The Spallation Neutron Source – Status and Applications
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MASTER 9700 South Cass Avenue Argonne, Illinois 60439 USA
ANL/KDH—SO DE84 001440 ANL/NDM-80 NEUTRON TOTAL CROSS SECTION MEASUREMENTS IN THE ENERGY REGION FROM 47 key to 20 MeV* by W. P. Poenitz and J. F. Whalon Applied Physics Division May, 1983 *This work supported by the U.S. Department of Energy Argonne National Laboratory MASTER 9700 South Cass Avenue Argonne, Illinois 60439 USA fflSTRtBtfUOU OF miS DOCUMENT IS UNLIMITED NUCLEAR DATA AMD MEASUREMENTS SERIES The Nuclear Data and Measurements Series presents results of studies in the field of microscopic nuclear data. The primary objective is the dissemination of information in the comprehensive form required for nuclear technology applications. This Series is devoted to: a) measured microscopic nuclear parameters, b) experimental techniques and facilities employed in measurements, c) the analysis, correlation and interpretation of nuclear data, and d) the evaluation of nuclear data. Contributions to this Series are reviewed to assure technical competence and, unless otherwise stated, the contents can be formally referenced. This Series does not supplant formal journal publication but it does provide the more extensive informa- tion required for technological applications (e.g., tabulated numerical data) in a timely manner. 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 retpoosi- 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. -
Uses of Isotopic Neutron Sources in Elemental Analysis Applications
EG0600081 3rd Conference on Nuclear & Particle Physics (NUPPAC 01) 20 - 24 Oct., 2001 Cairo, Egypt USES OF ISOTOPIC NEUTRON SOURCES IN ELEMENTAL ANALYSIS APPLICATIONS A. M. Hassan Department of Reactor Physics Reactors Division, Nuclear Research Centre, Atomic Energy Authority. Cairo-Egypt. ABSTRACT The extensive development and applications on the uses of isotopic neutron in the field of elemental analysis of complex samples are largely occurred within the past 30 years. Such sources are used extensively to measure instantaneously, simultaneously and nondestruclively, the major, minor and trace elements in different materials. The low residual activity, bulk sample analysis and high accuracy for short lived elements are improved. Also, the portable isotopic neutron sources, offer a wide range of industrial and field applications. In this talk, a review on the theoretical basis and design considerations of different facilities using several isotopic neutron sources for elemental analysis of different materials is given. INTRODUCTION In principle there are two ways to use neutrons for elemental and isotopic abundance analysis in samples. One is the neutron activation analysis which we call it the "off-line" where the neutron - induced radioactivity is observed after the end of irradiation. The other one we call it the "on-line" where the capture gamma-rays is observed during the neutron bombardment. Actually, the sequence of events occurring during the most common type of nuclear reaction used in this analysis namely the neutron capture or (n, gamma) reaction, is well known for the people working in this field. The neutron interacts with the target nucleus via a non-elastic collision, a compound nucleus forms in an excited state. -
PGNAA Neutron Source Moderation Setup Optimization
Submitted to ‘Chinese Physics C PGNAA neutron source moderation setup optimization Zhang Jinzhao1(张金钊)Tuo Xianguo1(庹先国) (1.Chengdu University of Technology Applied Nuclear Techniques in Geoscience Key Laboratory of Sichuan Province,Chengdu 610059,China) Abstract: Monte Carlo simulations were carried out to design a prompt γ-ray neutron activation analysis (PGNAA) thermal neutron output setup using MCNP5 computer code. In these simulations the moderator materials, reflective materials and structure of the PGNAA 252Cf neutrons of thermal neutron output setup were optimized. Results of the calcuations revealed that the thin layer paraffin and the thick layer of heavy water moderated effect is best for 252Cf neutrons spectrum. The new design compared with the conventional neutron source design, the thermal neutron flux and rate were increased by 3.02 times and 3.27 times. Results indicate that the use of this design should increase the neutron flux of prompt gamma-ray neutron activation analysis significantly. Key word: PGNAA; neutron source; thermal neutron; moderation; reflection 1. Introduction study, Monte Carlo calculation was carried out for the Prompt gamma ray neutron activation analysis design of a 252Cf neutron source moderation setup for the (PGNAA) is a rapid, nondestructive, powerful analysis cement samples[7]. The model of Monte Carlo multielemental analysis technique, large samples of some simulation was verified by experiment[8, 9].We improve minor, trace light elements and is used in industrial the thermal neutron source yield rate of 252Cf neutron by control[1-5]. In a PGNAA analysis, the sample nuclear the PGNAA neutron source structure to the design. The composition is determined from prompt gamma rays calculation results for the new design were compared which produced through neutron inelastic scattering and with the previous, example: themal neutron flux rate, fast thermal neutron capture. -
Arxiv:1506.05417V2 [Physics.Ins-Det] 28 Jul 2016
http://dx.doi.org/10.1016/j.apradiso.2016.06.032 A precise method to determine the activity of a weak neutron source using a germanium detector M. J. M. Dukea, A. L. Hallinb, C. B. Kraussb, P. Mekarskib,∗, L. Sibleyb aSLOWPOKE Nuclear Reactor Facility, University of Alberta, Edmonton, AB T6G 2G7, Canada bDepartment of Physics, University of Alberta, Edmonton, AB T6G 2E1, Canada Abstract A standard high purity germanium (HPGe) detector was used to determine the previously unknown neutron activity of a weak americium-beryllium (AmBe) neutron source. γ rays were created through 27Al(n,n0), 27Al(n,γ) and 1H(n,γ) reactions induced by the neutrons on aluminum and acrylic disks, respectively. These γ rays were measured using the HPGe detector. Given the unorthodox experimental arrangement, a Monte Carlo simulation was developed to model the efficiency of the detector system to determine the neutron activity from the measured γ rays. The activity of our neutron source was determined to be 307.4 ± 5.0 n/s and is consistent for the different neutron-induced γ rays. Keywords: neutron activation, germanium detector, simulation, spectroscopy, activity determination 1. Introduction As neutrons are difficult to detect, determining the absolute activity of a neutron source is challenging. This difficulty increases as the activity of the source decreases. Sophisticated techniques exist for neutron activity measure- ments, including the manganese bath technique[1], proton recoil techniques[2] and the use of 3He proportional counters[3]; nevertheless, the development of a method utilizing commonly available high purity germanium (HPGe) detectors would be advantageous. HPGe's are an industry standard for measuring γ ray energies to high preci- sion. -
Spallation Neutron Sources for Science and Technology
Proceedings of the 8th Conference on Nuclear and Particle Physics, 20-24 Nov. 2011, Hurghada, Egypt SPALLATION NEUTRON SOURCES FOR SCIENCE AND TECHNOLOGY M.N.H. Comsan Nuclear Research Center, Atomic Energy Authority, Egypt Spallation Neutron Facilities Increasing interest has been noticed in spallation neutron sources (SNS) during the past 20 years. The system includes high current proton accelerator in the GeV region and spallation heavy metal target in the Hg-Bi region. Among high flux currently operating SNSs are: ISIS in UK (1985), SINQ in Switzerland (1996), JSNS in Japan (2008), and SNS in USA (2010). Under construction is the European spallation source (ESS) in Sweden (to be operational in 2020). The intense neutron beams provided by SNSs have the advantage of being of non-reactor origin, are of continuous (SINQ) or pulsed nature. Combined with state-of-the-art neutron instrumentation, they have a diverse potential for both scientific research and diverse applications. Why Neutrons? Neutrons have wavelengths comparable to interatomic spacings (1-5 Å) Neutrons have energies comparable to structural and magnetic excitations (1-100 meV) Neutrons are deeply penetrating (bulk samples can be studied) Neutrons are scattered with a strength that varies from element to element (and isotope to isotope) Neutrons have a magnetic moment (study of magnetic materials) Neutrons interact only weakly with matter (theory is easy) Neutron scattering is therefore an ideal probe of magnetic and atomic structures and excitations Neutron Producing Reactions -
Fusion and Spallation Irradiation Conditions Steven J
Fusion and Spallation Irradiation Conditions Steven J. Zinkle Metals and Ceramics Division Oak Ridge National Laboratory, Oak Ridge, TN International Workshop on Advanced Computational Science: Application to Fusion and Generation-IV Fission Reactors Washington DC, March 31-April 2, 2004 Comparison of fission and fusion (ITER) neutron spectra Stoller & Greenwood, JNM 271-272 (1999) 57 • Main difference between fission and DT fusion neutron spectra is the presence of significant flux above ~4 MeV for fusion –High energy neutrons typically cause enhanced production of numerous transmutation products including H and He –The Primary Knock-on Atom (PKA) spectra are similar for fission and fusion at low energies; fusion contains significant high-energy PKAs (>100 keV) Displacement Damage Mechanisms are being investigated with Molecular Dynamics Simulations Damage efficiency saturates when subcascade formation occurs Avg. Avg. fission fusion Molecular dynamics modeling of displacement cascades up to 50 keV PKA 200 keV and low-dose experimental tests (microstructure, tensile (ave. fusion) properties, etc.) indicates that defect production from fusion and fission neutron collisions are similar 10 keV PKA => Defect source term is similar for fission and fusion conditions (ave. fission) Peak damage state in iron cascades at 100K 5 nm A critical unanswered question is the effect of higher transmutant H and He production in the fusion spectrum Radiation Damage can Produce Large Changes in Structural Materials • Radiation hardening and embrittlement -
Neutron Sources
Neutron Sources Nadia Fomin Fundamental Neutron Physics Summer School Knoxville, TN 2015 Much content “borrowed” from Kevin Anderson, Mike Snow, Geoff 1 Greene, Scott Dewey, Mike Moncko, Jack Carpenter, and many others http://knoxbeerweek.com/ Neutron Sources Nadia Fomin Fundamental Neutron Physics Summer School Knoxville, TN 2015 Much content “borrowed” from Kevin Anderson, Mike Snow, Geoff 3 Greene, Scott Dewey, Mike Moncko, Jack Carpenter, and many others What is neutron physics ? Research which uses “low energy” neutrons from nuclear reactors and accelerator-driven spallation sources to address questions in nuclear, particle, and astrophysics Neutron Properties -22 Electric charge: qn=0, electrically neutral [qn<10 e] -5 -25 2 Size: rn~10 Angstrom=1 Fermi [area~ 10 cm =0.1 “barn”] Internal Structure: quarks [ddu, md~ mu~few MeV ] + gluons Spin: sn= 1/2 [Fermi statistics] Magnetic Dipole Moment: mn/ mp = -0.68497935(17) -26 Electric Dipole Moment: zero[dn < 10 e-cm] Mass: mn=939.566 MeV [mn> mp+ me, neutrons can decay] Lifetime: tn=880ish (depends on whom you ask) Neutrons are hard to get Neutrons are bound in nuclei, need several MeV for liberation E E=0 We want E~kT~25 meV (room temperature) VNN How to slow down a heavy neutral particle with Mn= Mp ? Lots of collisions… p n [1/2]N=(1 MeV)/(25 meV) for N collisions E 0 E/2 Neutrons are unstable when free->they can’t be accumulated easily Neutrons: Fast and Furious. And slow and gentle . Thermal ~25meV (2200m/s, λT=1.8Å) . Cold 50μeV-25meV . Very cold 2x10-7 - 5x10-5 eV . -
NUCLIDES FAR OFF the STABILITY LINE and SUPER-HEAVY NUCLEI in HEAVY-ION NUCLEAR REACTIONS Marc Lefort
NUCLIDES FAR OFF THE STABILITY LINE AND SUPER-HEAVY NUCLEI IN HEAVY-ION NUCLEAR REACTIONS Marc Lefort To cite this version: Marc Lefort. NUCLIDES FAR OFF THE STABILITY LINE AND SUPER-HEAVY NUCLEI IN HEAVY-ION NUCLEAR REACTIONS. Journal de Physique Colloques, 1972, 33 (C5), pp.C5-73-C5- 102. 10.1051/jphyscol:1972507. jpa-00215109 HAL Id: jpa-00215109 https://hal.archives-ouvertes.fr/jpa-00215109 Submitted on 1 Jan 1972 HAL is a multi-disciplinary open access L’archive ouverte pluridisciplinaire HAL, est archive for the deposit and dissemination of sci- destinée au dépôt et à la diffusion de documents entific research documents, whether they are pub- scientifiques de niveau recherche, publiés ou non, lished or not. The documents may come from émanant des établissements d’enseignement et de teaching and research institutions in France or recherche français ou étrangers, des laboratoires abroad, or from public or private research centers. publics ou privés. JOURNAL RE PHYSIQUE CoLIoque C5, supplement au no 8-9, Tome 33, Aoiit-Septembre 1972, page C5-73 NUCLIDES FAR OFF THE STABILITY LINE AND SUPER-HEAVY NUCLEI IN HEAW-ION NUCLEAR REACTIONS by Marc Lefort Chimie Nucleaire-Institut de Physique Nucleaire-ORSAY, France Abstract A review is given on the new species which attempts already made for the synthesis of super- have been produced in the recent years by heavy ion heavy elements. A discussion is presented on the reactions, mainly 12C, 160, ''0, 22~eand 20~eions. following problems : reaction thresholds and The first section is devoted to the formation of coulomb barriers for heavily charged projectiles, neutron rich exotic light nuclei and to the mecha- complete fusion cross section as compared to the nism of multinuclear transfer reactions responsible total cross section, main decay channels for exci- for this formation. -
Synthesis of Neutron-Rich Transuranic Nuclei in Fissile Spallation Targets
Synthesis of neutron-rich transuranic nuclei in fissile spallation targets Igor Mishustina,b, Yury Malyshkina,c, Igor Pshenichnova,c, Walter Greinera aFrankfurt Institute for Advanced Studies, J.-W. Goethe University, 60438 Frankfurt am Main, Germany b“Kurchatov Institute”, National Research Center, 123182 Moscow, Russia cInstitute for Nuclear Research, Russian Academy of Science, 117312 Moscow, Russia Abstract A possibility of synthesizing neutron-reach super-heavy elements in spal- lation targets of Accelerator Driven Systems (ADS) is considered. A dedi- cated software called Nuclide Composition Dynamics (NuCoD) was developed to model the evolution of isotope composition in the targets during a long-time irradiation by intense proton and deuteron beams. Simulation results show that transuranic elements up to 249Bk can be produced in multiple neutron capture reactions in macroscopic quantities. However, the neutron flux achievable in a spallation target is still insufficient to overcome the so-called fermium gap. Fur- ther optimization of the target design, in particular, by including moderating material and covering it by a reflector will turn ADS into an alternative source of transuranic elements in addition to nuclear fission reactors. 1. Introduction Neutrons propagating in a medium induce different types of nuclear reactions depending on their energy. Apart of the elastic scattering, the main reaction types for low-energy neutrons are fission and neutron capture, which dominate, respectively, at higher and lower energies with the boarder -
Status of the Project and Physics of the Spallation Target
PHYSOR 2004 -The Physics of Fuel Cycles and Advanced Nuclear Systems: Global Developments Chicago, Illinois, April 25-29, 2004, on CD-ROM, American Nuclear Society, Lagrange Park, IL. (2004) The TRADE Experiment: Status of the Project and Physics of the Spallation Target C. Rubbia1, P. Agostini1, M. Carta1, S. Monti1, M. Palomba1, F. Pisacane1, C. Krakowiak2, M. Salvatores2, Y. Kadi*3, A. Herrera-Martinez3, L. Maciocco4 1ENEA, Lungotevere Thaon di Revel, 00196 Rome, ITALY 2CEA, CEN-Cadarache, 13108 Saint-Paul-Lez-Durance, FRANCE 3CERN, 1211 Geneva 23, SWITZERLAND 4AAA, 01630 Saint-Genis-Pouilly, FRANCE The neutronic characteristics of the target-core system of the TRADE facility have been established and optimized for a reference proton energy of 140 MeV. Similar simulations have been repeated for two successive upgrades of the proton energy, 200 and 300 MeV, corresponding to different performances and design requirements and different characteristics of the proposed cyclotron and, as a consequence, of the proton beam. An extensive comparison of the main physical parameters has been also carried out, in order to evaluate advantages and disadvantages of different proton beam energies in the design of the spallation target and to allow the optimal engineering design of the whole TRADE facility. KEYWORDS: TRADE facility, ADS, Spallation target physics, Experimentation, External neutron sources, intermediate proton energy. 1. Introduction The TRADE “TRiga Accelerator Driven Experiment”, to be performed in the existing TRIGA reactor of the ENEA Casaccia Centre, has been proposed as a major project in the way for validating the ADS concept. Actually, TRADE will be the first experiment in which the three main components of an ADS – the accelerator, the spallation target and the sub- critical blanket – will be coupled at a power level sufficient to appreciate feedback reactivity effects. -
Spallation and Neutron-Capture Produced Cosmogenic Nuclides in Aubrites
70th Annual Meteoritical Society Meeting (2007) 5054.pdf SPALLATION AND NEUTRON-CAPTURE PRODUCED COSMOGENIC NUCLIDES IN AUBRITES. J. Masarik1, K. Nishiizumi2 and K. C. Welten2, 1Department of Nuclear Physics, Comenius University Bratislava, Slovakia, E-mail: ma- [email protected], 2Space Sciences Laboratory, University of California, Berkeley, CA 94720, USA, Introduction: A purely physical model for the simulation of cosmic-ray-particle interactions with matter was used to investi- gate the production rates of cosmogenic nuclides in aubrites with radii ranging from 5 cm to 120 cm. Production rates of spal- logenic and neutron-capture produced nuclides were investigated and compared with measured cosmogenic nuclide concentrations to constrain the complex exposure histories of aubrites. Calculational Model: The numerical simulation of interac- tions of primary and secondary cosmic-ray particles was done with the LAHET Code System (LCS) [1] which uses MCNP [2] for transport of low energy neutrons. The investigated objects were spheres with various radii that were divided into spherical layers. We used the spectrum of the galactic-cosmic-ray particles corresponding to solar modulation parameter Φ = 550 MeV and a flux of 4.8 protons/s·cm2. The statistical errors of the LCS calcu- lated fluxes were 3–5%. The production rates of nuclides were calculated by integrating over energy the product of these fluxes and cross sections for the nuclear reactions making the investi- gated nuclide. For cross sections of spallogenic products, we relied on the values evaluated by us and tested by earlier calcula- tions [e.g., 3]. Previous calculations of the 53Mn production rate in aubrites showed good agreement with measured 53Mn concen- trations in the Norton County aubrite [4]. -
Pulsed Spallation Neutron Sources
(LoMr^** U-J / •*> =* —%3 f& APR 1 7 1938 OSTI PULSED SPALLATION NEUTRON SOURCES John M. Carpenter Intense Pulsed Neutron Source Division Argonne National Laboratory This paper reviews the early history of pulsed spallation neutron source development at Argonne and provides an overview of existing sources world wide. A number of proposals for machines more powerful than currently exist are under development, which are briefly described. I review the status of the Intense Pulsed Neutron Source, its instrumentation, and its user program, and provide a few examples of applications in fundamental condensed matter physics, materials science and technology. HISTORY OF PULSED SOURCE DEVELOPMENTS AT ARGONNE This is a day for remembering, reflecting and projecting into the future. Think back to the year 1968,26 years ago. Please don't fix upon the gathering war half a world away, the * burnings in our cities, or the riots in our own Grant Park; these were dark rumblings of political change that even now have not played out. Think instead of the scientific scene. ZGS had already been operating for five years and improvements were afoot. New, bigger machines were being designed and built around the world for high energy physics research. Several high flux research reactors were under design, construction or commissioning: HFBR (Brookhaven), HFIR (Oak Ridge), HFR (ILL Grenoble), A^R2 (Argonne), British HFR. Argonne had an already long-established tradition in neutron scattering based on its smaller research reactors, beginning with Enrico Fermi and Walter Zinn at CP-3, and continuing at the 5-MW CP-5. In January of 1968, as a young and dewy professor of Nuclear Engineering at the University of Michigan, where I had built some instruments for neutron scattering research at the 2-MW Ford Reactor, I was invited to serve in an instrument design group, led by Don Connor of the SSS division, that was supposed eventually to provide instruments for A^R2.