Design of an Organic Simplified Nuclear Reactor
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Molten Salts As Blanket Fluids in Controlled Fusion Reactors [Disc 6]
r1 0 R N L-TM-4047 MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes Stanley Cantor .:, .:, .- t. This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or 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. om-TM- 4047 Contract No. W-7405-eng-26 REACTOR CHENISTRY DIVISION MOLTEN SALTS AS BLANKET FLUIDS IN CONTROLLED FUSION REACTORS W. R. Grimes and Stanley Cantor DECEMBER 1972 OAK RIDGE NATIONAL LABORATORY Oak Ridge, Tennessee 37830 operated by UNION CARBIDE CORPORATION for the 1J.S. ATOMIC ENERGY COMMISSION This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the United States Atomic Energy Commission, nor any of their employees, nor any of their contractors, subcontractors, or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, com- pleteness or usefulness of any information, apparatus, product or process disclosed, or represents that its use would not infringe privately owned rights. i iii CONTENTS Page Abstract ............................. 1 Introduction ........................... 2 Behavior of Li2BeFq in a Eypothetical CTR ............3 Effects of Strong Magnetic Fields .............5 Effects on Chemical Stability .............5 Effects on Fluid Dynamics ...............7 Production of Tritium .................. -
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. -
Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety. Proceedings of the Specialists` Meeting
J — v ft INIS-mf—15B1 7 INTERNATIONAL ATOMIC ENERGY AGENCY NUCLEAR ELECTRIC Ltd. Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety PROCEEDINGS OF THE SPECIALISTS’ MEETING JOINTLY ORGANISED BY THE IAEA AND NUCLEAR ELECTRIC Ltd. AND HELD IN GLOUCESTER, UK 14-17 MAY 1996 NUCLEAR ELECTRIC Ltd. 1996 VOL INTRODUCTION The Specialists ’ Meeting on Monitoring and Diagnosis Systems to Improve Nuclear Power Plant Reliability and Safety, held in Gloucester, UK, 14 - 17 May 1996, was organised by the International Atomic Energy Agency in the framework of the International Working Group on Nuclear Power Plant Control and Instrumentation (IWG-NPPCI) and the International Task Force on NPP Diagnostics in co-operation with Nuclear Electric Ltd. The 50 participants, representing 21 Member States (Argentina, Austria, Belgium, Canada, Czech Republic, France, Germany, Hungary, Japan, Netherlands, Norway, Russian Federation, Slovak Republic, Slovenia, Spain, Sweden, Switzerland, Turkey, Ukraine, UK and USA), reviewed the current approaches in Member States in the area of monitoring and diagnosis systems. The Meeting attempted to identify advanced techniques in the field of diagnostics of electrical and mechanical components for safety and operation improvements, reviewed actual practices and experiences related to the application of those systems with special emphasis on real occurrences, exchanged current experiences with diagnostics as a means for predictive maintenance. Monitoring of the electrical and mechanical components of systems is directly associated with the performance and safety of nuclear power plants. On-line monitoring and diagnostic systems have been applied to reactor vessel internals, pumps, safety and relief valves and turbine generators. The monitoring techniques include nose analysis, vibration analysis, and loose parts detection. -
Nuclear Space Power Safety and Facility Guidelines Study
NUCLEAR SPACE POWER SAFETY AND FACILITY GUIDELINES STUDY (SEPTEMBER 1995) rss Has NUCLEAR SPACE POWER SAFETY AND FACILITY GUIDELINES STUDY (11 September 1995) Prepared for: Department of Energy Office of Procurement Assistance and Program Management HR-522.2 Washington, D.C. 20585 by: William F. Mehlman The Johns Hopkins University Applied Physics Laboratory Johns Hopkins Road Laurel, Maryland 20723-6099 in response to: Department of Energy grant to The Johns Hopkins University Applied Physics Laboratory DE-FG01-94NE32180 dated 27 September 1994 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 any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsi- bility 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. Refer- ence herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof. IfH DISTRIBUTION OF THIS DOCUMENT IS UNLIMITED DISCLAIMER Portions of this document may be illegible in electronic image products. Images are produced from the best available original document. TABLE OF CONTENTS 1.0 INTRODUCTION 1 1.1 PURPOSE ...1 1.2 BACKGROUND 1 1.3 SCOPE 3 2.0 NUCLEAR SPACE SAFETY GUIDELINES AND CONSIDERATIONS . -
A Review of the Benefits and Applications of the Thorium Fuel Cycle Vincent Hall University of Arkansas, Fayetteville
University of Arkansas, Fayetteville ScholarWorks@UARK Chemical Engineering Undergraduate Honors Chemical Engineering Theses 12-2010 A review of the benefits and applications of the thorium fuel cycle Vincent Hall University of Arkansas, Fayetteville Follow this and additional works at: http://scholarworks.uark.edu/cheguht Recommended Citation Hall, Vincent, "A review of the benefits nda applications of the thorium fuel cycle" (2010). Chemical Engineering Undergraduate Honors Theses. 25. http://scholarworks.uark.edu/cheguht/25 This Thesis is brought to you for free and open access by the Chemical Engineering at ScholarWorks@UARK. It has been accepted for inclusion in Chemical Engineering Undergraduate Honors Theses by an authorized administrator of ScholarWorks@UARK. For more information, please contact [email protected], [email protected]. A REVIEW OF THE BENEFITS AND APPLICATIONS OF THE THORIUM FUEL CYCLE An Undergraduate Honors College Thesis in the Ralph E. Martin Department of Chemical Engineering College of Engineering University of Arkansas Fayetteville, AR by Vincent Hall 09-21-2010 1 Abstract This paper aims to inform the reader of the benefits that can be achieved by using thorium as a fuel for nuclear power. Stages of the thorium cycle are directly compared against the current uranium based nuclear fuel cycle. These include mining, milling, fuel fabrication, use of various reactor designs, reprocessing, and disposal. Thorium power promises several key advantages over traditional nuclear power methods, namely a dramatic decrease in long lived radioactive waste, increased fuel efficiency, greater chemical stability during disposal, and higher adaptability for differing reactor designs across a wider range of the thermal neutron spectrum. -
Cooling Wide-Bandgap Materials in Power Electronics
Cooling Wide-Bandgap Materials in Power Electronics By Josh Perry Marketing Communications Specialist Advanced Thermal Solutions, Inc. (ATS) Engineers are always looking for an edge in their designs to extract as much power and performance as possible from a system, while attempting to meet industry trends in miniaturization. In the power electronics industry, this has required an examination of the materials being used to overcome inherent limitations from heat, voltage, or switching speed. Engineers are using wide-bandgap materials to expand the capabilities of power electronics, pushing them beyond the thermal and electrical limits of silicon-based components. (Background image created by Xb100 – Freepik.com) For years, silicon was the answer for the power electronics market, but in the past decade there has been a growing movement towards wide-bandgap materials, particularly silicon carbide (SiC) and gallium nitride (GaN). Wide-bandgap materials have higher breakdown voltage and perform more 1 efficiently at high temperatures than silicon-based components. [1] Recent research indicated, “For commercial applications above 400 volts, SiC stands out as a viable near-term commercial opportunity especially for single-chip current ratings in excess of 20 amps.” [2] This efficiency allows systems to consume less power, charge faster, and convert energy at a higher rate. A recent article from Electronic Design explained that SiC power devices “operate at higher switching speeds and higher temperatures with lower losses than conventional silicon.” SiC has an internal resistance that is 100 times lower than silicon and a breakdown electric field of 2.8 MV/cm, which is far higher than silicon’s 0.3 MV/cm, meaning that SiC components can handle the same level of current in smaller packages. -
Engineering Design of Aries-Iii*
PAPER ENGINEERING DESIGN OF ARIES-HI* O.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, L.A. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. Gierszewski, Canadian Fusion Fuels Tech. Prog., Mississauga, Ontario, Canada, L5J1K3 R. Hollies, Hollies Fluids Consulting, Pinawa, MB, ROE 1 L0 Canada and the ARIES Team M Z. <*• « (5 E B RECEIVE. AUG 2 6 1993 o M c -5 «3 OSTI Th« uibmitted manuscript has been authored by a contractor of the U. 5. Government under contract No. W-31-109-ENG-38- l Accordingly, the U. S. Government retains a nonexclusive, royalty-free license to publish or reproduce tha published form of this contribution, or allow others to do so, far U. 5. Government purposes. July 1993 •so * Work supported by the U.S. Department of Energy, Office of Fusion Energy, under Contract No. W-31-109-Eng-38. Paper to be presented at the Second Wisconsin Symposium on 3He and Fusion Power, University of Wisconsin, Madison, Wl, July 19-21,1993. DWTFMBUTION OF THIS DOOUMENT IS UNLIMITED ENGINEERING DESIGN OF ARIES-III* D.K. Sze, Argonne National Laboratory, Argonne, IL 60439 C. Wong, General Atomics, San Diego, CA 92138 E. Cheng, TSI Research, Solana Beach, CA 92075 M.E. Sawan, I.N. Sviatoslavsky, J.P. Blanchard, LA. El-Guebaly, H.Y. Khater, E.A. Mogahed University of Wisconsin, Madison, Wl 53706 P. -
Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors
0 Department of Nuclear Engineering And Radiation Health Physics DESIGN AND ANALYSIS OF A NUCLEAR REACTOR CORE FOR INNOVATIVE SMALL LIGHT WATER REACTORS. By Alexey I. Soldatov A DISSERTATION Submitted to Oregon State University March 9, 2009 1 AN ABSTRACT OF THE DISSERTATION OF Alexey I. Soldatov for the degree of Doctor of Philosophy in Nuclear Engineering presented on March 9, 2009. Title: Design and Analysis of a Nuclear Reactor Core for Innovative Small Light Water Reactors. Abstract approved: Todd S. Palmer In order to address the energy needs of developing countries and remote communities, Oregon State University has proposed the Multi-Application Small Light Water Reactor (MASLWR) design. In order to achieve five years of operation without refueling, use of 8% enriched fuel is necessary. This dissertation is focused on core design issues related with increased fuel enrichment (8.0%) and specific MASLWR operational conditions (such as lower operational pressure and temperature, and increased leakage due to small core). Neutron physics calculations are performed with the commercial nuclear industry tools CASMO-4 and SIMULATE-3, developed by Studsvik Scandpower Inc. The first set of results are generated from infinite lattice level calculations with CASMO-4, and focus on evaluation of the principal differences between standard PWR fuel and MASLWR fuel. Chapter 4-1 covers aspects of fuel isotopic composition changes with burnup, evaluation of kinetic parameters and reactivity coefficients. Chapter 4-2 discusses gadolinium self-shielding and shadowing effects, and subsequent impacts on power generation peaking and Reactor Control System shadowing. 2 The second aspect of the research is dedicated to core design issues, such as reflector design (chapter 4-3), burnable absorber distribution and programmed fuel burnup and fuel use strategy (chapter 4-4). -
Dr. Starr of Atomics International New Head of American Nuclear Societ Y Group Includes Members from 29 Countries Devoted to Ad- Vancement of Nuclear Scienc E
VOL. 1 NO. 2 ATOMICS INTERNATIONAL a division of North American Aviation, Inc . SEPTEMBER 1958 Dr. Starr Of Atomics International New Head Of American Nuclear Societ y Group Includes Members From 29 Countries Devoted To Ad- vancement Of Nuclear Scienc e At the annual meeting in June of the American Nuclear Society (ANS) . Dr. Chauncey Starr, general manager of Atomics International and vice president of North American Aviation, Inc., was elected president of the society to succeed Dr . Leland J . Haworth . Direc- tor of the Brookhaven National Laboratory . The American Nuclear Society was formed in 1955 to advance nuclear science and engineering . to encour- age research . establish scholarships. and to disseminate technical information . Membership of 3,000 Includes 29 Countries The organization's membership of 3 .000 includes about 140 members from 29 countries outside the United States representing many branches of science and technology . Members are associated with educa. tional , governmental, and research institutions, and with government contractors and industrial companies. First Student Award Establishe d In keeping with one of the objectives of the society, the first annual graduate student award has been estab- lished for the most outstanding graduate student work- ing in the nuclear sciences . NEW ANS OFFICERS-At the recent meeting of the URER ; Dr. Chauncey Starr, general manager of Atomics The award is the first of its kind by the society and American Nuclear Societe , new officers elected are : (felt International and vice-president of North American Avia- to right) John A . Swartnut, deputy director of Oak Ridge tion, Inc. PRESIDENT ; and Octave J. -
Standardization of Radioanalytical Methods for Determination of 63Ni and 55Fe in Waste and Environmental Samples
NKS-356 ISBN 978-87-7893-440-6 Standardization of Radioanalytical Methods for Determination of 63Ni and 55Fe in Waste and Environmental Samples Xiaolin Hou 1) Laura Togneri 2) Mattias Olsson 3) Sofie Englund 4) Olof Gottfridsson 5) Martin Forsström 6) Hannele Hironen 7) 1) Technical university of Denmark, DTU Nutech 2) Loviisa Power Plant, Fortum Power, Finland 3) Forsmarks Kraftgrupp AB, Sweden 4) OKG Aktiebolag, Sweden 5) Ringhals AB, Sweden 6) Studsvik Nuclear AB, Sweden (7) Olkiluoto Nuclear Power Plant, Finland January 2016 Abstract This report presents the progress on the NKS-B STANDMETHOD project which was conduced in 2014-2015, aiming to establish a Nordic standard methods for the determination of 63Ni and 55Fe in nuclear reactor process- ing water samples as well as other waste and environmental samples. Two inter-comparison excercises for determination of 63Ni and 55Fe in waste samples have been organized in 2014 and 2015, an evaluation of the results is given in this report. Based on the the results from this project in 2014-2015, Nordic standard methods for determination 63Ni in nuclear reactor processing water and for simultaneous determination of 55Fe and 63Ni in other types of waste and environmental samples respectively are proposed. Meanwhile an analytical method for determination of 55Fe in reactor water samples is also recommended. In addition, some procedures for sequential separation of actinides are presented for the simultaneous determinaiton of isotopes of actinides in waste samples are presented. Key words Radioanalysis; 63Ni; 55Fe; standard method; reactor water NKS-356 ISBN 978-87-7893-440-6 Electronic report, January 2016 NKS Secretariat P.O. -
Accident Source Terms for Light-Water Nuclear Power Plants: High Burnup and Mixed Oxide Fuels
ERIINRC 02-202 ACCIDENT SOURCE TERMS FOR LIGHT-WATER NUCLEAR POWER PLANTS: HIGH BURNUP AND MIXED OXIDE FUELS Draft Report: June 2002 Final Report: November 2002 Energy Research, Inc. - P.O. Box 2034 Rockville, Maryland 20847-2034 Work Performed Under the Auspices of the United States Nuclear Regulatory Commission Office of Nuclear Regulatory Research Washington, D.C. 20555 ERL/NRC 02-202 ACCIDENT SOURCE TERMS FOR LIGHT-WATER NUCLEAR POWER PLANTS: HIGH BURNUP AND MIXED OXIDE FUELS Draft Report: June 2002 Final Report: November 2002 Energy Research, Inc. P. 0. Box 2034 Rockville, Maryland 20847-2034 Work performed under the auspices of United States Nuclear Regulatory Commission Washington, D.C. Under Contract Number NRC-04-97-040 I This page intentionally left blank PREFACE performed by a This report has been prepared by Energy Research, Inc. based on work Office panel of experts organized by the United States Nuclear Regulatory Commission, if necessary, of Nuclear Regulatory Research, to develop recommendations for changes, to high burnup to the revised source term as published inlNUREG-1465, for application and mixed oxide fuels. the panel facilitator, and Dr. Brent Boyack of Los Alamos National Laboratory served as of the final report. Energy Research, Inc. has been responsible for the preparation Individual contributors to this report include: Executive Summary M. Khatib-Rahbar Section 1 M. Khatib-Rahbar Section 2 H. Nourbakhsh Section 3 B. Boyack Section 4 M. Khatib-Rahbar A. Hidaka of the Japan Substantial technical input was provided to the panel, by Mr. Evrard of the Institut de Atomic Energy Research Institute (JAERI), and Mr. -
Indian Nuclear Power Programme & Its Linkage To
Indian Nuclear Power Programme & its linkage to ADS S. Banerjee Bhabha Atomic Research Centre Mumbai, India 1 Contents 1. Indian nuclear power programme- present & future. 2. Nuclear fuel-cycle aspects. 3. Gains of Sub-critical reactor operation as ADS. 4. ADS for waste incineration & thorium utilization as nuclear fuel. 5. Indian efforts on ADS R&D- Roadmap, ongoing & future plans. 2 Elements of Indian nuclear programme . Indigenous development of a Reactor Technology (Pressurized Heavy Water Reactor- PHWR) - Total technology development - Based on indigenous resources . Adopting Closed-Fuel Cycle - Best use of fissile & fertile materials - Reduction of the waste burden . Three-Stage Programme - Modest uranium reserve - Utilization of large thorium reserve 3 Salient Features of PHWR • Natural Uranium Fuel - Low burn up - Efficient use of 235U per ton of U mined • Heavy Water – moderator and coolant - Development of heavy water technology - Tritium management • On-power fuelling - Fuelling machine development - Daily entry into reactor core • Neutron economy - Excellent physics design - Complex engineering - Careful choice of in-core materials - Neutrons: best utilized in fission & conversion • Large pressure vessel not required - Distributed pressure boundaries 4 Challenges faced in PHWR programme – and successfully met • Indigenous capability in fabrication of fuel and structural materials: - From low grade resources to finished fuel - Perfection in making in-core structural components • Mastering heavy water technology: - Ammonia and