Neutron Activation Analysis
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Neutron Interactions and Dosimetry Outline Introduction Tissue
Outline • Neutron dosimetry Neutron Interactions and – Thermal neutrons Dosimetry – Intermediate-energy neutrons – Fast neutrons Chapter 16 • Sources of neutrons • Mixed field dosimetry, paired dosimeters F.A. Attix, Introduction to Radiological • Rem meters Physics and Radiation Dosimetry Introduction Tissue composition • Consider neutron interactions with the majority tissue elements H, O, C, and N, and the resulting absorbed dose • Because of the short ranges of the secondary charged particles that are produced in such interactions, CPE is usually well approximated • Since no bremsstrahlung x-rays are generated, the • The ICRU composition for muscle has been assumed in absorbed dose can be assumed to be equal to the most cases for neutron-dose calculations, lumping the kerma at any point in neutron fields at least up to 1.1% of “other” minor elements together with oxygen to an energy E ~ 20 MeV make a simple four-element (H, O, C, N) composition Neutron kinetic energy Neutron kinetic energy • Neutron fields are divided into three • Thermal neutrons, by definition, have the most probable categories based on their kinetic energy: kinetic energy E=kT=0.025eV at T=20C – Thermal (E<0.5 eV) • Neutrons up to 0.5eV are considered “thermal” due to simplicity of experimental test after they emerge from – Intermediate-energy (0.5 eV<E<10 keV) moderator material – Fast (E>10 keV) • Cadmium ratio test: • Differ by their primary interactions in tissue – Gold foil can be activated through 197Au(n,)198Au interaction and resulting biological effects -
Concrete Analysis by Neutron-Capture Gamma Rays Using Californium 252
CONCRETE ANALYSIS BY NEUTRON-CAPTURE GAMMA RAYS USING CALIFORNIUM 252 Dick Duffey, College of Engineering, University of Maryland; Peter F. Wiggins, Naval Systems Engineering Department, U.S. Naval Academy; Frank E. Senftle, U.S. Geological Survey; and A. A. El Kady, United Arab Republic Atomic Energy Establishment, Cairo The feasibility of analyzing concrete and cement by a measurement of the neutron-capture or prompt gamma rays was investigated; a 100-ug californium-252 source was used to supply the neutrons. A lithium drifted germanium crystal detected the capture gamma rays emitted. The capture gamma rays from cement, sand, and 3 coarse aggregates-quartzite gravel, limestone, and diabase--:were studied. Concrete blocks made from these materials were then tested. The capture gamma ray response of the calcium, silicon, and iron in the concrete blocks was in accord with the elements identified in the mix materials. The principal spectral lines used were the 6.42 MeV line of calcium, the 4.93 MeV line of silicon, and the doublet of iron at about 7 .64 MeV. The aluminum line at 7. 72 MeV was ob served in some cases but at a lower intensity with the limited electronic equipment available. This nuclear spectroscopic technique offers a possi ble method of determining the components of sizable concrete samples in a nondestructive, in situ manner. In addition, the neutron-capture gamma ray technique might find application in control of the concrete and cement processes and furnish needed information on production operations and inventories. • FROM THE point of view of the geochemical analyst, concrete may be considered as rock relocated and reformed at the convenience of the engineer. -
Conceptual Design Report Jülich High
General Allgemeines ual Design Report ual Design Report Concept Jülich High Brilliance Neutron Source Source Jülich High Brilliance Neutron 8 Conceptual Design Report Jülich High Brilliance Neutron Source (HBS) T. Brückel, T. Gutberlet (Eds.) J. Baggemann, S. Böhm, P. Doege, J. Fenske, M. Feygenson, A. Glavic, O. Holderer, S. Jaksch, M. Jentschel, S. Kleefisch, H. Kleines, J. Li, K. Lieutenant,P . Mastinu, E. Mauerhofer, O. Meusel, S. Pasini, H. Podlech, M. Rimmler, U. Rücker, T. Schrader, W. Schweika, M. Strobl, E. Vezhlev, J. Voigt, P. Zakalek, O. Zimmer Allgemeines / General Allgemeines / General Band / Volume 8 Band / Volume 8 ISBN 978-3-95806-501-7 ISBN 978-3-95806-501-7 T. Brückel, T. Gutberlet (Eds.) Gutberlet T. Brückel, T. Jülich High Brilliance Neutron Source (HBS) 1 100 mA proton ion source 2 70 MeV linear accelerator 5 3 Proton beam multiplexer system 5 4 Individual neutron target stations 4 5 Various instruments in the experimental halls 3 5 4 2 1 5 5 5 5 4 3 5 4 5 5 Schriften des Forschungszentrums Jülich Reihe Allgemeines / General Band / Volume 8 CONTENT I. Executive summary 7 II. Foreword 11 III. Rationale 13 1. Neutron provision 13 1.1 Reactor based fission neutron sources 14 1.2 Spallation neutron sources 15 1.3 Accelerator driven neutron sources 15 2. Neutron landscape 16 3. Baseline design 18 3.1 Comparison to existing sources 19 IV. Science case 21 1. Chemistry 24 2. Geoscience 25 3. Environment 26 4. Engineering 27 5. Information and quantum technologies 28 6. Nanotechnology 29 7. Energy technology 30 8. -
1663-29-Othernuclearreaction.Pdf
it’s not fission or fusion. It’s not alpha, beta, or gamma dosimeter around his neck to track his exposure to radiation decay, nor any other nuclear reaction normally discussed in in the lab. And when he’s not in the lab, he can keep tabs on his an introductory physics textbook. Yet it is responsible for various experiments simultaneously from his office computer the existence of more than two thirds of the elements on the with not one or two but five widescreen monitors—displaying periodic table and is virtually ubiquitous anywhere nuclear graphs and computer codes without a single pixel of unused reactions are taking place—in nuclear reactors, nuclear bombs, space. Data printouts pinned to the wall on the left side of the stellar cores, and supernova explosions. office and techno-scribble densely covering the whiteboard It’s neutron capture, in which a neutron merges with an on the right side testify to a man on a mission: developing, or atomic nucleus. And at first blush, it may even sound deserving at least contributing to, a detailed understanding of complex of its relative obscurity, since neutrons are electrically neutral. atomic nuclei. For that, he’ll need to collect and tabulate a lot For example, add a neutron to carbon’s most common isotope, of cold, hard data. carbon-12, and you just get carbon-13. It’s slightly heavier than Mosby’s primary experimental apparatus for doing this carbon-12, but in terms of how it looks and behaves, the two is the Detector for Advanced Neutron Capture Experiments are essentially identical. -
STUDY of the NEUTRON and PROTON CAPTURE REACTIONS 10,11B(N, ), 11B(P, ), 14C(P, ), and 15N(P, ) at THERMAL and ASTROPHYSICAL ENERGIES
STUDY OF THE NEUTRON AND PROTON CAPTURE REACTIONS 10,11B(n, ), 11B(p, ), 14C(p, ), AND 15N(p, ) AT THERMAL AND ASTROPHYSICAL ENERGIES SERGEY DUBOVICHENKO*,†, ALBERT DZHAZAIROV-KAKHRAMANOV*,† *V. G. Fessenkov Astrophysical Institute “NCSRT” NSA RK, 050020, Observatory 23, Kamenskoe plato, Almaty, Kazakhstan †Institute of Nuclear Physics CAE MINT RK, 050032, str. Ibragimova 1, Almaty, Kazakhstan *[email protected] †[email protected] We have studied the neutron-capture reactions 10,11B(n, ) and the role of the 11B(n, ) reaction in seeding r-process nucleosynthesis. The possibility of the description of the available experimental data for cross sections of the neutron capture reaction on 10B at thermal and astrophysical energies, taking into account the resonance at 475 keV, was considered within the framework of the modified potential cluster model (MPCM) with forbidden states and accounting for the resonance behavior of the scattering phase shifts. In the framework of the same model the possibility of describing the available experimental data for the total cross sections of the neutron radiative capture on 11B at thermal and astrophysical energies were considered with taking into account the 21 and 430 keV resonances. Description of the available experimental data on the total cross sections and astrophysical S-factor of the radiative proton capture on 11B to the ground state of 12C was treated at astrophysical energies. The possibility of description of the experimental data for the astrophysical S-factor of the radiative proton capture on 14C to the ground state of 15N at astrophysical energies, and the radiative proton capture on 15N at the energies from 50 to 1500 keV was considered in the framework of the MPCM with the classification of the orbital states according to Young tableaux. -
Energy Deposition by Neutrons
22.55 “Principles of Radiation Interactions” Neutrons Classification of neutrons by energy Thermal: E < 1 eV (0.025 eV) Epithermal: 1 eV < E < 10 keV Fast: > 10 keV Neutron sources Neutron energies Reactors neutrons in the few keV to several MeV Fusion reactions 14 MeV Large accelerators Hundreds of MeV Energy Deposition by Neutrons • Neutrons are generated over a wide range of energies by a variety of different processes. • Like photons, neutrons are uncharged and do not interact with orbital electrons. • Neutrons can travel considerable distances through matter without interacting. • Neutrons will interact with atomic nuclei through several mechanisms. o Elastic scatter o Inelastic scatter o Nonelastic scatter o Neutron capture o Spallation • The type of interaction depends on the neutron energy Radiation Interactions: neutrons Page 1 of 8 22.55 “Principles of Radiation Interactions” Cross Sections • Because mass attenuation coefficients, µ/ρ (cm2/g) have dimensions of cm2 in the numerator, they have come to be called “cross sections”. • Cross sections do not represent a physical area, but a probability of an interaction. • Cross sections usually expressed in the unit, barn: (10-24 cm2) • The atomic cross sections can be derived from the mass attenuation coefficient. Photons Cross sections are attenuation coefficients, expressed at the atom level (Probability of interaction per atom) ρ N = atom density (#atoms/cm3) N = N A A A 0 2 σA = atomic cross section (cm /atom) 23 N0 = 6.02 x 10 atoms/mole ρ = g/cm3 µ = N A σ A A = g/mole ρ µ = N σ A 0 A µ N σ ⎛ µ ⎞⎛ A ⎞ 0 A ⎜ ⎟⎜ ⎟ = σ A = ⎜ ⎟⎜ ⎟ ρ A ⎝ ρ ⎠⎝ N 0 ⎠ Radiation Interactions: neutrons Page 2 of 8 22.55 “Principles of Radiation Interactions” Neutron Cross Sections Analogous to photons • Neutrons interact by different mechanisms depending on the neutron energy and the material of the absorber o Scattering • elastic • inelastic o Capture • Each energy loss mechanism has a cross section • Neutron cross sections expressed in barns (1 barn = 10-24 cm2). -
Computing Neutron Capture Rates in Neutron-Degenerate Matter †
universe Article Computing Neutron Capture Rates in Neutron-Degenerate Matter † Bryn Knight and Liliana Caballero * Department of Physics, University of Guelph, Guelph, ON N1G 2W1, Canada; [email protected] * Correspondence: [email protected] † This paper is based on the talk at the 7th International Conference on New Frontiers in Physics (ICNFP 2018), Crete, Greece, 4–12 July 2018. Received: 28 November 2018; Accepted: 16 January 2019; Published: 18 January 2019 Abstract: Neutron captures are likely to occur in the crust of accreting neutron stars (NSs). Their rate depends on the thermodynamic state of neutrons in the crust. At high densities, neutrons are degenerate. We find degeneracy corrections to neutron capture rates off nuclei, using cross sections evaluated with the reaction code TALYS. We numerically integrate the relevant cross sections over the statistical distribution functions of neutrons at thermodynamic conditions present in the NS crust. We compare our results to analytical calculations of these corrections based on a power-law behavior of the cross section. We find that although an analytical integration can simplify the calculation and incorporation of the results for nucleosynthesis networks, there are uncertainties caused by departures of the cross section from the power-law approach at energies close to the neutron chemical potential. These deviations produce non-negligible corrections that can be important in the NS crust. Keywords: neutron capture; neutron stars; degenerate matter; nuclear reactions 1. Introduction X-ray burst and superburst observations are attributed to accreting neutron stars (NSs) (see, e.g., [1,2]). In such a scenario, a NS drags matter from a companion star. -
Neutron Capture Cross Sections of Cadmium Isotopes
Neutron Capture Cross Sections of Cadmium Isotopes By Allison Gicking A thesis submitted to Oregon State University In partial fulfillment of the requirements for the degree of Bachelor of Science Presented June 8, 2011 Commencement June 17, 2012 Abstract The neutron capture cross sections of 106Cd, 108Cd, 110Cd, 112Cd, 114Cd and 116Cd were determined in the present project. Four different OSU TRIGA reactor facilities were used to produce redundancy in the results and to measure the thermal cross section and resonance integral separately. When the present values were compared with previously measured values, the differences were mostly due to the kind of detector used or whether or not the samples were natural cadmium. Some of the isotopes did not have any previously measured values, and in that case, new information about the cross sections of those cadmium isotopes has been provided. Table of Contents I. Introduction………………………………………………………………….…….…1 II. Theory………………………………………………………………………...…...…3 1. Neutron Capture…………………………………………………….….……3 2. Resonance Integral vs. Effective Thermal Cross Section…………...………5 3. Derivation of the Activity Equations…………………………………....…..8 III. Methods………………………………………………………….................…...…...12 1. Irradiation of the Samples………………………………………….….....…12 2. Sample Preparation and Parameters………………..………...………..……16 3. Efficiency Calibration of Detectors…………………………..………....…..18 4. Data Analysis…………………………………...…….………………...…..19 5. Absorption by 113Cd……………………………………...……...….………20 IV. Results………………………………………………….……………..……….…….22 -
22.4 Optimization of He-II UCN Source with Spallation Neutron Source
JP0150620 JAERI-Conf 2001-002 ICANS-XV 15th Meeting of the International Collaboration on Advanced Neutron Sources November 6-9,2000 Tsukuba, Japan 22.4 Optimization of He-II UCN Source with Spallation Neutron Source K. Mishima1, M. Ooi2, E. Choi1, Y. Kiyanagi2, Y. Masuda3*, S. Muto3, M. Tanaka4 and M. Yoshimura1 1 Research Center for Nuclear Physics, Osaka University, Ibaraki-shi, 567-0047 Japan 2 Hokkaido University, Sapporo-shi, 060-0808 Japan 3 KEK, 1-1 Oho, Tsukuba-shi, 305-0801 Japan 4 Kobe Tokiwa Collage, Kobe-shi, 653-0838 Japan * [email protected] Abstract A spallation neutron source was designed for super thermal UCN production in He-II. The configuration of neutron production target, moderator and He-II bottle was optimized in order to obtain high neutron flux with low y heating in He-II. In the optimization the advantage of the spallation neutron source is used: The spallation neutron source has high n/y ratio and freedom in target moderator configuration in comparison with the reactor. As a result, a great improvement in UCN density is expected compared with the present most intense UCN source at the Grenoble reactor. Introduction Ultra cold neutrons (UCNs) have been used for the measurements of /3 -decay lifetime, neutron electric dipole moment (EDM) and so on. UCNs have also a promising role in neutron p-decay asymmetry experiments. The experimental accuracy and - 1094 - JAERI-Conf 2001-002 possibility in these experiments are limited by UCN density. The motivation of the present work is to realize high intensity UCN source far beyond the Grenoble UCN source that is the most intense UCN source at present. -
Direct Measurement of the Neutron
Louisiana State University LSU Digital Commons LSU Doctoral Dissertations Graduate School 1-9-2020 Stellar Nucleosynthesis: Direct Measurement of the Neutron- Capture Cross Sections of Stable Germanium Isotopes and Design of a Next Generation Ion Trap for the Study of Beta- Delayed Neutron Emission Alexander Laminack Louisiana State University and Agricultural and Mechanical College Follow this and additional works at: https://digitalcommons.lsu.edu/gradschool_dissertations Part of the Instrumentation Commons, Nuclear Commons, Physical Processes Commons, and the Stars, Interstellar Medium and the Galaxy Commons Recommended Citation Laminack, Alexander, "Stellar Nucleosynthesis: Direct Measurement of the Neutron-Capture Cross Sections of Stable Germanium Isotopes and Design of a Next Generation Ion Trap for the Study of Beta- Delayed Neutron Emission" (2020). LSU Doctoral Dissertations. 5131. https://digitalcommons.lsu.edu/gradschool_dissertations/5131 This Dissertation is brought to you for free and open access by the Graduate School at LSU Digital Commons. It has been accepted for inclusion in LSU Doctoral Dissertations by an authorized graduate school editor of LSU Digital Commons. For more information, please [email protected]. STELLAR NUCLEOSYNTHESIS: DIRECT MEASUREMENT OF THE NEUTRON-CAPTURE CROSS SECTIONS OF STABLE GERMANIUM ISOTOPES AND DESIGN OF A NEXT GENERATION ION TRAP FOR THE STUDY OF β-DELAYED NEUTRON EMISSION A Dissertation Submitted to the Graduate Faculty of the Louisiana State University and Agricultural and Mechanical College in partial fulfillment of the requirements for the degree of Doctor of Philosophy in The Department of Physics and Astronomy by Alexander Laminack B. S., The Unviersity of Alabama, 2015 May 2020 To my wife and son: Kristy Allen Alexander Laminack and Daniel Allen Laminack. -
Safety Aspects in Plutonium Handling
B.A.R.C./I-259 1 < n GOVERNMENT OF INDIA ATOMIC ENERGY COMMISSION SAFETY ASPBCTS IN PLUTONIUM HANDLING by S. Janardhanan, T. N. Krishnamurthi, S. B. Dabhadkar and S. D. Soman Health Physics Division BHABHA ATOMIC RESEARCH CENTRE BOMBAY, INDIA 1973 B.AJI.C./I-259 GOVERNMENT OF INDIA ATOMIC ENERGY COMISSION SA5BTY ASPECTS IN FTAJTONIUM HANDLING by S. Janardhanan, T.N. Krishnamurthl, S.D. Dabhadkar and S.D. Soman Health HiyBics Division BHABHA ATOMIC RESEARCH CENTRE BOMBAY, INDIA 1973 COMPEMPS fege So. 1. INTRODUCTION 1 2. RADIOLOGICAL SAFETY 1 2.1 Formation of ELutoniun iBotopes 1 2.2 Nuclear Characteristics of FLutoniua Radionuclides 2 2.3 External Hazardo 2 2.4 Internal Hazards 23 3. ENGINEERING SAFETY 31 "5.1 Glove Box for Hutoniun Handling 31 3.2 Design Safety Consideration 32 3.3 Ventilation for Hutonlum Laboratory 35 3.4 Surfaoe Finish for Plutonium Laboratory 36 3.5 Ere -commie 8 ioning Checks for Plutonium Laboratory 56 4. aONTAMINVTION EVALUATION, CONTROL AND HffiVENTION 37 4.1 Special Technique for Pu-Alr Monitoring 38 4i2 Surface and Bars onnel Monitoring 39 4.3 Decontamination 39 5. PLUTONIUM FIRE SAFETY 48 5.1 Plutonium Metal FireB . 49 5.2 Protective Measures for Hutonium Fires 50 5.3 Fire Safety in Storage, Handling and Shipment of 51 HLutonium Metal 6. CRITICALITY SAFETY . 51 6.1 Oriticality BarameterB 52 6.2 MethodB of Criticality Control 54 6.3 Safety FactorB 55 Page No. 6.4 Criticelity Data 57 6.5 Soluble Poisons 61 f, .6 Solid Poisons 61 f) .7 Pipe Intersections 61 6.8 Storage of Pu Metal, Compounds and Solution 61 6.9 Transport of Plutonium Metal, Compounds and Solution 68 6.10 Magnitude of Critieality Accident 68 6.11 Administration of Nuclear Safety 72 REFERENCES 73 Appendix-Is Design Details of a Typical Inert Atmosphere 75 Glove Box for Plutonium Handling laboratory Appendix-Hi Design Details of a Typical Normal Atmosphere 79 Glove Box and Pumehood SAFETY ASPECTS ITT PLUTONIUM HANDLING by S. -
Cross Sections and Neutron Yields for U-233, U-235 and Pu-239 at 2200
AE-11 Cross sections and neutron yields for U233, U235 and Pu239 at 2200 mjsec. N.G. Sjostrand andJ.S. Story AKTIEBOLAGET ATOMENERGI STOCKHOLM • SWEDEN • I960 ADDENDUM to report AE - 11 233 Cross sections and neutron yields for U and Pu239 at 2200 m/sec. N. Go Sjostrand and J. S. Story This is a preliminary report written in February 1959 and not intended for wide distribution. No corrections or additions have been made for this new edition. AE-11 Cross sections and neutron yields for U233, U235 and Pu239 at 2200 m/sec. N.G. Sjostrand and J.S. Story Summary: The experimental information on the 2200 m/sec values for <r , , ™ 233 235 239 3-ds (T^, a, V, and rj for U , U and Pu has been collected and discussed. The values will later be used in an evaluation of a "best" set of data. In an appendix the isotopic abundances of the uranium isotopes are discussed and 239 also the alpha activities of the uranium isotopes and Pu . Printed April 1960 LIST OF CONTENTS Page The absorption cross-sections 2 Notes on data in Table 3 4 The fission cross section 5 The capture to fission ratio 9 The number of neutrons per fission 11 The number of fission neutrons per absorbed neutron 14 Appendix. Half-lives and atomic abundances of the isotopes in natural uranium 20 Notation 20 Experimental Results. Mass spectrometry 20 Alpha Counting Experiments 21 Assessment of Recommended Values 26 References 29 TABLES 1. g-factors according to WESTCOTT (1958) 1 2. 2 3.0".