1 Overview of Nuclear Reactor Systems and Fundamentals
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Fuel Geometry Options for a Moderated Low-Enriched Uranium Kilowatt-Class Space Nuclear Reactor T ⁎ Leonardo De Holanda Mencarinia,B,Jeffrey C
Nuclear Engineering and Design 340 (2018) 122–132 Contents lists available at ScienceDirect Nuclear Engineering and Design journal homepage: www.elsevier.com/locate/nucengdes Fuel geometry options for a moderated low-enriched uranium kilowatt-class space nuclear reactor T ⁎ Leonardo de Holanda Mencarinia,b,Jeffrey C. Kinga, a Nuclear Science and Engineering Program, Colorado School of Mines (CSM), 1500 Illinois St, Hill Hall, 80401 Golden, CO, USA b Subdivisão de Dados Nucleares - Instituto de Estudos Avançados (IEAv), Trevo Coronel Aviador José Alberto Albano do Amarante, n 1, 12228-001 São José dos Campos, SP, Brazil ABSTRACT A LEU-fueled space reactor would avoid the security concerns inherent with Highly Enriched Uranium (HEU) fuel and could be attractive to signatory countries of the Non-Proliferation Treaty (NPT) or commercial interests. The HEU-fueled Kilowatt Reactor Using Stirling Technology (KRUSTY) serves as a basis for a similar reactor fueled with LEU fuel. Based on MCNP6™ neutronics performance estimates, the size of a 5 kWe reactor fueled with 19.75 wt% enriched uranium-10 wt% molybdenum alloy fuel is adjusted to match the excess reactivity of KRUSTY. Then, zirconium hydride moderator is added to the core in four different configurations (a homogeneous fuel/moderator mixture and spherical, disc, and helical fuel geometries) to reduce the mass of uranium required to produce the same excess reactivity, decreasing the size of the reactor. The lowest mass reactor with a given moderator represents a balance between the reflector thickness and core diameter needed to maintain the multiplication factor equal to 1.035, with a H/D ratio of 1.81. -
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. -
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. -
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. -
Assessing Potential Induced Radioactivity in Materials Processed with X-Ray Energy Above 5 Mev: Assessment Protocols and Practical Experience
FERMILAB-PUB-20-562-DI Assessing potential induced radioactivity in materials processed with X-ray energy above 5 MeV: Assessment protocols and practical experience Hervé Michel1; Thomas Kroc2; Brian J. McEvoy 3; Deepak Patil4 Pierre Reppert5; Mark A. Smith6 1Director, Radiation Technology EMEAA, STERIS, Hogenweidstrasse 6, 4658 Däniken, Switzerland, [email protected] 2Applications Physicist for Technology Development, Fermilab, Batavia, Illinois, USA, [email protected] 3Senior Director Global Technologies, STERIS, IDA Business & Technology Park, Tullamore, County Offaly, R35 X865, Ireland, [email protected] 4Senior Director, Radiation Technology, 1880 Industrial Drive, Libertyville, IL 60048 [email protected] 5Validation Manager, STERIS, Hogenweidstrasse 6, 4658 Däniken, Switzerland, [email protected] 6Managing Director, Ionaktis, LLC, PO Box 11599, Charlotte, NC 28220 USA [email protected] Abstract In accordance with ISO11137-1 section 5.1.2, ‘the potential for induced radioactivity in product shall be assessed’. This article describes how compliance to this requirement may be achieved using qualified test methods. Materials of consideration are conceptually discussed. Results of testing conducted on products processed with a 7.5 MeV X-ray irradiation process are provided. As X-ray becomes more widely used in healthcare sterilization, having standard assessment protocols for activation coupled with a shared database of material test results will benefit all healthcare product manufacturers seeking to avail of this innovative technology. This manuscript has been authored by Fermi Research Alliance, LLC under Contract No. DE-AC02-07CH11359 with the U.S. Department of Energy, Office of Science, Office of High Energy Physics. 1. Introduction Radioactive material of natural origin is ubiquitous in nature, widely varying in type and amount. -
Boron-Proton Nuclear-Fusion Enhancement Induced in Boron-Doped Silicon Targets by Low-Contrast Pulsed Laser
PHYSICAL REVIEW X 4, 031030 (2014) Boron-Proton Nuclear-Fusion Enhancement Induced in Boron-Doped Silicon Targets by Low-Contrast Pulsed Laser † A. Picciotto,1,* D. Margarone,2, A. Velyhan,2 P. Bellutti,1 J. Krasa,2 A. Szydlowsky,3,4 G. Bertuccio,5 Y. Shi,5 A. Mangione,6 J. Prokupek,2,7 A. Malinowska,4 E. Krousky,8 J. Ullschmied,8 L. Laska,2 M. Kucharik,7 and G. Korn2 1Micro-Nano Facility, Fondazione Bruno Kessler, 38123 Trento, Italy 2Institute of Physics ASCR, v.v.i. (FZU), ELI-Beamlines Project, 182 21 Prague, Czech Republic 3Institute of Plasma Physics and Laser Microfusion, 01-497 Warsaw, Poland 4National Centre for Nuclear Research, 05-400 Otwock, Poland 5Politecnico di Milano, Department of Electronics Information and Bioengineering, 22100 Como, Italy 6Institute of Advanced Technologies, 91100 Trapani, Italy 7Czech Technical University in Prague, FNSPE, 115 19 Prague, Czech Republic 8Institute of Plasma Physics of the ASCR, PALS Laboratory, 182 00 Prague, Czech Republic (Received 12 January 2014; revised manuscript received 1 April 2014; published 19 August 2014) We show that a spatially well-defined layer of boron dopants in a hydrogen-enriched silicon target allows the production of a high yield of alpha particles of around 109 per steradian using a nanosecond, low-contrast laser pulse with a nominal intensity of approximately 3 × 1016 Wcm−2. This result can be ascribed to the nature of the long laser-pulse interaction with the target and with the expanding plasma, as well as to the optimal target geometry and composition. The possibility of an impact on future applications such as nuclear fusion without production of neutron-induced radioactivity and compact ion accelerators is anticipated. -
Beryllium – a Unique Material in Nuclear Applications
INEEL/CON-04-01869 PREPRINT Beryllium – A Unique Material In Nuclear Applications T. A. Tomberlin November 15, 2004 36th International SAMPE Technical Conference This is a preprint of a paper intended for publication in a journal or proceedings. Since changes may be made before publication, this preprint should not be cited or reproduced without permission of the author. This document 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, or any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of any information, apparatus, product or process disclosed in this report, or represents that its use by such third party would not infringe privately owned rights. The views expressed in this paper are not necessarily those of the U.S. Government or the sponsoring agency. BERYLLIUM – A UNIQUE MATERIAL IN NUCLEAR APPLICATIONS T. A. Tomberlin Idaho National Engineering and Environmental Laboratory P.O. Box 1625 2525 North Fremont Ave. Idaho Falls, ID 83415 E-mail: [email protected] ABSTRACT Beryllium, due to its unique combination of structural, chemical, atomic number, and neutron absorption cross section characteristics, has been used successfully as a neutron reflector for three generations of nuclear test reactors at the Idaho National Engineering and Environmental Laboratory (INEEL). The Advanced Test Reactor (ATR), the largest test reactor in the world, has utilized five successive beryllium neutron reflectors and is scheduled for continued operation with a sixth beryllium reflector. -
Simulation of Induced Radioactivity for a Heavy Ion Medical Machine
Chinese Physics C Vol. 38, No. 11 (2014) 118201 Simulation of induced radioactivity for a heavy ion medical machine XU Jun-Kui(Md¿)1;2 SU You-Wu(kÉ)2;1) LI Wu-Yuan(oÉ)2 MAO Wang(f!)2 XIA Jia-Wen(gZ©)2 CHEN Xi-Meng(Ú)1 YAN Wei-Wei(î)2 XU Chong(MÇ)2 1 School of Nuclear Science and Technology, Lanzhou University, Lanzhou 730000, China 2 Institute of Modern Physics, Chinese Academy of Science, Lanzhou 730000, China Abstract: The radioactivity induced by carbon ions of the Heavy Ion Medical Machine (HIMM) was studied to asses its radiation protection and environmental impact. Radionuclides in the accelerator component, and in the cooling water and air at the target area, which are induced from primary beam and secondary particles, are simulated by FLUKA Monte Carlo code. It is found that radioactivity in the cooling water and air is not very important at the required beam intensity and energy that is needed for treatment, while radionuclides in the accelerator component may cause some problems for maintenance work and, therefore, a suitable cooling time is needed after the machine is shut down. Key words: radioactivity, HIMM, heavy ion PACS: 07.89.+b, 28.41.Qb DOI: 10.1088/1674-1137/38/11/118201 1 Introduction back to the early period when Curie and Joliot found the activation reaction in 1934 [4]. In recent years, improve- Nowadays, radiation therapy is an important means ments of the accelerator have meant that more kinds of tumor treatment. More than 50% of all patients with of particles, of a higher energy can be accelerated and, localized malignant tumors are treated with radiation [1]. -
Nuclear Weapons Technology 101 for Policy Wonks Bruce T
NUCLEAR WEAPONS TECHNOLOGY FOR POLICY WONKS NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS BRUCE T. GOODWIN BRUCE T. GOODWIN BRUCE T. Center for Global Security Research Lawrence Livermore National Laboratory August 2021 NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS BRUCE T. GOODWIN Center for Global Security Research Lawrence Livermore National Laboratory August 2021 NUCLEAR WEAPONS TECHNOLOGY 101 FOR POLICY WONKS | 1 This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory in part under Contract W-7405-Eng-48 and in part under Contract DE-AC52-07NA27344. The views and opinions of the author expressed herein do not necessarily state or reflect those of the United States government or Lawrence Livermore National Security, LLC. ISBN-978-1-952565-11-3 LCCN-2021907474 LLNL-MI-823628 TID-61681 2 | BRUCE T. GOODWIN Table of Contents About the Author. 2 Introduction . .3 The Revolution in Physics That Led to the Bomb . 4 The Nuclear Arms Race Begins. 6 Fission and Fusion are "Natural" Processes . 7 The Basics of the Operation of Nuclear Explosives. 8 The Atom . .9 Isotopes . .9 Half-life . 10 Fission . 10 Chain Reaction . 11 Critical Mass . 11 Fusion . 14 Types of Nuclear Weapons . 16 Finally, How Nuclear Weapons Work . 19 Fission Explosives . 19 Fusion Explosives . 22 Staged Thermonuclear Explosives: the H-bomb . 23 The Modern, Miniature Hydrogen Bomb . 25 Intrinsically Safe Nuclear Weapons . 32 Underground Testing . 35 The End of Nuclear Testing and the Advent of Science-Based Stockpile Stewardship . 39 Stockpile Stewardship Today . 41 Appendix 1: The Nuclear Weapons Complex . -
Reactor Physics Analysis of Air-Cooled Nuclear System
REACTOR PHYSICS ANALYSIS OF AIR-COOLED NUCLEAR SYSTEM A Thesis by HANNIEL JOUVAIN HONANG Submitted to the Office of Graduate and Professional Studies of Texas A&M University in partial fulfillment of the requirements for the degree of MASTER OF SCIENCE Chair of Committee, Pavel V. Tsvetkov Committee Members, Marc Holtzapple Sean McDeavitt Head of Department, Yassin Hassan May 2016 Major Subject: Nuclear Engineering Copyright 2016 Hanniel Jouvain Honang ABSTRACT The design of SACRé (Small Air-Cooled Reactor) fixated on evaluations of air as a potential coolant. The assessment offered in this thesis focused on reactor physic analyses, and materials review and incorporation in a system defined by a highly corrosive environment. The oxidizing nature of air at high-temperature warrants the need to examine and compare materials for their oxidation temperature, their melting and boiling temperature, and their thermal conductivity. Material choices for the fuel, the cladding, the system’s casing/structural material and the reflector were evaluated in this study. Survey of materials and literature lead to the selection of six different cladding materials which are FeCrAl, APMT, Inconel 718 and stainless steel of type 304, 316 and 310. A review of their thermal properties, for a high oxidation temperature and melting temperature and the exhibition of a hard neutron spectrum lead to the selection of APMT steel material. This material was not only be selected as the fuel cladding but also as a casing for reflector and shielding materials. The design of this 600 MWth system was investigated considering reflector materials for fast spectrum. Lead-based reflectors (lead bismuth eutectic, lead oxide and pure lead), magnesium-based reflectors (magnesium oxide and magnesium aluminum oxide), and aluminum oxide reflectors were evaluated in this thesis.