class or division number of material 2.
    [Show full text]
  • Aug. 21, 1973 3,753,883
    Aug. 21, 1973 B GRIGGS 3,753,883 PROCESS FOR PROVIDING A HYDRIDE-FREE AND OXIDE-FREE SURFACE ON ZIRCONIUM AND ZIRCONIUM-ALLOY BODIES Filed June 26, 1972 (&J.70A) ~7£//J. Al3J- OcJ 3,753,883 United States Patent Office Patented Aug. 21, 1973 1 3,753,883 The single figure of the drawing is a graph showing the PROCESS FOR PROVIDING A HYDRIDE-FREE current-potential-time relationship employed^ in carrying AND OXIDE-FREE SURFACE ON ZIRCO- out the present invention in accordance with one em- NIUM AND ZIRCONIUM-ALLOY BODIES bodiment thereof. Bruce Griggs, Richland, Wash., assignor to the United 5 In accordance with this invention, a body consisting States of America as represented by the United States essentially of zirconium and having a zirconium hydride Atomic Energy Commission surface layer is electrolytically anodized in aqueous nitric Filed June 26, 1972, Ser. No. 266,110 Int. CI. C23b J/00,1/02 acid solution to remove the hydride surface, fluoride ion U.S. CI. 204—144.5 7 Claims is added to the solution and electrolytic anodization is 10 continued to render the surface susceptible to chemical etching and chemical etching is performed in situ using ABSTRACT OF THE DISCLOSURE the anodization bath as etchant, or the body may be A zirconium or zirconium-alloy body having a zirco- etched in a separate HN03-HF etching solution. nium hydride surface layer is electrolytically anodized In the anodization operation, nitric acid is suitably in aqueous nitric acid solution to remove the hydride 15 present in 2.0% to 20% by weight of the aqueous solu- surface.
    [Show full text]
  • Hazardous Materials Descriptions and Codes
    2012 Commodity Flow Survey Hazardous Materials Descriptions and Codes Hazardous Materials Descriptions and Proper Shipping Names UN or NA Code Accellerene, see p-Nitrosodimethylaniline Accumulators, electric, see Batteries, wet etc Accumulators, pressurized, pneumatic or hydraulic (containing non-flammable gas), see Articles pressurized, pneumatic or hydraulic (containing non-flammable gas) Acetal 1088 Acetaldehyde 1089 Acetaldehyde ammonia 1841 Acetaldehyde oxime 2332 Acetic acid, glacial or Acetic acid solution, with more than 80 percent acid, by mass 2789 Acetic acid solution, not less than 50 percent but not more than 80 percent acid, by 2790 mass Acetic acid solution, with more than 10 percent and less than 50 percent acid, by mass 2790 Acetic anhydride 1715 Acetone 1090 Acetone cyanohydrin, stabilized 1541 Acetone oils 1091 Acetonitrile 1648 Acetyl bromide 1716 Acetyl chloride 1717 Acetyl iodide 1898 Acetyl methyl carbinol 2621 Acetylene, dissolved 1001 Acetylene tetrabromide, see Tetrabromoethane Acid butyl phosphate, see Butyl acid phosphate Acid, sludge, see Sludge acid Acridine 2713 Acrolein dimer, stabilized 2607 Acrolein, stabilized 1092 Acrylamide, solid 2074 Acrylamide solution 3426 Acrylic acid, stabilized 2218 Acrylonitrile, stabilized 1093 Actuating cartridge, explosive, see Cartridges, power device Adhesives, containing a flammable liquid 1133 Adiponitrile 2205 Aerosols, poison, Packing Group III (each not exceeding 1 L capacity) 1950 Aerosols, flammable, (each not exceeding 1 L capacity) 1950 Source: Electronic Code of Federal Regulations http://ecfr.gpoaccess.gov/cgi/t/text/text- idx?c=ecfr&sid=dfec99df9f21ef29b59a8565433a56cd&rgn=div6&view=text&node=49:2.1.1.3.8.2&idno=49 1 Hazardous Materials Descriptions and Proper Shipping Names UN or NA Code Aerosols, flammable, n.o.s.
    [Show full text]
  • Hydrogen-Enhanced Combustion of a Composite Propellant with Zrh2 As
    Combustion and Flame 187 (2018) 67–76 Contents lists available at ScienceDirect Combustion and Flame journal homepage: www.elsevier.com/locate/combustflame Hydrogen-enhanced combustion of a composite propellant with ZrH 2 as the fuel ∗ Yanjing Yang a, Fengqi Zhao a, , Huixiang Xu a, Qing Pei a, Hanyu Jiang a, Jianhua Yi a, Chunlei Xuan a, Sanping Chen b a Science and Technology on Combustion and Explosion Laboratory, Xi’an Modern Chemistry Research Institute, Xi’an 710065, Shaanxi, China b Key Laboratory of Synthetic and Natural Functional Molecule Chemistry of Ministry of Education, College of Chemistry and Material Science, Northwest University, Xi’an 710065, Shaanxi, China a r t i c l e i n f o a b s t r a c t Article history: The reaction mechanisms of metal hydrides in the combustion of solid propellants are closely related to Received 20 February 2017 their effects on the energetic and combustion properties of propellants. Here, we report a first attempt to Revised 1 September 2017 investigate the reaction mechanisms of ZrH 2 , a promising candidate for fuels, in the combustion of HTPB Accepted 5 September 2017 propellants using ammonium perchlorate (NH ClO , AP) as the oxidizer. ZrH is determined to possess a Available online 16 October 2017 4 4 2 good resistance to the direct oxidation by AP. Thus, it would dehydrogenate independently to generate Keywords: H 2 and metallic Zr, which is believed to be very favorable for decreasing the gaseous molecular masses. Solid propellant On the other hand, due to the attachment of gaseous reactants to it, ZrH 2 was found to tune the de- Combustion composition behaviors of AP by enhancing the generation of NO in the high-temperature decomposition Reaction mechanism stage.
    [Show full text]
  • Hydrogen in Zirconium Alloys: a Review
    Journal of Nuclear Materials 518 (2019) 440e460 Contents lists available at ScienceDirect Journal of Nuclear Materials journal homepage: www.elsevier.com/locate/jnucmat Hydrogen in zirconium alloys: A review * Arthur T. Motta a, , Laurent Capolungo b, Long-Qing Chen c, Mahmut Nedim Cinbiz d, Mark R. Daymond e, Donald A. Koss c, Evrard Lacroix a, Giovanni Pastore f, Pierre-Clement A. Simon a, Michael R. Tonks g, Brian D. Wirth h, Mohammed A. Zikry i a Department of Mechanical and Nuclear Engineering, 138 Reber Bldg, Penn State University, University Park, PA, 16802, USA b Materials Science and Technology Division, Los Alamos National Laboratory, Los Alamos, NM, 87545, USA c Department of Materials Science and Engineering, The Pennsylvania State University, University Park, PA, 16802-5006, USA d Reactor and Nuclear Systems Division, Nuclear Fuel Materials Group, Oak Ridge National Laboratory, Oak Ridge, TN, 37831, USA e Dept. of Mechanical and Materials Engineering, Queen's University, Kingston, Ontario, K7L 3N6, Canada f Idaho National Laboratory, Fuel Modeling and Simulation Department, Idaho Falls, ID, 83415, USA g Department of Materials Science and Engineering, University of Florida, Gainesville, FL, 32611, USA h Department of Nuclear Engineering, University of Tennessee, Knoxville, TN, 37996-1410, USA i Dept. of Mechanical and Aerospace Engineering, North Carolina State University, Raleigh, NC, 27695-7910, USA article info abstract Article history: Hydrogen absorbed into zirconium alloy nuclear fuel cladding as a result of the waterside corrosion Received 4 January 2019 reaction can affect the properties of nuclear fuel, principally through the precipitation of brittle hydride Received in revised form particles.
    [Show full text]
  • Chemical Upcycling of Polymers
    Report of the Basic Energy Sciences Roundtable on Chemical Upcycling of Polymers April 30–May 1, 2019 Bethesda, Maryland Chair: Phillip F. Britt, Oak Ridge National Laboratory Co-Chair: Geoffrey W. Coates, Cornell University Co-Chair: Karen I. Winey, University of Pennsylvania Participants: Phillip Britt, Oak Ridge National Laboratory Jeffrey Byers, Boston College Eugene Chen, Colorado State University Geoffrey Coates, Cornell University Bryan Coughlin, University of Massachusetts–Amherst Christopher Ellison, University of Minnesota Jeannette Garcia, IBM Alan Goldman, Rutgers University Javier Guzman, ExxonMobil John Hartwig, Lawrence Berkeley National Laboratory/University of California–Berkeley Brett Helms, Lawrence Berkeley National Laboratory George Huber, University of Wisconsin Cynthia Jenks, Argonne National Laboratory Jill Martin, Dow Chemical Maureen McCann, Purdue University Steve Miller, University of Florida Hugh O'Neill, Oak Ridge National Laboratory Aaron Sadow, Ames Laboratory Susannah Scott, University of California–Santa Barbara Lawrence Sita, University of Maryland Dion Vlachos, University of Delaware Karen Winey, University of Pennsylvania Robert Waymouth, Stanford University Contents List of Figures .............................................................................................................................................. v List of Sidebar Figures ............................................................................................................................... v Abbreviations, Acronyms
    [Show full text]