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Light Isotopes of Berkelium and Californium
Lawrence Berkeley National Laboratory Recent Work Title LIGHT ISOTOPES OF BERKELIUM AND CALIFORNIUM Permalink https://escholarship.org/uc/item/1fm7b1fp Author Chetham-Strode, Alfred Publication Date 1956-06-26 eScholarship.org Powered by the California Digital Library University of California .... I UCRL 3322 UNIVERSITY OF CALIF-ORNIA .. i/ I / LIGHT ISOTOPES OF BERKELIUM AND CALIFORNIUM •' TWO-WEEK LOAN COPY This is a Library Circulating Copy r 'which may be borrowed for two weeks. For a personal retention copy, call Tech. Info. Dioision, Ext. 5545 DISCLAIMER This document was prepared as an account of work sponsored by the United States Government. While this document is believed to contain correct information, neither the United States Government nor any agency thereof, nor the Regents of the University of · California, nor any of their employees, makes any warranty, express or implied, or assumes any legal 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 its 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 the Regents of the University of California. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof or the Regents of the University of California. UCRL- 3322 Chemistry Distribution UNIVERSITY OF CALIFORNIA Radiation Laboratory Berkeley, California Contract No. W-7405-eng-48 LIGHT ISOTOPES OF BERKELIUM AND CALI~ORNIUM Alfred Chetham-Strode, Jr. -
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. -
1. Public Health Statement
AMERICIUM 1 1. PUBLIC HEALTH STATEMENT This public health statement tells you about americium and the effects of exposure. The Environmental Protection Agency (EPA) identifies the most serious hazardous waste sites in the nation. These sites make up the National Priorities List (NPL) and are the sites targeted for long-term federal cleanup activities. Americium has been found in at least 8 of the 1,636 current or former NPL sites. However, the total number of NPL sites evaluated for americium is not known. As more sites are evaluated, the sites at which americium is found may increase. This information is important because exposure to americium may harm you and because these sites may be sources of exposure. When a substance is released from a large area, such as an industrial plant, or from a container, such as a drum or bottle, it enters the environment. This release does not always lead to exposure. You are normally exposed to a substance only when you come in contact with it. You may be exposed by breathing, eating, or drinking the substance, or by skin contact. However, since americium is radioactive, you can also be exposed to its radiation if you are near it. External or internal exposure to radiation may occur from natural or man-made sources. Naturally occurring sources of radiation are cosmic radiation from space or naturally occurring radioactive materials in our body or in soil, air, water, or building materials. Man-made sources of radiation are found in consumer products, industrial equipment, atom bomb fallout, and to a smaller extent, from hospital waste and nuclear reactors. -
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 Hansen Letter
The Hansen Letter Introduction by Howard Morland, November 2003: This seven-thousand-word letter by Chuck Hansen, dated August 27, 1979, delivered a coup de grace to the government=s case for censorship of my Progressive magazine article on the H- bomb. It is a bit odd that Senator Charles Percy of Illinois was the intended recipient of the letter. He was never involved in The Progressive case, nor was he Chuck Hansen=s senator. He did not, apparently, request such a communication, and after receiving it he did not subsequently play a role in The Progressive case. However, copies of the letter immediately began to circulate among all persons concerned with the case. Hansen=s reason for writing the letter is not entirely clear, except as a vehicle for outlining his theory about the H-bomb secret. As he states in the letter, AThese... are some of the ideas I believe are presented in the Morland article (I have not seen the article).@ The defense attorneys in The Progressive case regarded him as an ally, of sorts, but wanted no part of his call for the punishment of Edward Teller, Theodore Taylor, and George Rathjens for security violations. Nonetheless, the defense was preparing to argue in court that the widespread distribution of this Hansen letter should moot The Progressive case. The letter clearly outlines the three H-bomb principles at issue in the case: separation of stages, compression, and radiation coupling. However it introduces two obvious technical flaws. Hansen describes the use of two primaries, or fission triggers, one at either end of the fusion secondary, which would explode simultaneously to compress the fusion secondary between them. -
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). -
Fission Target Design and Integration of Neutron Converter for Eurisol-Ds Project J
FISSION TARGET DESIGN AND INTEGRATION OF NEUTRON CONVERTER FOR EURISOL-DS PROJECT J. Bermudez, O. Alyakrinskiy, M. Barbui, L.B. Tecchio Laboratori Nazionali di Legnaro I.N.F.N. Viale dell'Università 2, 35020 Legnaro (PADOVA) ITALY. F. Negoita, L. Serbina, E. Udup “Horia Hulubei” - National Institute for Physics and Nuclear Engineering (IFIN-HH) Str. Atomistilor 407, P.O. Box MG-6, 077125 Bucharest-Magurele, Romania Abstract A study of a new fission target for EURISOL-DS is presented with a detailed description of the target. Calculations of several configurations were done using Monte Carlo code FLUKA aimed to obtaining 1015 fissions/s on single target. In Eurisol, neutrons inducing the fission reactions are produced by a proton beam 1GeV- 4mA interacting with a mercury converter. The target configuration was customized to gain fission yield from the large amount of low energy neutrons produced by the Hg converter. To this purpose, the fissile material is composed by discs of 238- Uranium carbide enriched with 15 g of 235-U. Studies of several geometries were done in order to define the shape and composition of uranium target, taking into account the mechanical and space constraints. Furthermore different configurations of reflector and moderators materials were considered to increase the thermal neutrons confined around the target and so enhance the performance of the system. The final configuration consists in six modular target containers inclined respect to the vertical, containing the fission targets, ion sources with RIB extraction and steering elements, cryopanels and devices for handling. The cross sections of the modules are rectangular with 10 mm coating of water for cooling. -
EPA Facts About Americium-241 July 2002
Argonne National Laboratory, EVS Human Health Fact Sheet, August 2005 Americium What Is It? Americium is a malleable, silvery white metal that tarnishes slowly in dry air at room temperature. Americium does not occur naturally but is produced artificially Symbol: Am by successive neutron capture reactions by plutonium isotopes. There are sixteen known isotopes of americium and all of them are radioactive. Atomic Number: 95 (Isotopes are different forms of an element that have the same number of (protons in nucleus) protons in the nucleus but a different number of neutrons.) Americium-241 was first produced in 1944 in a nuclear reactor at the University of Chicago. Atomic Weight: - Dr. Glenn Seaborg gave the new element its name in 1946 in honor of the (not naturally occurring) continent on which it was discovered. Of the sixteen radioactive isotopes, only three have half-lives long enough to warrant concern at Department of Energy (DOE) environmental management sites: americium-241, americium-242m, and americium-243. The half-lives of these three isotopes range from 150 to 7,400 Radioactive Properties of Key Americium Isotopes years, while those of the other and Associated Radionuclides Specific Radiation Energy (MeV) isotopes are less than a day. Half- Decay Isotope Activity Americium-241 is generally the Life Mode Alpha Beta Gamma most prevalent isotope at DOE (Ci/g) (α) (β) (γ) sites such as Hanford. It has a Am-241 430 yr 3.5 α 5.5 0.052 0.033 half-life of 430 years and decays Am-242m 150 yr 9.8 IT 0.025 0.044 0.0051 by emitting an alpha particle Am-242 16 hr 820,000 β, EC - 0.18 0.018 with attendant gamma radiation. -
Americium Cas #7440-35-9
AMERICIUM CAS #7440-35-9 Division of Toxicology ToxFAQsTM April 2004 This fact sheet answers the most frequently asked health questions (FAQs) about americium. For more information, call the ATSDR Information Center at 1-888-422-8737. This fact sheet is one in a series of summaries about hazardous substances and their health effects. It is important you understand this information because this substance may harm you. The effects of exposure to any hazardous substance depend on the dose, the duration, how you are exposed, personal traits and habits, and whether other chemicals are present. HIGHLIGHTS: Very low levels of americium occur in air, water, soil, and food, as well as in smoke detectors. Exposure to radioactive americium may result in increased cancer risk. Americium has been found in at least 8 of the 1,636 National Priorities List (NPL) sites identified by the Environmental Protection Agency (EPA). What is americium? ‘ Americium strongly sticks to soil particles and does not travel very far into the ground. Americium is a man-made radioactive chemical. Americium ‘ Plants may take up small amounts of americium from the has no naturally occurring or stable isotopes. Two soil. important isotopes of americium are americium 241 (241Am) ‘ Fish may take up americium, but little builds up in the (read as americium two-forty-one) and 243Am. Both isotopes fleshy tissue. In shellfish, americium is attached to the shell have the same chemical behavior in the environment and the and not to the parts you normally eat. same chemical effects on your body. How might I be exposed to americium? 241Americium is used in ionization smoke detectors. -
Burnup Analysis for HTR-10 Reactor Core Loaded with Uranium and Thorium Oxide
Nuclear Engineering and Technology 52 (2020) 674e680 Contents lists available at ScienceDirect Nuclear Engineering and Technology journal homepage: www.elsevier.com/locate/net Original Article Burnup analysis for HTR-10 reactor core loaded with uranium and thorium oxide * ** Mohamed A. Alzamly a, , Moustafa Aziz a, , Alya A. Badawi b, Hanaa Abou Gabal b, Abdel Rraouf A. Gadallah a a Egyptian Nuclear and Radiological Regulatory Authority (ENRRA), Egypt b Department of Nuclear and Radiation Engineering, Faculty of Engineering, University of Alexandria, Egypt article info abstract Article history: We used MCNP6 computer code to model HTR-10 core reactor. We used two types of fuel; UO2 and Received 17 April 2019 (ThþPu)O2 mixture. We determined the critical height at which the reactor approached criticality in both Received in revised form two cases. The neutronic and burnup parameters were investigated. The results indicated that the core 13 September 2019 fueled with mixed (ThþPu)O , achieved about 24% higher fuel cycle length than the UO case. It also Accepted 21 September 2019 2 2 enhanced safeguard security by burning Pu isotopes. The results were compared with previously pub- Available online 25 September 2019 lished papers and good agreements were found. © 2019 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the Keywords: Pebble-bed CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/). HTR-10 Burnup Thorium based fuel 1. Introduction ceramic [2]. The coolant outlet temperature in HTR-10 is much higher than High Temperature Reactors (HTRs) and Very High Temperature PWRs (700 Ce950 C compared to 300 C) [3].