DOCSLIB.ORG

Hheat Pipe Technology

Total Page：16

File Type：pdf, Size：1020Kb

Download full-text PDF Read full-text
Hheat Pipe Technology I ......... HHEAT PIPE TECHNOLOGY CUMULATIVE VOLUME March 1971 (NASA-CR-135953) HEAT PIPE TECHNOLOGY: N73-3390 A BIBLIOGRAPHY WITH ABSTRACTS Cumulative Volume (New Mexico Univ.) --239 p HC $14.00 CSCL 20M Unclas G3/33 15822 TECHNOLOGY APPLICATION CENTER THE UNIVERSITY OF NEW MEXICO ALBUQUERQUE, NEW MEXICO 87106 TAC BIBLIOGRAPHIC SERIES NUMBER I TAC-BIBL- (71/1) L HEAT PIPE TECHNOLOGY A BIBLIOGRAPHY WITH ABSTRACTS CUMULATIVE VOLUME March 31, 1971 ASSEMBLED BY THE HEAT PIPE INFORMATION OFFICE of THE TECHNOLOGY APPLICATION CENTER INSTITUTE FOR SOCIAL RESEARCH & DEVELOPMENT THE UNIVERSITY OF NEW MEXICO ALBUQUERQUE, NEW MEXICO REPRODUCTION RESTRICTIONS OVERRIDDEN U NASA Scientifio and Technical Information Facility I COPYRIGHT @ , 1971 by THE TECHNOLOGY APPLICATION CENTER UNIVERSITY OF NEW MEXICO The publisher reserves all rights to reproduce this book, in whole or in part, with the exception of the right to use short quotations for review of the book. REPRODUCTION RESTRICTIONS OVERRIDDEN NASA Scientific and Technical Information Facility /.,x PRECEDING PAGE BLANK NOT FIL~ED PREFACE During the era since the launching of the first Sputnik, Americans have risen to the challenge of space exploration with vast scientific and technical research programs. Recog- nizing the fact that much of this space research and develop- ment might prove valuable to the general public and commercial enterprises, NASA's Technology Utilization Program developed a system of six centers for disseminating the results of this re- search. The Technology Application Center at The University of New Mexico is the center serving the Rocky Mountain Southwest. Its mission is to promote the beneficial use of new technology. One of the activities of the Technology Application Center has been to identify new, high-interest areas of technology and to assemble and update abstract volumes on these subjects. Dr. K. T. Feldman, Jr., of the College of Engineering, Josef E. Spitzer, an Applications Engineer at the Technology Application Center, and Eugene Burch, Assistant Director of the Center, con- ceived the idea of a comprehensive reference to the area of Heat Pipe Technology, which would be kept up-to-date by the Center's wide contacts in heat pipe research. This volume is the product of that concept. Today, the engineer or scientist who is not constantly keep- ing himself aware of new developments in his field of expertise soon finds his knowledge obsolete. In addition, estimates indi- cate that at least 10 percent of our Nation's $12.5-billion-plus research-and-development expenditures is spent on duplication of previous efforts. To meet these challenges in an area of declin- ing research budgets and tremendous environmental problems, we at the Technology Application Center are sincerely committed to a continuous interaction with those forward-looking individuals, companies, and industries seeking to develop a better nation and world. William A. Shinnick Director Technology Application Center University of New Mexico 111 PRECEDING PAGE BLANK NOT FILMED INTRODUCTION Since the invention of the modern heat pipe at Los Alamos in 1963, the growth of information on pipes has been rapid and diffused. At the present time, publications on heat pipe are increasing at a rate of about 200 per year. Consequently, a considerable number of important references may not be widely known and may be difficult to obtain. Examples of such refer- ences include government laboratory reports, industrial con- tractor reports, university research reports, and some journal articles. Recognizing the need for complete and up-to-date informa- tion on heat pipes, the Heat Pipe Information Office was es- tablished at The University of New Mexico. The most modern literature-search techniques as well as the assistance of many workers in the field have been used to compile an extensive bibliography with abstracts on all types of heat pipe refer- ences including patents. Also, a library containing essential- ly all of these articles has been established. In addition to publishing this bibliography with abstracts, the Heat Pipe In- formation Office will publish a quarterly update of the bibli- ography and will provide copies of references. Some foreign references have been translated into English. Although a considerable effort has been made to insure that the bibliography is complete, readers are encouraged to notify the Office of omissions. K. T. Feldman, Jr. Technical Editor Professor of Mechanical Engineering Director of Cooperative Educational Program School of Engineering University of New Mexico v FIL ED PRECEDING PAGE BLANK NOT ACKNOWLEDGEMENTS This volume is, in large part, based on the efforts of Josef Spitzer, who devoted a vast amount of time and energy in preparing, editing, and promoting Heat Pipe Technology, and to Dr. K. T. Feldman, Jr., the technical editor, whose bibliographies, documents, and encouragement and guidance assisted in the success of this effort. Appreciation is ex- tended to Mr. Monte F. Mott, Chief of the Patents and Tech- nology Utilization Division of the NASA Pasadena Office, whose collection of Heat Pipe Patents was made available for this work. The cooperation of Dr. C. A. Busse of EURATOM and his efforts in collecting and announcing papers and ref- erences in the European sector were extremely helpful. Thanks are further extended to staff members of the Technology Application Center, Walter W. Long, Associate Director; Mark Money, Administrative Officer; and especially to Eugene Burch, Assistant Director, all of whom participated in the successful publication of this volume. This publication was further made possible by the Tech- nology Utilization Program of NASA, from which the Technology Application Center derives the major portion of its support, and by the close cooperation of the College of Engineering of The University of New Mexico. W.A.S. vii PRECEDING PAGE BLANK NOT FILMFED CONTENTS PREFACE INTRODUCTION ACKNOWLEDGEMENTS A. GENERAL INFORMATION, REVIEWS, SURVEYS B. HEAT PIPE APPLICATIONS B.1 General Applications B.2 Thermionic and Thermoelectric Converters B.3 Aerospace Oriented Applications B.4 Nuclear Systems B.5 Electronic Applications C. HEAT PIPE THEORY C.1 General Theory C.2 Heat Transfer C.3 Condensation and Evaporation C.4 Fluid Flow D. DESIGN AND FABRICATION D.1 General D.2 Wicks D.3 Materials E. TESTING AND OPERATION F. SUBJECT AND AUTHOR INDEX F.1 Bibliography F.2 Subject Index F.3 Author Index G. HEAT PIPE RELATED PATENTS G.1 Patents G.2 Subject Index G.3 Author Index G.4 Patent Number Index ix A. GENERAL INFORMATION, REVIEWS, SURVEYS 65001 THEORY OF HEAT PIPES Los Alamos Scientific Lab., N. Mex., T. P. Cotter, 26 Mar. 1965, 36 p refs (Contract W-7405-ENG-36), (LA-3246-MS) Avail:TAC A heat pipe is a self-contained structure which achieves very high thermal con- ductance by means of two-phase fluid flow with capillary circulation. A quantitative engineering theory for the design and performance analysis of heat pipes is given. 65002 ON THE OPERATION OF HEAT PIPES B. D. Marcus, Applied Thermodynamics Dept. Physical Electronics Laboratory - Physical Research Div., TRW Space Technology Laboratories, Redondo Beach, Cal. (9895-6001-TU- 000) 19 p 4 refs Avail:TAC Description of a heat pipe and analysis of the transfer processes involved. A heat pipe is a closed system capable of transferring large quantities of thermal en- ergy between a source and sink which exhibit only a small temperature difference. Hy- pothesized external and internal heat pipe configurations are diagrammed and the opti- mum wick thickness is considered. Included are a description of nomenclature and ap- pendices on contact angles and thermal conductivities. 66001 SURVEY OF LOS ALAMOS AND EURATOM HEAT PIPE INVESTIGATIONS Los Alamos Scientific Lab., N. Mex., W. A. Ranken and J. E. Kemme [1965], 12 p refs Presented at the IEEE Thermionic Conversion Specialist Conf., San Diego, Calif. (Con- tract W-7405-ENG-36), (LA-DC-7555: CONF-651049-3) Avail:TAC A review is presented of investigations of heat pipes for thermionic diode uses. The theory of heat pipes is presented. Experimentally obtained properties of heat pipes and several possible pipe designs are discussed. 66002 EVAPORATION-CONDENSATION HEAT TRANSFER DEVICE Grover, George M. (to U.S. Atomic Energy Commission). U.S. Patent 3,229,759. Jan. 18, 1966. A heat transfer device comprising a sealed tube of niobium-l% zirconium alloy, the inside surface of the tube being, for the most part, covered by capillary means and a small amount of lithium wetting the capillary means is described. 67001 PROCEEDINGS OF JOINT ATOMIC ENERGY COMMISSION/SANDIA LABORATORIES HEAT PIPE CONFERENCE, VOLUME I Sandia Corp., Albuquerque, N. Mex., Space Isotope Power Dept., Oct. 1966, 91 p refs Conf. Held in Albuquerque, N. Mex., 1 Jun 1966 (Contract AT(29-1)-789), (SC-M-66-623: CONF-660645) Avail:TAC CONTENTS: 1. STATUS OF THE ENGINEERING THEORY OF HEAT PIPES, T. R. Cotter (Los Alamos Sci- entific Lab), p 5-9 (See N67-26792 14-33) 2. HEAT PIPE CAPABILITY EXPERIMENTS, J. E. Kemme (Los Alamos Scientific Lab), p 11-25 refs (See N67-26793-14-33) 3. OPERATING LIMITS OF THE HEAT PIPE, A. Carnesale, A. H. Cosgrove, and J. K. Ferrell (N. Carolina State Coll.) p 27-44 refs (See N67-26794 14-33) 4. FEASIBILITY STUDIES OF SPACE RADIATORS USING VAPOR CHAMBER FINS, H. C. Haller and S. Lieblein (NASA Lewis Res. Center) p 47-67 refs (See N67-26795 14-33) 5. NOTES ON HEAT PIPES AND VAPOR CHAMBERS AND THEIR APPLICATION TO THERMAL CON- TROL OF SPACECRAFT, S. Katzoff (NASA Langley Res. Center) p 69-89 refs (See N67-26796 14-33) 67002 HEAT PIPE ANALYSIS G. H. Parker (Westinghouse Electric Corp., Pittsburgh, Pa.) and J. P. Hanson (Pennsyl- vania, University, Philadelphia, Pa.) Avail:TAC IN: ADVANCES IN ENERGY CONVERSION ENGINEERING; AMERICAN SOCIETY OF MECHANICAL ENGINEERS, INTERSOCIETY ENERGY CONVERSION ENGINEERING CONFERENCE, MIAMI BEACH, FLA., AUGUST 13-17, 1967, PAPERS.
Load more

Recommended publications
  • WASH-1097.Pdf
    WASH 1097 UC-80 THE USE OF THORIUM IN NUCLEAR POWER REACTORS JUNE 1969 PREPARED BY Brookhaven National Laboratory AND THE Division of Reactor Development and Technology WITH THE ASSISTANCE OF ARGONNE NATIONAL LABORATORY BABCOCK & WILCOX GULF GENERAL ATOMIC OAK RIDGE NATIONAL LABORATORY PACIFIC NORTHWEST LABORATORY For sale by the Superintendent of Documents, U.S. Government Printing Office Washington, D.C. 20402 - Price $1.25 FOREWORD This report on "The Use of Thorium in Nuclear Power Reactors" was prepared under the direction of the Division of Reactor Development and Technology, U.S.A.E.C., as part of an overall assessment of the Civilian Nuclear Power Program initiated in response to a request in 1966 by the Joint Committee on Atomic Energy. It represents the results of the inquiry by the Thorium Systems Task Force whose membership included representatives of Babcock & Wilcox Company, Gulf General Atomic Company, the Argonne National Laboratory, the Brookhaven National Laboratory, the Oak Ridge National Laboratory, the Pacific Northwest Laboratory, and the U.S. Atomic Energy Commission. Publication of this report, which provides information basic to the AEC reactor development program, completes one phase of the evaluation effort outlined in the 1967 Supplement to the 1962 Report to the President on Civilian Nuclear Power, issued in February 1967. The 1967 Supplement outlined changes since 1962 in the technical, economic and resource picture and provided background for further study. Specifically, this report represents the consensus of the task force on the potential use of the thorium cycle and the specific thorium fueled reactor designs which have been proposed.
    [Show full text]
  • Eighth World Conference on Nondestructive Testing Huitieme Conference Moiudiale Sur Les Essais Non Destructifs
    ./ 1ÍOIS_ UJ._ EIGHTH WORLD CONFERENCE ON NONDESTRUCTIVE TESTING HUITIEME CONFERENCE MOIUDIALE SUR LES ESSAIS NON DESTRUCTIFS A NONDESTRUCTIVE EXAMINATION PROGRAM FOR UNCLAD CARBON-COMPOSITE REACTOR FUEL ELEMENTS UN PROGRAMME D'KSSAIS NON DESTRUCTIFS POUR LES ELEMENTS COMBUSTIBLES DE REACTEUR NON GAINÊS EN COMPOSITE DU CARBONE FULLBRIGHT H. J. LOS ALAMOS, NEW MEXICO LOS ALAMOS SCIENTIFIC LABORATORY U. S. A. SUMMARY- ^ non<lestructive testing program for the examination of (U,Zr)C—C reactor fuel elements is described. RESUME :O n décrit un programme d'essais non destructifs pour examiner les elements combustibles de réacteur en (U.Zr)C-C. I. INTRODUCTION The Los Alamos Scientific Laboratory has been active for the past twenty years in the development and testing of graphitic-based high temperature reactor fuel elements. The initial involvement was in the field of nuclear propulsion systems. Project Rover began as a program to develop a nuclear-powered, hydrogen-propelled rocket engine. The target exhaust temperature of the propellant was about 2775 K. The fuel element for such an engine would have to maintain its integrity and strength at higher temperatures and would have to resist currosion by the hot hydrogen gas, which is very reactive. These constraints limited the choice of materials to a very few. Carbon melts above about 3800 K, has excellent high-tenperature strength, and is not a strong neutron absorber. It is very reactive to high temperature hydrogen. The basic fuel element foi the Rover Program became uranium-loaded graphite. The enriched uranium fuel was incorporated into the graphite matrix as uranium oxide, later as py- rolytic-carbon coated uranium dicarbide inicrospheres, and, aosf recently, as a solid solution of uranium carbide and zirconium carbide.
    [Show full text]
  • Quantities of Fissile Materials in US and Soviet
    Quantities of Fissile Materials in --US and Soviet ~uclearWeapons Arsenals * Frank von Hippel David H. ~lbri~ht+ Barbara G. Levi PU/CEES Report No. 168 July 1986 * Also Woodrow Wilson School of Public and International Affairs, Princeton University . + Also Federation of American Scientists, 307 Massachusetts Ave. N.E., Washington, DC 20002. Center for Energy and Environmental Studies The Engineering Quadrangle Princeton University Princeton, NJ 08544 TABLE OF CONTENTS a I. INTRODUCTION 11. US STOCKPILE OF WEAPON-GRADE URANIUM 111. US STOCKPILE OF WEAPON-GRADE PLUTONIUM a IV. DISPOSITION OF THE US GOVERNMENT'S STOCKPILE OF NATURAL URANIUM V. SOVIET STOCKPILE OF PLUTONIUM I. INTRODUCTION --TABLE OF CONTENTS History of the Proposal to Cut Off the Production of Fissile Material for Nuclear Weapons a The Verifiability of a Fissile Cutoff The Importance of Knowing the Amounts of Fissile Materials Already in the Nuclear Arsenals 2 REFERENCES Table 1-1. The Amounts of Fissile Material in the US Weapons Stockpile and An Upper-Bound Estimate of the Amount of Separated Plutonium in the USSR I. INTRODUCTION History of the Proposal to Cut Off the Production -of Fissile Material for Nuclear Weapons Although the original nuclear weapons control proposals such as the 1946 Baruch Plan - focused on the control of nuclear weapons materials, recent arms control negotiations have focused principally on the control of long-range nuclear weapons delivery systems. This has been in part due to the shift in the focus of the nuclear arms race from the quantitative to the qualitative. In part also it resulted from the Soviet Union's reluctance to allow intrusive verification arrangements.
    [Show full text]
  • Ultra High Temperature Reactor Critical Experiment (Ucx) Safety Analysis Report
    r-- Cs ‘iA-:279 CL-I 4 FIE~ORT COLLECTION IREYRODUCTIQN COPY LOS ALAMOS SCIENTIFIC LABORATORY LOS ALAMOS of the ~ NEW MEXICO University of California ULTRA HIGH TEMPERATURE REACTOR CRITICAL EXPERIMENT (UCX) SAFETY ANALYSIS REPORT J— UNITED STATES ATOMIC ENERGY COMMISSION CONTRACT W-7405 -ENG. 36 ,— LEGAL NO TIC E-I This report was prepared as an account of Government sponsored work. Neither the United States, nor the Commission, nor any person acting on behalf of the Commission: A. Makea any warranty or representation, expressed or implied, with respect to the accu- racy, completeness, or usefulness of tbe information contatned in this report, or that the use of any information, apparatus, method, or process disclosed In this report may not Infringe privately owned rights; or B. Assumes any liabilities with respect to the use of, or for damages resulting from the use of any information, apparatus, method, or process disclosed in this report. As used in the above, “person acttng on behalf of the Commission” includes any em- ployee or contractor of the Commission, or employee of such contractor, to the extent that such employee or contractor of the Commission, or employee of such contractor prepares, disseminates, or provides access to, any information pursuant to his employment or contract with the Commteeion, or MS employment with such contractor. Printed in USA. Price $4.00. Availablefrom the Clearinghousefor Federal Scientific and Technical Information, NationalBureau of Standards, U. S. Department of Commerce, Springfield,Virginia LA-3279 UC-80, REACTOR TECHNOLOGY TID-4500 (38thEd.) LOS ALAMOS SCIENTIFIC LABORATORY LOS ALAMOS of the> NEW MEXICO University of California Report written: March 1965 Report distributed:March 31, 1965 ULTRA HIGH TEMPERATURE REACTOR CRITICAL EXPERIMENT (UCX) SAFETY ANALYSIS REPORT Prepared By K-Division o 9 I AESTRACT The UHTREX Critical Experiment uses the core, reflector, fuel elements, and control rod materials of UHTREX to produce data for the verification of nuclear design calculations.
    [Show full text]
  • Nuclear Fuels and Reprocessing Technologies: a US Perspective
    INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective March 2021 Guy Fredrickson Tae-Sic Yoo 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, trademark, 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. INL/EXT-20-59106 Review – Nuclear Fuels and Reprocessing Technologies: A U.S. Perspective Guy Fredrickson Tae-Sic Yoo March 2021 Idaho National Laboratory Pyrochemistry & Molten Salt Systems Department 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 Page intentionally left blank ABSTRACT Reprocessing and/or waste management issues are of concern to the “back end” of the nuclear fuel cycle. Of course, there are a great many “nuclear fuel cycle” scenarios to consider; if not in practice, then at least in theory. The simplest conceptually is the “once through” fuel cycle in which the spent fuel is discarded.
    [Show full text]
  • NRC Collection of Abbreviations
    I Nuclear Regulatory Commission c ElLc LI El LIL El, EEELIILE El ClV. El El, El1 ....... I -4 PI AVAILABILITY NOTICE Availability of Reference Materials Cited in NRC Publications Most documents cited in NRC publications will be available from one of the following sources: 1. The NRC Public Document Room, 2120 L Street, NW., Lower Level, Washington, DC 20555-0001 2. The Superintendent of Documents, U.S. Government Printing Office, P. 0. Box 37082, Washington, DC 20402-9328 3. The National Technical Information Service, Springfield, VA 22161-0002 Although the listing that follows represents the majority of documents cited in NRC publica- tions, it is not intended to be exhaustive. Referenced documents available for inspection and copying for a fee from the NRC Public Document Room include NRC correspondence and internal NRC memoranda; NRC bulletins, circulars, information notices, inspection and investigation notices; licensee event reports; vendor reports and correspondence; Commission papers; and applicant and licensee docu- ments and correspondence. The following documents in the NUREG series are available for purchase from the Government Printing Office: formal NRC staff and contractor reports, NRC-sponsored conference pro- ceedings, international agreement reports, grantee reports, and NRC booklets and bro- chures. Also available are regulatory guides, NRC regulations in the Code of Federal Regula- tions, and Nuclear Regulatory Commission Issuances. Documents available from the National Technical Information Service Include NUREG-series reports and technical reports prepared by other Federal agencies and reports prepared by the Atomic Energy Commission, forerunner agency to the Nuclear Regulatory Commission. Documents available from public and special technical libraries include all open literature items, such as books, journal articles, and transactions.
    [Show full text]
  • Pacific Northwest National Laboratory Operated by Battelle for the U.S
    PNNL-11510 UC-2050 Pacific Northwest National Laboratory Operated by Battelle for the U.S. Department of Energy U.S. Graphite Reactor D&D Experience APR 14 1997 OSTI S.M.K. Garrett N. C. Williams February 1997 "0 Z Z T Prepared for the U.S. Department of Energy under Contract DE-AC06-76RLO1830 DISCLAIMER 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 Battelle Memorial Institute, 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. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof, or Battelle Memorial Institute. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. PACIFIC NORTHWEST LABORATORY operated by BATTELLE MEMORIAL INSTITUTE for the UNITED STATES DEPARTMENT OF ENERGY under Contract DE-AC06-76RLO 1830 ' This document was printed on recycled paper. PNNL-11510 UC-2050 U.S. Graphite Reactor D&D Experience S.M.K. Garrett N. C. Williams DISCLAIMER This report was prepared as an account of work sponsored by an agency of the United States Government.
    [Show full text]
  • Restricted Data Declassification Decisions 1946 to the Present (RDD 8)
    OFFICIAL USE ONLY RESTRICTED DATA DECLASSIFICATION DECISIONS 1946 TO THE PRESENT (RDD-8) January 1, 2002 U.S. Department of Energy Office of Health, Safety and Security Office of Classification Contains information which may be exempt from public release under the Freedom of Information Act (5 U.S.C. 552), exemption number(s) 2. Approval by the Department of Energy prior to public release is required. Reviewed by: Richard J. Lyons Date: 3/20/2002 NOTICE This document provides historical perspective on the sequence of declassification actions performed by the Department of Energy and its predecessor agencies. It is meant to convey the amount and types of information declassified over the years. Although the language of the original declassification authorities is cited verbatim as much as possible to preserve the historical intent of the declassification, THIS DOCUMENT IS NOT TO BE USED AS THE BASIS FOR DECLASSIFYING DOCUMENTS AND MATERIALS without specific authorization from the Director, Information Classification and Control Policy. Classification guides designed for that specific purpose must be used. OFFICIAL USE ONLY OFFICIAL USE ONLY This page intentionally left blank OFFICIAL USE ONLY OFFICIAL USE ONLY FOREWORD This document supersedes Restricted Data Declassification Decisions - 1946 To The Present (RDD-7), January 1, 2001. This is the eighth edition of a document first published in June 1994. This latest edition includes editorial corrections to RDD-7, all declassification actions that have been made since the January 1, 2001, publication date of RDD-7 and any additional declassification actions which were subsequently discovered or confirmed. Note that the terms “declassification” or “declassification action,” as used in this document, refer to changes in classification policy which result in a specific fact or concept that was classified in the past being now unclassified.
    [Show full text]
  • Porosity Effect in the Core Thermal Hydraulics for Ultra High Temperature Gas-Cooled Reactor
    Porosity Effect in the Core Thermal Hydraulics for Ultra High Temperature Gas-cooled Reactor Motoo FUMIZAWA Department of Mechanical Systems Engineering, Shonan Institute of Technology 1-1-25 Tsujido-Nishikaigan, Fujisawa, Kanagawa 251-8511 Japan Yoshihiko KANEKO Department of Energy Science and Nuclear Engineering, Musashi Institute of Technology, Japan Masanori IZUMI Japan Atomic Energy Agency, Japan Abstract ∆Tsl(z): temperature difference between fuel matrix surface and fuel element surface; (oC) This study presents an experimental method of porosity evaluation and a predictive thermal-hydraulic analysis with packed spheres in a nuclear reactor core. The porosity 1. Introduction experiments were carried out in both a fully shaken state with the closest possible packing and in a state of non-vibration. The Nowadays, the very high temperature gas-cooled reactor predictive analysis considering the fixed porosity value was projects, or so called GIF (Generation IV International Forum), applied as a design condition for an Ultra High Temperature is energetically developing design studies to establish 1,000 oC Reactor Experiment (UHTREX). The thermal-hydraulic as a coolant outlet temperature and to realize hydrogen computer code was developed and identified as PEBTEMP. production [1-2]. Over an extended period, a fundamental The highest outlet coolant temperature of 1316 oC was design studies have been carried out in the field of high achieved in the case of an UHTREX at Los Alamos Scientific temperature gas-cooled reactors, or HTGR’s [3-8], which show Laboratory, which was a small scale UHTR. In the present that the coolant outlet temperature was around 900 oC. Interest study, the fuel was changed to a pebble type, a porous media.
    [Show full text]
  • Hydrogen Production Using Nuclear Energy No
    IAEA Nuclear Energy Series IAEA Nuclear No. NP-T-4.2No. Energy Hydrogen Production Using Nuclear IAEA Nuclear Energy Series No. NP-T-4.2 Basic Hydrogen Production Principles Using Nuclear Energy Objectives Guides Technical Reports INTERNATIONAL ATOMIC ENERGY AGENCY VIENNA ISBN 978–92–0–135110–4 ISSN 1995–7807 IAEA NUCLEAR ENERGY SERIES PUBLICATIONS STRUCTURE OF THE IAEA NUCLEAR ENERGY SERIES Under the terms of Articles III.A and VIII.C of its Statute, the IAEA is authorized to foster the exchange of scientific and technical information on the peaceful uses of atomic energy. The publications in the IAEA Nuclear Energy Series provide information in the areas of nuclear power, nuclear fuel cycle, radioactive waste management and decommissioning, and on general issues that are relevant to all of the above mentioned areas. The structure of the IAEA Nuclear Energy Series comprises three levels: 1 — Basic Principles and Objectives; 2 — Guides; and 3 — Technical Reports. The Nuclear Energy Basic Principles publication describes the rationale and vision for the peaceful uses of nuclear energy. Nuclear Energy Series Objectives publications explain the expectations to be met in various areas at different stages of implementation. Nuclear Energy Series Guides provide high level guidance on how to achieve the objectives related to the various topics and areas involving the peaceful uses of nuclear energy. Nuclear Energy Series Technical Reports provide additional, more detailed, information on activities related to the various areas dealt with in the IAEA Nuclear Energy Series. The IAEA Nuclear Energy Series publications are coded as follows: NG — general; NP — nuclear power; NF — nuclear fuel; NW — radioactive waste management and decommissioning.
    [Show full text]
  • The Times They Were a Changin'
    the Agnew Years The Times They Were a Changin’ regain the initiative in weapons development that we’d lost to Livermore. In 1970 this Laboratory was still largely a weapons lab, but Livermore was doing a better. more aggressive selling job and was pushing for the enhanced radiation weapons and all the strategic weapons—the nuclear warheads for Minuteman and Polaris. Their reputation was better than ours, or at least perceived to be so by some people. Harold’s vision was to restore the luster that Los Alamos had lost. It’s true that he thought the Laboratory was premier in all fields and he would undertake anything, but above all he wanted to be first in our principal mission of weapons develop- ment, SCHREIBER: There’s another aspect to the Bradbury-Agnew transition that I feel is also important to recognize, At the end of World War 11, when Norris became Director, a lot of people who had served during the war years on Laboratory advisory boards simply disappeared. Norris really didn’t have an Raemer Schreiber (left) joined the Laboratory in 1943. In the ’50s he was the Leader existing management structure to work with, of the Weapons and the Nuclear Propulsion divisions and then, in 1961, was so he was able to start with a clean slate. appointed Technical Associate Director. He remained in that position after Agnew Twenty-five years later the Laboratory was became Director until “Harold, in 1972, decided I was really Deputy Director, so he firmly established, and Norris was working changed my title.
    [Show full text]
  • Massoud T. Simnad Papers
    http://oac.cdlib.org/findaid/ark:/13030/kt467nf3ms No online items Massoud T. Simnad Papers Special Collections & Archives, UC San Diego Special Collections & Archives, UC San Diego Copyright 2011 9500 Gilman Drive La Jolla 92093-0175 [email protected] URL: http://libraries.ucsd.edu/collections/sca/index.html Massoud T. Simnad Papers MSS 0577 1 Descriptive Summary Languages: English Contributing Institution: Special Collections & Archives, UC San Diego 9500 Gilman Drive La Jolla 92093-0175 Title: Massoud T. Simnad Papers Identifier/Call Number: MSS 0577 Physical Description: 8 Linear feet(20 archive boxes and 2 oversize folders) Date (inclusive): 1960-2002 Abstract: Papers of Massoud T. Simnad (1921-2002), an engineer in nuclear energy and UCSD adjunct professor of materials science and engineering. The collection documents Simnad's work in the field of nuclear reactor technologies and superconductivity and contains files related to his research, consulting, journal articles, grant proposals, and conference papers. Acquisition Information Acquired 2002. Preferred Citation Massoud T. Simnad Papers, MSS 577. Special Collections & Archives, UC San Diego. Biography Massoud T. Simnad was born in Iran in 1921 and grew up in Istanbul. At the age of 15, he left Istanbul for London where he studied mining engineering at London University's Imperial College of Science and Technology. He earned his B.S. in 1942 and his Ph.D in 1946 at Cambridge University specializing in materials science. After graduation he accepted a guest fellowship at the Carnegie-Mellon University in Pittsburgh. From 1949, Simnad lived in the U.S. and served as an educator, technical adviser, and consultant to various academic institutions and scientific corporations.
    [Show full text]