The Hansen Letter
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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. -
Computer Simulations and the Trading Zone
PETER &A Computer Simulations and the Trading Zone At the root of most accounts of the development of science is the covert premise that science is about ontology: What objects are there? How do they interact? And how do we discover them? It is a premise that underlies three distinct epochs of inquiry into the nature of science. Among the positivists, the later Carnap explicitly advocated a view that the objects of physics would be irretrievably bound up with what he called a "framework," a full set of linguistic relations such as is found in Newtonian or Eiustcini;~mechanics. That these frameworks held little in common did not trouble Car- nap; prediction mattered more than progress. Kuhn molded this notion and gave it a more historical focus. Unlike the positivists, Kuhn and other commentators of the 1960's wanted to track the process by which a community abandoned one framework and adopted another. To more recent scholars, the Kuhnian categoriza- tion of group affiliation and disaffiliation was by and large correct, but its underlying dynamics were deemed deficient because they paid insufficient attention to the sociological forces that bound groups to their paradigms. All three generations embody the root assumption that the analysis of science studies (or ought to study) a science classified and divided according to the objects of its inquiry. All three assume that as these objects change, particular branches of science split into myriad disconnected parts. It is a view of scientific disunity that I will refer to as "framework relativism. 55 In this essay, as before, I will oppose this view, but not by Computer Simulations I 19 invoking the old positivist pipe dreams: no universal protocol languages, no physicalism, no Corntian hierarchy of knowledge, and no radical reductionism. -
Use of DD-108 Neutron Generator with ISU Sub-Critical Assembly
From: Ramsey, Kevin To: Maxwell Daniels Cc: Campbell, Vivian; Font, Ossy; Yin, Xiaosong; Gonzalez, Hipolito; Johnson, Robert; Tripp, Christopher Subject: Use of DD-108 neutron generator with ISU sub-critical assembly Date: Thursday, July 20, 2017 3:46:00 PM We have evaluated your proposal to use a neutron generator to pulse your sub-critical assembly, and concluded that you may use the neutron generator under the current authorization in Materials License SNM-1373. Our finding that you may proceed without an amendment is based on the following understanding. If your understanding differs, please inform us. It is our understanding that you want to use the Adelphi Technology DD-108 Neutron Generator described at http://www.adelphitech.com/products/dd108.html. The technical brochure located at http://www.adelphitech.com/pdfs/DD108-9_generator_Flier_24-Nov- 14_A.PDF states that the device uses deuterium gas to produce 2.45 MeV neutrons. The NRC does not regulate the possession and use of deuterium, so there is no need to add the device to one of your NRC licenses. PLEASE NOTE – NRC regulates tritium and a license amendment would be needed to possess and use a tritium neutron generator. Our criticality safety evaluation concluded that using a neutron source will affect the fission rate, but will not affect the neutron multiplication or criticality analysis. From the description and pictures of the neutron generator, it appears that it would only contain a small amount of deuterium. As long as this is not permitted to come into physical contact with the SNM, there should be no issue. -
How I Learned to Stop Worrying and Dismantle the Bomb New Approaches to Nuclear Warhead Verification
HOW I LEARNED TO STOP WORRYING AND DISMANTLE THE BOMB NEW APPROACHES TO NUCLEAR WARHEAD VERIFICATION Alex Glaser,* Sébastien Philippe,* and Robert J. Goldston** *Princeton University **Princeton University and Princeton Plasma Physics Laboratory Duke University, January 19, 2017 Revision 1 CONSORTIUM FOR VERIFICATION TECHNOLOGY PNNL Oregon State MIT U Michigan INL Yale U Wisconsin Columbia Penn State Princeton and PPPL U Illinois LBNL LLNL Sandia NNSS Duke ORNL NC State LANL Sandia U Florida (not shown: U Hawaii) Five-year project, funded by U.S. DOE, 13 U.S. universities and 9 national labs, led by U-MICH Princeton participates in the research thrust on disarmament research (and leads the research thrust of the consortium on policy) A. Glaser, S. Philippe, R. Goldston, How I Learned to Stop Worrying and Dismantle the Bomb, Duke University, January 19, 2017 2 INTERNATIONAL PARTNERSHIP FOR NUCLEAR DISARMAMENT VERIFICATION Established in 2015; currently 26 participating countries Working Group One: “Monitoring and Verification Objectives” (chaired by Italy and the Netherlands) Working Group Two: “On-Site Inspections” (chaired by Australia and Poland) Working Group Three: “Technical Challenges and Solutions” (chaired by Sweden and the United States) www.state.gov/t/avc/ipndv A. Glaser, S. Philippe, R. Goldston, How I Learned to Stop Worrying and Dismantle the Bomb, Duke University, January 19, 2017 3 WHAT’S NEXT FOR NUCLEAR ARMS CONTROL? 2015 STATEMENT BY JAMES MATTIS “The nuclear stockpile must be tended to and fundamental questions must be asked and answered: • We must clearly establish the role of our nuclear weapons: do they serve solely to deter nuclear war? If so we should say so, and the resulting clarity will help to determine the number we need. -
Radiological Safety Aspects of the Operation of Neutron Generators
\ This publication is no longer valid Nuclear Safety Information Centre, B0655 Please see http://www-ns.iaea.org/standards/ OBSOLETE SAFETY SERIES No. 42 Radiological Safety Aspects of the Operation of Neutron Generators INTERNATIONAL ATOMIC ENERGY AGENCY, VIENNA, 1 976 This publication is no longer valid Please see http://www-ns.iaea.org/standards/ This publication is no longer valid Please see http://www-ns.iaea.org/standards/ RADIOLOGICAL SAFETY ASPECTS OF THE OPERATION OF NEUTRON GENERATORS This publication is no longer valid Please see http://www-ns.iaea.org/standards/ The following States are Members of the International Atomic Energy Agency: AFGHANISTAN HOLY SEE PHILIPPINES ALBANIA HUNGARY POLAND ALGERIA ICELAND PORTUGAL A RG EN TIN A IN D IA QATAR AUSTRALIA INDONESIA REPUBLIC OF SOUTH VIETNAM AUSTRIA IRAN ROMANIA BANGLADESH IRAQ SAUDI ARABIA BELG IU M IRELAND SENEGAL BOLIVIAISRAEL SIERRA LEONE BRAZIL ITALY SINGAPORE BULGARIA IVORY COAST SOUTH AFRICA BURMA JAMAICA SPAIN BYELORUSSIAN SOVIET JAPAN SRI LANKA SOCIALIST REPUBLIC JORDANSUDAN CAMBODIA KENYA SWEDEN CANADA KOREA, REPUBLIC OF SWITZERLAND CHILE KUWAIT SYRIAN ARAB REPUBLIC COLOM BIA LEBANON THAILAND COSTA RICA LIBERIA TUNISIA CUBA LIBYAN ARAB REPUBLIC TURKEY CYPRUS LIECHTENSTEIN UGANDA CZECHOSLOVAKIA LUXEMBOURG UKRAINIAN SOVIET SOCIALIST DEMOCRATIC PEOPLE’S MADAGASCAR REPU BLIC REPUBLIC OF KOREA MALAYSIA UNION OF SOVIET SOCIALIST DENMARK MALI REPUBLICS DOMINICAN REPUBLIC MAURITIUS UNITED ARAB EMIRATES ECUADOR M EXICO UNITED KINGDOM OF GREAT EGYPT MONACO BRITAIN AND NORTHERN -
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. -
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. -
The Influence of the Presence Or Absence of a Neutron Reflector on the Critical Mass of Uranium
Archive of SID The influence of the presence or absence of a neutron reflector on the critical mass of uranium Maryam Noorani Department of physics, University of Mohaghegh Ardabili, Ardabil, Iran [email protected] Farhad Zolfagharpour Department of physics, University of Mohaghegh Ardabili, Ardabil, Iran [email protected] Sara Azimkhani Department of physics, University of Mohaghegh Ardabili, Ardabil, Iran [email protected] Abstract To increase productivity and improve the neutron economy in the reactor, neutron reflection is used. This reflectors cause lack of neutron leakage and reactor fuel can reach critical mass faster. Various materials such as beryllium, neutron, carbon, water, lead and so on could satisfy this property. In this paper, by using the MCNP code, critical mass of uranium in the term of percent of enrichment for different reflectors is obtained. The results show beryllium, carbon and deuterium are an excellent choice for this purpose. Also increasing the thickness of the neutron reflector causes an increase in neutron multiplication factor. Keywords: Neutron reflector, Critical mass, Uranium. www.SID.ir Archive of SID Introduction Initial calculations of critical mass or the amount of fissile material needed to continue nuclear fission refers to Heisenberg works on it (Logan, 1995). Heisenberg expresses that by using fissile material and calculating the critical mass can manufacture nuclear weapon (Serber, 1992) but calculations of nuclear reactors for energy production in 1950s was pursued with greater intensity. Nowadays the calculation of critical mass takes place by computing codes and simulation and codes for neutron transport (Kastanya, 2015). For a nuclear reactor that is working with a constant potential over the time, it is needed that neutron chain reaction takes place inside with the multiplication factor K=1, it means that number of neutrons produced by fission is equal to the total number of neutrons absorbed and leaked out of the reactor core (Krane, 1995). -
The Tokamak As a Neutron Source
PREPARED FOR THE U.S. DEPARTMENT OF ENERGY, UNDER CONTRACT DE-AC02-76-CHO-3073 PPPL-2656 PPPL-2656 UC-420 THE TOKAMAK AS A NEUTRON SOURCE BY H.W. HENDEL AND D.L JASSBY November 1989 PMNCITON PLASMA PHYSICS LASOffATORY PRINCETON UNIVERSITY, PRINCETON, NEW JERSEY NOTICE Available from: National Technical Information Service U.S. Department of Commerce 5285 Port Royal Road Springfield. Virginia 22161 703-487-4650 Use the following price codes when ordering: Price: Printed Copy A04 Microfiche A01 THE TOKAMAK AS A NEUTRON SOURCE by H.W. Hendel and D.L. Jassby PPPL—2656 DE90 001821 Princeton Plasma Physics Laboratory Princeton University Princeton, N.J. 08543 ABSTRACT This paper describes the tokamak in its role as a neutron source, with emphasis on experimental results for D-D neutron production. The sections summarize tokamak operation, sources of fusion and non-fusion neutrons, principal nsutron detection methods and their calibration, neutron energy spectra and fluxes outside the tokamak plasma chamber, history of neutron production in tokamaks, neutron emission and fusion power gain from JET and TFTR (the largest present-day tokamaks), and D-T neutron production from burnup of D-D tritons. This paper also discusses the prospects for future tokamak neutron production and potential applications of tokamak neutron sources. DISCLAIMER This report was prepared as JH account or 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 repre^r-s that its use would not infringe privately owned rights. -
DOE-OC Green Book
SUBJECT AREA INDICATORS AND KEY WORD LIST FOR RESTRICTED DATA AND FORMERLY RESTRICTED DATA U.S. DEPARTMENT OF ENERGY AUGUST 2018 TABLE OF CONTENTS PURPOSE ....................................................................................................................................................... 1 BACKGROUND ............................................................................................................................................... 2 Where It All Began .................................................................................................................................... 2 DIFFERENCE BETWEEN RD/FRD and NATIONAL SECURITY INFORMATION (NSI) ......................................... 3 ACCESS TO RD AND FRD ................................................................................................................................ 4 Non-DoD Organizations: ........................................................................................................................... 4 DoD Organizations: ................................................................................................................................... 4 RECOGNIZING RD and FRD ............................................................................................................................ 5 Current Documents ................................................................................................................................... 5 Historical Documents ............................................................................................................................... -
The Los Alamos Thermonuclear Weapon Project, 1942-1952
Igniting The Light Elements: The Los Alamos Thermonuclear Weapon Project, 1942-1952 by Anne Fitzpatrick Dissertation submitted to the Faculty of Virginia Polytechnic Institute and State University in partial fulfillment of the requirements for the degree of DOCTOR OF PHILOSOPHY in SCIENCE AND TECHNOLOGY STUDIES Approved: Joseph C. Pitt, Chair Richard M. Burian Burton I. Kaufman Albert E. Moyer Richard Hirsh June 23, 1998 Blacksburg, Virginia Keywords: Nuclear Weapons, Computing, Physics, Los Alamos National Laboratory Igniting the Light Elements: The Los Alamos Thermonuclear Weapon Project, 1942-1952 by Anne Fitzpatrick Committee Chairman: Joseph C. Pitt Science and Technology Studies (ABSTRACT) The American system of nuclear weapons research and development was conceived and developed not as a result of technological determinism, but by a number of individual architects who promoted the growth of this large technologically-based complex. While some of the technological artifacts of this system, such as the fission weapons used in World War II, have been the subject of many historical studies, their technical successors -- fusion (or hydrogen) devices -- are representative of the largely unstudied highly secret realms of nuclear weapons science and engineering. In the postwar period a small number of Los Alamos Scientific Laboratory’s staff and affiliates were responsible for theoretical work on fusion weapons, yet the program was subject to both the provisions and constraints of the U. S. Atomic Energy Commission, of which Los Alamos was a part. The Commission leadership’s struggle to establish a mission for its network of laboratories, least of all to keep them operating, affected Los Alamos’s leaders’ decisions as to the course of weapons design and development projects.