ABSTRACT ZHU, YUWEI. Analysis of Neutron Thermalization in Liquid
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Topical Report Submittal Reactor Coolant for the Kairos Power Fluoride Salt-Cooled High Temperature Reactor
KP-NRC-1903-002 March 8, 2019 Project No. 99902069 US Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Subject: Kairos Power LLC Topical Report Submittal Reactor Coolant for the Kairos Power Fluoride Salt-Cooled High Temperature Reactor This letter submits the subject topical report which provides specification information and thermophysical properties for reactor coolant for the Kairos Power Fluoride Salt-Cooled, High Temperature Reactor (KP-FHR). This topical report is provided for NRC review and approval and is expected to be referenced by future license applicants using the KP-FHR. The scope and schedule for submittal of this report was discussed in a closed meeting with NRC staff January 16, 2019. Kairos Power respectfully requests NRC acceptance review be completed and a review schedule be provided within 60 days of the receipt of this letter. In recognition of an aggressive deployment schedule and substantial pre-application engagement, Kairos Power has established a generic assumption of a 12-month review for topical reports. Portions of the attached report are considered proprietary, and Kairos Power requests it be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390. Enclosure 1 provides the proprietary version of the report and Enclosure 2 provides the non-proprietary report. An affidavit supporting the withholding request is provided in Enclosure 3. Additionally, the information indicated as proprietary has also been determined to contain Export Controlled Information. This information must be protected from disclosure pursuant to the requirements of 10 CFR 810. If you have any questions or need any additional information, please contact Darrell Gardner at [email protected] or (704) 604-6064. -
Measured Enthalpy and Derived Thermodynamic Properties of Solid and Liquid Lithium Tetrafluoroberyllate
JOURNAL OF RESEARCH of the Notiona l Bureau of Standards-A. Ph ysics and Chemistry Vol. 73A, No.5, September- October 1969 Measured Enthalpy and Derived Thermodynamic Properties of Solid and Liquid Lithium Tetrafluoroberyllate, from 273 to 900 K 1 Thomas B. Douglas and William H. Payne 2 Institute for Basic Standards, National Bureau of Standards, Washington, D.C. 20234 (May 20, 1969) The enthalpy of a sampl e of lithium tetraAu oroberyllate, Li,BeF4 , of 98.6 percent purity was ?,easu. red re laLJ ve to 273 K a t eleven te mpe ratures from 323 to 873 K. Corrections we re appli ed fo r the Im purI li es and fo r ex t e n ~ lv e premelting below the m e lti~ g po int (745 K ). The e nthalpy and heat capacity, a nd the e ntropy a nd GIbbs free-energy functIOn rela LJ ve to the undetermined value of 5,°98 15 ' we re computed from empiri cal functIO ns of tem peratu re derived from the data and are tabuhied from 273 to 900 K. ' Key words: Drop calorimetry; enthalpy data; lithium beryllium Au oride; lithium te traAu orobe ryllate; premeltmg; th e rmodynamic properties. 1. Introduction The temperature-composition phase diagram of the condensed phases of the LiF-BeF 2 system has been As part of a long-term research program at the investigated in a number of laboratories. The version National Bureau of Standards on the thermodynamic in a fairly recent compilation of phase diagrams [3] is properties of the simpler li ght-element compounds, based on th e results of two groups of workers [4, 5]. -
"Sony Mobile Critical Substance List" At
Sony Mobile Communications Public 1(16) DIRECTIVE Document number Revision 6/034 01-LXE 110 1408 Uen C Prepared by Date SEM/CGQS JOHAN K HOLMQVIST 2014-02-20 Contents responsible if other than preparer Remarks This document is managed in metaDoc. Approved by SEM/CGQS (PER HÖKFELT) Sony Mobile Critical Substances Second Edition Contents 1 Revision history.............................................................................................3 2 Purpose.........................................................................................................3 3 Directive ........................................................................................................4 4 Application ....................................................................................................4 4.1 Terms and Definitions ...................................................................................4 5 Comply to Sony Technical Standard SS-00259............................................6 6 The Sony Mobile list of Critical substances in products................................6 7 The Sony Mobile list of Restricted substances in products...........................7 8 The Sony Mobile list of Monitored substances .............................................8 It is the responsibility of the user to ensure that they have a correct and valid version. Any outdated hard copy is invalid and must be removed from possible use. Public 2(16) DIRECTIVE Document number Revision 6/034 01-LXE 110 1408 Uen C Substance control Sustainability is the backbone -
1462 Element of Month Beryllium
All About Elements: Beryllium 1 Ward’s All About Elements Series Fun Facts Building Real-World Connections to About… 4 the Building Blocks of Chemistry Beryllium PERIODIC TABLE OF THE ELEMENTS 1. Prior to being named beryllium, this element GROUP 1/IA 18/VIIIA 1 2 was known as glucinium, which originated H KEY He from the Greek word glykys, meaning sweet. Atomic Number 1.01 2/IIA 35 13/IIIA 14/IVA 15/VA 16/VIA 17/VIIA 4.00 3 4 5 6 7 8 9 10 Symbol It was so named due to it characteristic Li Be Br B C N O F Ne 6.94 9.01 79.90 Atomic Weight 10.81 12.01 14.01 16.00 19.00 20.18 11 12 13 14 15 16 17 18 sweet taste. Na Mg Al Si P S Cl Ar 8 9 10 22.99 24.31 3/IIIB 4/IVB 5/VB 6/VIB 7/VIIB VIIIBVIII 11/IB 12/IIB 26.98 28.09 30.97 32.07 35.45 39.95 19 20 21 22 23 24 25 26 27 28 29 30 31 32 33 34 35 36 Be K Ca Sc Ti V Cr Mn Fe Co Ni Cu Zn Ga Ge As Se Br Kr 2. Emerald, morganite and aquamarine are 39.10 40.08 44.96 47.87 50.94 52.00 54.94 55.85 58.93 58.69 63.55 65.41 69.72 72.64 74.92 78.9678.96 79.90 83.80 37 38 39 40 41 42 43 44 45 46 47 48 49 50 51 52 53 54 precious forms of beryl. -
Guideline Ver6.2 Se Ria L No. CAS RN® Substance Group 1 Substance
Guideline Ver6.2 Rank CAS RN® Substance Group 1 Substance Group 2 Substance Name 1=Prohibited No. Serial 2=Reduction 1 124-73-2 ozone depleting substances(Halons) Ethane, 1,2-dibromo-1,1,2,2-tetrafluoro- 1 2 25497-30-7 ozone depleting substances(Halons) Dibromotetrafluoroethane 1 3 27336-23-8 ozone depleting substances(Halons) Dibromotetrafluoroethane,compressed 1 4 353-59-3 ozone depleting substances(Halons) Methane, bromochlorodifluoro- 1 5 354-56-3 ozone depleting substances(Halons) Ethane, pentachlorofluoro- 1 6 75-61-6 ozone depleting substances(Halons) Methane, dibromodifluoro- 1 7 75-63-8 ozone depleting substances(Halons) Methane, bromotrifluoro- 1 8 110003-27-5 ozone depleting substances(HBFCs) 1,3-dibromo-1,1,2-trifluoropropane 1 9 111483-20-6 ozone depleting substances(HBFCs) 1-bromo-2,3-difluoropropane 1 10 124-72-1 ozone depleting substances(HBFCs) 2-bromo-1,1,1,2-tetrafluoroethane 1 11 148875-95-0 ozone depleting substances(HBFCs) C3H3FBr4 1 12 148875-98-3 ozone depleting substances(HBFCs) C3H2F2Br4 1 13 1511-62-2 ozone depleting substances(HBFCs) Methane, bromodifluoro- 1 14 172912-75-3 ozone depleting substances(HBFCs) HBFC-131 B3 Tribromofluoroethane 1 15 1800-81-3 ozone depleting substances(HBFCs) 1-bromo-1,2-difluoroethane 1 16 1868-53-7 ozone depleting substances(HBFCs) Dibromofluoromethane 1 17 1871-72-3 ozone depleting substances(HBFCs) FLUOROBROMOPROPANE 1 18 2252-78-0 ozone depleting substances(HBFCs) 1-Bromo-1,1,2,3,3,3-hexafluoropropane 1 19 2252-79-1 ozone depleting substances(HBFCs) 2-bromo-1,1,1,3,3,3-hexafluoropropane -
Fluoride Salt Coolant Properties for Nuclear Reactor Applications: a Review
Fluoride salt coolant properties for nuclear reactor applications: A review The MIT Faculty has made this article openly available. Please share how this access benefits you. Your story matters. Citation Romatoski, R. R. and L.W. HU. "Fluoride salt coolant properties for nuclear reactor applications: A review." Annals of Nuclear Energy 109 (November 2017): 635-647 As Published http://dx.doi.org/10.1016/j.anucene.2017.05.036 Publisher Elsevier BV Version Author's final manuscript Citable link https://hdl.handle.net/1721.1/123988 Terms of Use Creative Commons Attribution-NonCommercial-NoDerivs License Detailed Terms http://creativecommons.org/licenses/by-nc-nd/4.0/ Fluoride salt coolant properties for nuclear reactor applications: A review R.R. Romatoskia and L.W. Hua,* a MASSACHUSETTS INSTITUTE OF TECHNOLOGY, NW12-220, 77 MASSACHUSETTS AVE., CAMBRIDGE, MA 02139 * Corresponding author E-mail addresses: [email protected] (R.R. Romatoski), [email protected] (L.W. Hu) ABSTRACT Fluoride salts are crucial to achieving the benefits of Fluoride-salt-cooled High-temperature Reactors (FHRs). Intensive studies and modeling are being performed in different countries aimed at FHR technology development. Better understanding of liquid fluoride salt coolant properties and their uncertainties are needed for design and analysis of nuclear facilities. The main objective of the present study is to perform a literature survey of the experimental data, numerical studies, reports, and other review compilations for the main thermophysical properties of liquid fluoride salts. The review recommends density, heat capacity, thermal conductivity, and viscosity properties for potential primary coolants LiF-BeF2 (flibe) and NaF-ZrF4 (nafzirf) and secondary coolant LiF-NaF-KF (flinak). -
Annex 1. Management Criteria for Substances of Environmental Concern (Automobile Products)
Annex 1. Management Criteria for Substances of Environmental Concern (Automobile Products) 1. Substances subject to management and management classifications We have adopted GADSL for our Management Criteria for Substances of Environmental Concern (Automobile Products). The management classifications and definitions for "prohibited substances" and "declarable substances" are shown in Table 1. [Precautions for use] The specific chemical substances within GADSL only enumerate some of the chemical substances that fall under their class of chemical substances. It does not regulate every chemical substance that falls under said class of chemical substances. The Japanese translation has been included for reference purposes, but there are some substances which do not have official Japanese names. The latest information on GADSL must be obtained and confirmed from the following website. [GADSL] The Global Automotive Declarable Substance List (GADSL) released by the Global Automotive Stakeholder Group (GASG) http://www.gadsl.org/ Table 1. Stanley's management classifications and definitions The reported substances contained within vehicle materials and parts have been indicated as either "P" or "D" via the following definitions. Classification Definition Target substances Response Substances that fall under Category P and those that fall under P of Category Promptly prohibit. Substances prohibited D/P of the substances of environmental from inclusion in the concern stipulated by GADSL Prohibited products, parts, materials, Four substances stipulated in the and secondary materials Prohibit all except for exempt parts European End of Life Vehicles (ELV) used at Stanley Electric stipulated in the European ELV Directive (lead, mercury, hexavalent Directive. chromium, and cadmium) Substances that must be reported to the company Substances that fall under Category D when they are used in the and those that fall under D of Category The supplier must promptly report to Declarable products, parts, materials, D/P of the substances of environmental Stanley. -
Toxicological Profile for Beryllium
TOXICOLOGICAL PROFILE FOR BERYLLIUM U.S. DEPARTMENT OF HEALTH AND HUMAN SERVICES Public Health Service Agency for Toxic Substances and Disease Registry September 2002 BERYLLIUM ii DISCLAIMER The use of company or product name(s) is for identification only and does not imply endorsement by the Agency for Toxic Substances and Disease Registry. BERYLLIUM iii UPDATE STATEMENT Toxicological profiles are revised and republished as necessary, but no less than once every three years. For information regarding the update status of previously released profiles, contact ATSDR at: Agency for Toxic Substances and Disease Registry Division of Toxicology/Toxicology Information Branch 1600 Clifton Road NE, E-29 Atlanta, Georgia 30333 V FOREWORD This toxicological profile is prepared in accordance with guidelines* developed by the Agency for Toxic Substances and Disease Registry (ATSDR) and the Environmental Protection Agency (EPA). The original guidelines were published in the Federal Register on April 17, 1987. Each profile will be revised and republished as necessary. The ATSDR to&ological profile succinctly characterizes the toxicologic and adverse health effects information for the hazardous substance described therein. Each peer-reviewed profile identifies and reviews the key literature that describes a hazardous substance's toxicologic properties. Other pertinent literature is also presented, but is described in less detail than the key studies. The profile is not intended to be an exhaustive document; however, more comprehensive sources of specialty information are referenced. The focus of the profiles is on health and toxicologic information; therefore, each toxicological profile begins with a public health statement that describes, in nontechnical language, a substance's relevant toxicological properties. -
Toxicological Review of Beryllium and Compounds
EPA/635/R-98/008 TOXICOLOGICAL REVIEW OF BERYLLIUM AND COMPOUNDS (CAS No.7440-41-7) In Support of Summary Information on the Integrated Risk Information System (IRIS) April 1998 U.S. Environmental Protection Agency Washington, DC DISCLAIMER This document has been reviewed in accordance with U.S. Environmental Protection Policy. Mention of trade names or commercial products does not constitute endorsement or recommendation for use. ii CONTENTS DISCLAIMER .............................................................ii FOREWORD ..............................................................v CONTRIBUTORS AND REVIEWERS ......................................... vi 1. INTRODUCTION ........................................................1 2. CHEMICAL AND PHYSICAL INFORMATION RELEVANT TO ASSESSMENTS ..... 2 3. TOXICOKINETICS RELEVANT TO ASSESSMENTS ...........................6 3.1. ABSORPTION ...................................................6 3.1.1. Respiratory Absorption ......................................7 3.1.2. Gastrointestinal Absorption ..................................10 3.1.3. Dermal Absorption ........................................10 3.2. DISTRIBUTION .................................................10 3.3. ELIMINATION AND EXCRETION ..................................11 4. HAZARD IDENTIFICATION ..............................................12 4.1. STUDIES IN HUMANS—EPIDEMIOLOGY, CASE REPORTS, AND CLINICAL CONTROLS .........................................12 4.1.1. Chronic Beryllium Disease ...................................12 -
1 Supplementary Information
Electronic Supplementary Material (ESI) for Journal of Materials Chemistry A. This journal is © The Royal Society of Chemistry 2021 1 Supplementary Information 2 The Impact of Hydrogen Valence on Its Bonding and Transport in Molten Fluoride Salts 3 Stephen T. Lam1,2*, Qing-Jie Li1, Jonathan Mailoa3, Charles Forsberg1, Ronald Ballinger1,4, Ju Li1,4 4 1Department of Nuclear Science and Engineering, Massachusetts Institute of Technology, Cambridge, MA 5 02139, USA 6 2Department of Chemical Engineering, University of Massachusetts Lowell, Lowell, MA 01854, USA 7 3Bosch Research and Technology Center, Cambridge, MA 02139, USA 8 4Department of Materials Science and Engineering, Massachusetts Institute of Technology, Cambridge, 9 MA 02139, USA 10 * Corresponding author: [email protected] 11 12 Supplementary Notes 13 Supplementary Note 1: Simulated versus experimental local structure of fluorides 14 For structural analysis, X-ray and neutron diffraction methods are most commonly used. In 15 polyatomic systems, the total interference function 퐹푁(푄) is decomposed into a weighted linear combination 16 of the component pair structure factors 푆훼훽(푄). Taking Fourier transforms of these structure factors, the real 17 space distribution functions 푔훼훽(푟) are determined. In practice, scattering methods for multi-component 18 systems should be coupled to simulation and other experimental methods to fully understand and resolve 19 features of the diffraction pattern [1][2][3]. 20 The fluoride salts LiF, NaF, KF, BeF2, Flibe and Flinak are simulated since they are the prototypical 21 salt and salt constituents of interest. The local structure is determined by the radial distribution function and 22 compared. Overall, there is good agreement between the simulations and experiments across a range of 23 fluorides. -
Program Plan for Development of Molten-Salt Breeder Reactors
ORNL-5018 Program Plan for Development of Molten-Salt Breeder Reactors L.E. McNeese and Staff of the Molten-Salt Reactor Program DECEMBER 1974 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the U.S. ATOMIC ENERGY COMMISSION Contents 1 Program Plan Overview 23 1.1 Introduction and Summary . 23 1.2 Status of Technology and Planned Development Activities . 24 1.2.1 Development of structural metal for primary and secondary circuits . 25 1.2.2 Fuel processing . 26 1.2.3 Fuel processing materials development . 27 1.2.4 Chemical research and development . 29 1.2.5 Analytical research and development . 30 1.2.6 Reactor safety . 31 1.2.7 Reactor design and analysis . 32 1.2.8 Graphite development . 34 1.2.9 Reactor technology development . 35 1.2.10 Maintenance . 36 1.2.11 Instrumentation and controls development . 38 1.2.12 Molten-Salt Test Reactor mockup . 38 1.2.13 Molten-Salt Test Reactor . 39 1.2.14 Molten-Salt Demonstration Reactor . 39 1.3 Key Program Milestones . 39 1.4 Estimated Fund Requirements . 40 1.5 References for Section 1 . 46 2 Development of Structural Metal for Primary and Secondary Circuits 47 2.1 Introduction . 47 2.1.1 Objective . 47 2.1.2 Scope . 48 2.2 Program Budget and Schedule . 50 2.2.1 Schedule and key program milestones . 50 2.2.2 Funding . 51 2.3 Material Requirements, Background, and Status of Development . 52 2.3.1 Material requirements . 52 2.3.2 Background . 52 2.3.3 Status of development . -
Heat Transfer Salts for Nuclear Reactor Systems – Chemistry Control, Corrosion Mitigation, and Modeling
Project No. 10-905 Heat Transfer Salts for Nuclear Reactor Systems – Chemistry Control, Corrosion Mitigation, and Modeling Reactor Concepts RD&D Dr. Mark Anderson University of Wisconsin, Madison In collaboration with: Pacific Northwest National Laboratory University of California, Berkeley Brian Robinson, Federal POC Michael McKellar, Technical POC Heat Transfer Salts for Nuclear Reactor Systems - chemistry control, corrosion mitigation and modeling CFP-10-100 Dr. Mark Anderson, Dr. Kumar Sridharan, Dr. Dane Morgan , Dr. Per Peterson, Dr. Pattrick Calderoni, Mr. Randall Scheele , Dr. Andrew Casella, Dr. Bruce McNamara, Brian Kelleher , Robert Sellers, Tony (Guiqiu) Zheng, Tommy Cisneros, Oday Albakri, Nick Kuwahara, Jun Yang, Maxwell Strassman, Arjun Kalra, William Ryan, David Pfotenhauer, Brad Motl, Paul Brooks UNIVERSITY OF WISCONSIN-MADISON, UNIVERSITY OF CALIFORNIA - BERKELEY, PACIFIC NORTHWEST NATIONAL LABORATORY i Executive Summary 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, culminating in a research reactor which operated for 15,000 hours without major error. This technical success has garnished interest in modern, high temperature, reactor schemes. Research using molten fluoride salts for nuclear applications requires a steady supply of high grade molten salts. There is no bulk supplier of research grade fluoride salts in the world, so a facility which could provide all the salt needed for testing at the University of Wisconsin had to be produced. Two salt purification devices were made for this purpose, a large scale purifier, and a small scale purifier, each designed to clean the salts from impurities and reduce their corrosion potential.