HSC Chemistry References
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Crown Chemical Resistance Chart
Crown Polymers, Corp. 11111 Kiley Drive Huntley, IL. 60142 USA www.crownpolymers.com 847-659-0300 phone 847-659-0310 facisimile 888-732-1270 toll free Chemical Resistance Chart Crown Polymers Floor and Secondary Containment Systems Products: CrownShield covers the following five (4) formulas: CrownShield 50, Product No. 320 CrownCote, Product No. 401 CrownShield 40-2, Product No. 323 CrownShield 28, Product No. 322 CrownPro AcidShield, Product No. 350 CrownCote AcidShield, Product No. 430 CrownPro SolventShield, Product No. 351 CrownCote SolventShield, Product No. 440 This chart shows chemical resistance of Crown Polymers foundational floor and secondary containment product line that would be exposed to chemical spill or immersion conditions. The chart was designed to provide general product information. For specific applications, contact your local Crown Polymers Floor and Secondary Containment Representative or call direct to the factory. ; Resistant to chemical immersion up to 7 days followed by wash down with water 6 Spillage environments that will be cleaned up within 72 hours after initial exposure. 9 Not Recommended Chemical CrownShield SolventShield AcidShield Chemical CrownShield SolventShield AcidShield 1, 4-Dichloro-2-butene 9 6 6 Aluminum Bromate ; ; ; 1, 4-Dioxane 9 6 6 Aluminum Bromide ; ; ; 1-1-1 Trichloroethane 9 ; ; Aluminum Chloride ; ; ; 2, 4-Pentanedione 6 ; 6 Aluminum Fluoride (25%) ; ; ; 3, 4-Dichloro-1-butene 6 6 6 Aluminum Hydroxide ; ; ; 4-Picoline (0-50%) 9 6 6 Aluminum Iodine ; ; ; Acetic Acid (0-15%) 9 6 6 -
Gasket Chemical Services Guide
Gasket Chemical Services Guide Revision: GSG-100 6490 Rev.(AA) • The information contained herein is general in nature and recommendations are valid only for Victaulic compounds. • Gasket compatibility is dependent upon a number of factors. Suitability for a particular application must be determined by a competent individual familiar with system-specific conditions. • Victaulic offers no warranties, expressed or implied, of a product in any application. Contact your Victaulic sales representative to ensure the best gasket is selected for a particular service. Failure to follow these instructions could cause system failure, resulting in serious personal injury and property damage. Rating Code Key 1 Most Applications 2 Limited Applications 3 Restricted Applications (Nitrile) (EPDM) Grade E (Silicone) GRADE L GRADE T GRADE A GRADE V GRADE O GRADE M (Neoprene) GRADE M2 --- Insufficient Data (White Nitrile) GRADE CHP-2 (Epichlorohydrin) (Fluoroelastomer) (Fluoroelastomer) (Halogenated Butyl) (Hydrogenated Nitrile) Chemical GRADE ST / H Abietic Acid --- --- --- --- --- --- --- --- --- --- Acetaldehyde 2 3 3 3 3 --- --- 2 --- 3 Acetamide 1 1 1 1 2 --- --- 2 --- 3 Acetanilide 1 3 3 3 1 --- --- 2 --- 3 Acetic Acid, 30% 1 2 2 2 1 --- 2 1 2 3 Acetic Acid, 5% 1 2 2 2 1 --- 2 1 1 3 Acetic Acid, Glacial 1 3 3 3 3 --- 3 2 3 3 Acetic Acid, Hot, High Pressure 3 3 3 3 3 --- 3 3 3 3 Acetic Anhydride 2 3 3 3 2 --- 3 3 --- 3 Acetoacetic Acid 1 3 3 3 1 --- --- 2 --- 3 Acetone 1 3 3 3 3 --- 3 3 3 3 Acetone Cyanohydrin 1 3 3 3 1 --- --- 2 --- 3 Acetonitrile 1 3 3 3 1 --- --- --- --- 3 Acetophenetidine 3 2 2 2 3 --- --- --- --- 1 Acetophenone 1 3 3 3 3 --- 3 3 --- 3 Acetotoluidide 3 2 2 2 3 --- --- --- --- 1 Acetyl Acetone 1 3 3 3 3 --- 3 3 --- 3 The data and recommendations presented are based upon the best information available resulting from a combination of Victaulic's field experience, laboratory testing and recommendations supplied by prime producers of basic copolymer materials. -
Molten Salt Chemistry Workshop
The cover depicts the chemical and physical complexity of the various species and interfaces within a molten salt reactor. To advance new approaches to molten salt technology development, it is necessary to understand and predict the chemical and physical properties of molten salts under extreme environments; understand their ability to coordinate fissile materials, fertile materials, and fission products; and understand their interfacial reactions with the reactor materials. Modern x-ray and neutron scattering tools and spectroscopy and electrochemical methods can be coupled with advanced computational modeling tools using high performance computing to provide new insights and predictive understanding of the structure, dynamics, and properties of molten salts over a broad range of length and time scales needed for phenomenological understanding. The actual image is a snapshot from an ab initio molecular dynamics simulation of graphene- organic electrolyte interactions. Image courtesy of Bobby G. Sumpter of ORNL. Molten Salt Chemistry Workshop Report for the US Department of Energy, Office of Nuclear Energy Workshop Molten Salt Chemistry Workshop Technology and Applied R&D Needs for Molten Salt Chemistry April 10–12, 2017 Oak Ridge National Laboratory Co-chairs: David F. Williams, Oak Ridge National Laboratory Phillip F. Britt, Oak Ridge National Laboratory Working Group Co-chairs Working Group 1: Physical Chemistry and Salt Properties Alexa Navrotsky, University of California–Davis Mark Williamson, Argonne National Laboratory Working -
Liquid Fluoride Salt Experiment Using a Small Natural Circulation Cell
ORNL/TM-2014/56 Liquid Fluoride Salt Experiment Using a Small Natural Circulation Cell Graydon L. Yoder, Jr. Dennis Heatherly David Williams Oak Ridge National Laboratory Josip Caja Mario Caja Approved for public release; Electrochemical Systems, Inc., distribution is unlimited. Yousri Elkassabgi John Jordan Roberto Salinas Texas A&M University April 2014 DOCUMENT AVAILABILITY Reports produced after January 1, 1996, are generally available free via US Department of Energy (DOE) SciTech Connect. Website http://www.osti.gov/scitech/ Reports produced before January 1, 1996, may be purchased by members of the public from the following source: National Technical Information Service 5285 Port Royal Road Springfield, VA 22161 Telephone 703-605-6000 (1-800-553-6847) TDD 703-487-4639 Fax 703-605-6900 E-mail [email protected] Website http://www.ntis.gov/help/ordermethods.aspx Reports are available to DOE employees, DOE contractors, Energy Technology Data Exchange representatives, and International Nuclear Information System representatives from the following source: Office of Scientific and Technical Information PO Box 62 Oak Ridge, TN 37831 Telephone 865-576-8401 Fax 865-576-5728 E-mail [email protected] Website http://www.osti.gov/contact.html This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. -
The Institute of Paper Chemistry
The Institute of Paper Chemistry Appleton, Wisconsin Doctor's Dissertation Reaction Products of Lignin Model Compounds and Sodium Hydrosulfide Thomas G. Zentner June, 1953 A STUDY OF THE REACTION PRODUCTS OF LIGNIN MODEL COMPOUNDS AND SODIUM HYDROSULFIDE A thesis submitted by Thomas G. Zentner B.S. 1948, Texas A & M College M.S. 1950, Lawrence College in partial fulfillment of the requirements of The Institute of Paper Chemistry for the degree of Doctor of Philosophy from Lawrence College, Appleton, Wisconsin June, 1952 TABLE OF CONTENTS INTRODUCTION 1 HISTORICAL REVIEW 2 PRESENTATION OF THE PROBLEM 8 EXPERIMENTAL PROCEDURES 10 Synthesis of Compounds 10 Synthesis of 1-(4-Hydroxy-3-methoxyphenyl)-l-propanol 10 Synthesis of 1-(4-Benzoxy-3-methoxyphenyl)-l-propanol 11 Reaction of 1-(4-Benzoxy-3-methoxyphenyl) l-propanol with Benzyl Chloride 12 Synthesis of Propiovanillone 14 Synthesis of (-(4-Acetyl-2-methoxyphenoxy)acetovanillone 17 Attempted Synthesis of a-(2-Methoxy-4-methylphehoxy)- propiovanillone 17 Attempted Synthesis of 4-[l-(2-Methoxy-4-methylphenoxy)- l-propyl]guaiacol 21 Synthesis of 2t,4-Dihydroxy-3-methoxychalcone 23 Synthesis of 4,4'-Dihydroxy-3,3 -dimethoxychalcone 24 Synthesis of 4-Propionylpyrocatechol 24 Synthesis of Bis[l-(4-hydroxy-3-methoxyphenyl)-1- propyl] Disulfide 26 Reaction of Isolated Native Lignin with Potassium Hydrosulfide 27 Sodium Hydrosulfide Cooks 28 Cooking Liquor 28 General Procedures 30 Propiovanillone' 32 iii 2 ,4-Dihydroxy-3-methoxychalcone 34 4,4'-Dihydroxy-3,3 '-methoxychalcohe 37 4'-Hydroxy-3t-methoxyflavanone 39 2-Vanillylidene-3-coumaranone 41 Vanillin 44 G- (4-Acetyl-2-methoxyphenoxy)acetovanillone 45 1-(4-Hydroxy-3-methoxyphenyl)-1-propanol 49 DISCUSSION 58 SUMMARY AND CONCLUSIONS 69 LITERATURE CITED 71 INTRODUCTION Although the kraft process has been in use for many years, there is no sound explanation of the role played by the sulfide ion in the cook. -
Thermal Properties of Licl-Kcl Molten Salt for Nuclear Waste Separation
Project No. 09-780 Thermal Properties of LiCl-KCl Molten Salt for Nuclear Waste Separation Fue l C yc le R&D Dr. Kumar Sridharan University of Wisconsin, Madison In collaboration with: Idaho National Laboratory Michael Simpson, Technical POC James Bresee, Federal POC Thermal Properties of LiCl -KCl Molten Salt for Nuclear Waste Separation Project Investigators: Dr. Kumar Sridharan, Dr. Todd Allen, Dr. Mark Anderson (University of Wisconsin) and Dr. Mike Simpson (Idaho National Laboratory) Post-Doctoral Research Associates: Dr. Luke Olson Graduate Students: Mr. Mehran Mohammadian and Mr. Sean Martin Undergradua te Students: Mr. Jacob Sager and Mr. Aidan Boyle University of Wisconsin -Madison NEUP Final Report Project Contact: Dr. Kumar Sridharan [email protected] Date: November 30th, 2012 Table of Contents 1. Introductory Narrative ............................................................................................................................. 1 2. Motivation ................................................................................................................................................ 2 3. Experimental Setup ................................................................................................................................... 3 3.1 Molten Salt Electrochemistry.............................................................................................................. 3 3.1.1 LiCl-KCl Eutectic Salt ................................................................................................................ -
Fissile, Fertile and Dual-Use Structural Materials Involved in Nuclear Reactors
ARTICLE NUCLEAR MATERIALS – FISSILE, FERTILE AND DUAL-USE STRUCTURAL MATERIALS INVOLVED IN NUCLEAR REACTORS N. R. DAS* The article presents a brief account of nuclear materials, with special emphasis on fissile, fertile and some important dual-use structural materials generally involved in nuclear reactors. The dual- use structural materials utilized in nuclear reactors have got important applications in both nuclear and non-nuclear fields. In the hostile environment, the important phenomena such as interactions between fission products and the surrounding elemental species, radiation-induced effects, corrosion, generation of gases, swelling and so forth, become increasingly complex and the performance of a nuclear reactor system thus becomes very much dependent on the physicochemical stability and nuclear compatibility of the dual-use structural materials used in fuel sub-assembly towards the fuel elements. In this context, the dual-use structural materials like stainless steel, zirconium alloys, etc. as claddings; water, liquid sodium or gases, etc. as coolants and water, boron, etc. as moderators, having good reliability and appropriate nuclear compatibility with the fuels, are of prime importance in reactor technology. In advanced designed reactors, development of novel fuels coupled with efficient dual-use structural materials may mitigate the challenges involved in optimizing the efficiency of the power reactors under specific experimental conditions. Introduction presented as 14N(, p)17O. In 1932, J. Chadwick discovered the fundamental particle, neutron, by bombardment of boron ince the discovery of X-rays by Wilhelm C. with alpha particle through the nuclear reaction,10B( , Roentgen and ‘Becquerel rays’ or ‘Uranic rays’ by n)13N. Subsequently, Irene and Frederic Joliot Curie in Henri Becquerel in the last decade of the nineteenth S 1934 discovered artificial radioactivity and Otto Hahn and century, conscientious activities in nuclear science have F. -
Chemical Resistance 100% SOLIDS EPOXY SYSTEMS
Chemical Resistance 100% SOLIDS EPOXY SYSTEMS CHEMICAL 8300 SYSTEM 8200 SYSTEM 8000 SYSTEM OVERKOTE PLUS HD OVERKOTE HD OVERKRETE HD BASED ON ONE YEAR IMMERSION TESTING –––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––––– Acetic Acid (0-15%) G II Acetonitrile LLG L Continuous Immersion Acetone (0-20%) LLL Acetone (20-30%) Suitable for continuous immersion in that chemical (based on LLG Acetone (30-50%) L G I ONE YEAR testing) to assure unlimited service life. Acetone (50-100%) G II Acrylamide (0-50%) LLL G Short-Term Exposure Adipic Acid Solution LLL Alcohol, Isopropyl LLL Suitable for short-term exposure to that chemical such as Alcohol, Ethyl LLG secondary containment (72 hours) or splash and spill Alcohol, Methyl LLI (immediate clean-up). Allyl Chloride LLI Allylamine (0-20%) L L I Allylamine (20-30%) L G I I Not Suitable Allylamine (30-50%) GGI Not suitable for any exposure to that chemical. Aluminum Bromide LL– Aluminum Chloride L L – Aluminum Fluoride (0-25%) L L – This chart shows chemical resistance of our various Aluminum Hydroxide LLL 1 topping materials (90 mils – ⁄4"). These ratings are based on Aluminum Iodide LL– temperatures being ambient. At higher temperatures, chemical Aluminum Nitrate LL– resistance may be effected. When chemical exposure is Aluminum Sodium Chloride L L – minimal to non-existent, a 9000 System–FlorClad™ HD or Aluminum Sulfate LLL 4600 System– BriteCast™ HD may be used. Alums L L L 2-Aminoethoxyethanol Resistance data is listed with the assumption that the material GGG has properly cured for at least four days, at recommended Ammonia – Wet L L – temperatures, prior to any chemical exposure. -
Corrosion-2020) (461 Event of the European Federation of Corrosion)
European Federation of Corrosion National Academy of Sciences of Ukraine Ministry of Education and Science of Ukraine Ukrainian Association of Corrosionists Karpenko Physico-Mechanical Institute Ivan Franko Lviv National University Ivano-Frankivsk National Technical University of Oil and Gas ХV International Conference «Problems of corrosion and corrosion protection of materials» (Corrosion-2020) (461 event of the European Federation of Corrosion) ABSTRACT BOOK October 15–16, 2020 Lviv, Ukraine UДC 539.3, 620.193, 620.194, 620.179, 620.197, 621.181:669.018, 621.785. XV International Conference “Problems of Corrosion and Corrosion Protection of Materials“ (Corrosion-2020). October 15-16, 2020, Lviv, Ukraine: Book of Abstract / Karpenko Physico-Mechanical Institute of NAS of Ukraine; S. Korniy, М.-О. Danyliak, Yu. Maksishko (Eds.). – Lviv, 2020. – 121 p. XV International Conference “Problems of Corrosion and Corrosion Protection of Materials“ (Corrosion-2020) was held at Lviv Palace of Arts on October 15-16, 2020. This Book of Abstract contains the results of studies are devoted to fundamentals of corrosion and corrosion assisted mechanical fracture; hydrogen and gas corrosion; new corrosion resistant materials; thermal spray, electroplated and other coatings; inhibitor, biocidal and electrochemical protection; testing methods and corrosion control; corrosion protection of oil and gas industry and chemical equipment. In the authors edition. Editorial board: S. Korniy, М.-О. Danyliak, Yu. Maksishko ©Karpenko Physico-Mechanical Institute of NAS of Ukraine, Lviv, 2020 CONFERENCE TOPICS: fundamentals of corrosion and corrosion assisted mechanical fracture; hydrogen and gas corrosion; new corrosion resistant materials and coatings; inhibitor and biocidal protection; electrochemical protection; testing methods and corrosion control; corrosion protected equipment of the oil and gas, chemical and energy industries. -
Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties
INL/EXT-10-18297 Rev. 1 Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties Manohar S. Sohal Matthias A. Ebner Piyush Sabharwall Phil Sharpe June 2013 The INL is a U.S. Department of Energy National Laboratory operated by Battelle Energy Alliance INL/EXT-10-18297 Rev. 1 Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties Manohar S. Sohal Matthias A. Ebner Piyush Sabharwall Phil Sharpe June 2013 Idaho National Laboratory Idaho Falls, Idaho 83415 http://www.inl.gov Prepared for the U.S. Department of Energy Office of Nuclear Energy Under DOE Idaho Operations Office Contract DE-AC07-05ID14517 DISCLAIMER This information was prepared as an account of work sponsored by an agency of the U.S. Government. Neither the U.S. Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness, of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. References herein to any specific commercial product, process, or service by trade name, trade mark, manufacturer, or otherwise, does not necessarily constitute or imply its endorsement, recommendation, or favoring by the U.S. Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the U.S. Government or any agency thereof. ABSTRACT The purpose of this report is to provide a review of thermophysical properties and thermochemical characteristics of candidate molten salt coolants, which may be used as a primary coolant within a nuclear reactor or heat transport medium from the Very High Temperature Reactor (VHTR) to a processing plant; for example, a hydrogen-production plant. -
Scaling Analysis for the Direct Reactor Auxiliary Cooling System for Ahtrs
Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs THESIS Presented in Partial Fulfillment of the Requirements for the Degree Master of Science in the Graduate School of The Ohio State University By Qiuping Lv, B.S. Graduate Program in Nuclear Engineering The Ohio State University 2013 Master's Examination Committee: Prof. Xiaodong Sun, Advisor Prof. Thomas E. Blue Prof. Richard N. Christensen Copyright by Qiuping Lv 2012 Abstract The Advanced High Temperature Reactor (AHTR) or Fluoride Salt Cooled High Temperature Reactor (FHR) is one of the advanced rector concepts that have been proposed for Gen IV reactors. The AHTR combines four main proven nuclear technologies, namely, the liquid salt of molten salt reactors, the coated particle fuel (TRISO particle) of high-temperature gas-cooled reactors, the pool configuration and passive safety system of sodium-cooled fast reactors, and the Brayton power cycle technology. The AHTR is capable of providing very high temperature (750 to 1,000ºC) heat for various industrial processing needs, hydrogen production, and electricity generation. The Direct Reactor Auxiliary Cooling System (DRACS) is a passive heat removal system that was derived from the Experimental Breeder Rector-II (EBR-II), and then improved in later fast reactor designs. The DRACS has been proposed for AHTR as the passive decay heat removal system. The DRACS features three coupled natural circulation/convection loops relying completely on buoyancy as the driving force. In the DRACS, two heat exchangers, namely, the DRACS Heat Exchanger (DHX) and the Natural Draft Heat Exchanger (NDHX) are used to couple these natural circulation/convection loops. -
Corrosion in Very High-Temperature Molten Salt for Next Generation CSP Systems
Corrosion in Very High-Temperature Molten Salt for Next Generation CSP Systems Brenda Garcia Diaz (PI), Josh Gray (Co-PI), Luke Olson, Michael Martinez-Rodriguez, Roderick Fuentes (SRNL) Ramana Reddy, John Van Zee (University of Alabama) Project Identifier: Garcia-Diaz_A Project Start: Q1 - FY2013 1 April 1st , 2013 Outline • Motivation • Innovation • Goals and Objectives • Background • Molten Salt and Material Selection • Molten Salt Corrosion Review • Current status • Corrosion measurements/Inhibitor studies • Thermodynamic modeling • Electrochemical Kinetics and CFD Corrosion Modeling • Future plans 2 April 1st , 2013 Motivation: Enable efficient, long-term high temperature heat transfer using molten salts • SunShot program seeks major price reductions • Higher temperature energy conversion allows for better thermodynamic efficiencies • Temp. Range for Study: 800 – 1000 °C • Limited number of options for very high temperature heat transfer – Steam or other gases • Large pipe diameters needed • Large pumping power required – Molten Glass • Viscous • Low thermal conductivities – Liquid metals • Limited operating temperature range • Alloying with piping materials • Vapor pressures – Molten Salts • Heat transfer behavior at 700 °C similar to water at 20 °C Image Source: NREL, available: http://earthobservatory.nasa.gov/Features/RenewableEnergy/Images/solar_two.jpg Table Source: SAND2011-2419 3 April 1st , 2013 Goals and Objectives • Goal #1 – Identify molten salt / material combinations that have long service life and meet performance