WorldWideScience

Sample records for weapons neutron research

  1. Weapons Neutron Research Facility (WNR)

    Data.gov (United States)

    Federal Laboratory Consortium — The Weapons Neutron Research Facility (WNR) provides neutron and proton beams for basic, applied, and defense-related research. Neutron beams with energies ranging...

  2. The use of neutron scattering in nuclear weapons research

    Energy Technology Data Exchange (ETDEWEB)

    Juzaitis, R.J. [Los Alamos National Lab., NM (United States)

    1995-10-01

    We had a weapons science breakout session last week. Although it would have been better to hold it closer in time to this workshop, I think that it was very valuable. it may have been less of a {open_quotes}short-sleeve{close_quotes} workshop environment than we would have liked, but as the first time two communities-the weapons community and the neutron scattering community- got together, it was a wonderful opportunity to transfer information during the 24 presentations that were made. This report contains discussions on the fundamental analysis of documentation of the enduring stockpile; LANSCE`s contribution to weapons; spallation is critical to understanding; weapons safety assessments; applied nuclear physics requires cross section information; fission models need refinement; and establishing teams on collaborative projects.

  3. Operational research in weapon system

    Directory of Open Access Journals (Sweden)

    R. S. Varma

    1958-04-01

    Full Text Available "The paper is divided into three parts: (a The first part deals with what operational research is. (bThe second part gives what we mean by Weapon Systems and discusses considerations that determine the choice of a particular weapon system from a class weapon systems. (cThe third part deals with some aspects of weapon replacement policy.The effectiveness of a weapon system is defined as E=D/C where E is weapon effectiveness (a comparative figure of merit; D is total damage inflicted or prevented and C is total cost, D and C being reduced to common dimensions. During the course of investigations, criteria regarding to choice of weapon or weapons from a set of weapon systems are established through production function and military effect curves. A procedure is described which maximizes the expectation of military utility in order to select a weapon system from the class of weapon systems. This is done under the following simplifying assumptions: (a Non- decreasing utility function; (b Constant average cost for each kind of weapons; and (c Independence of the performance of each unit of weapon. Some of the difficulties which arises when any of these restrictions is relaxed are briefly mentioned. Finally, the policy of weapon replacement and the factors governing the same are described."

  4. The morality of weapons research.

    Science.gov (United States)

    Forge, John

    2004-07-01

    I ask whether weapons research is ever justified. Weapons research is identified as the business of the engineer. It is argued that the engineer has responsibility for the uses to which the tools that he designs can be put, and that responsibility extends to the use of weapons. It is maintained that there are no inherently defensive weapons, and hence there is no such thing as 'defensive' weapons research. The issue then is what responsibilities as a professional the engineer has in regard to such research. An account is given to ground the injunction not to provide the means to harm as a duty for the engineers. This account is not, however, absolutist, and as such it allows justifiable exceptions. The answer to my question is thus not that weapons research is never justified but there must be a strong assurance that the results will only be used as a just means in a just cause.

  5. History of Laser Weapon Research

    Science.gov (United States)

    2012-01-01

    surgery/medicine, hair re- moval, presentation pointers, law enforcement, ranging and sighting devices, welding applications, and much more. Using...other laser technology develop- ments. The first chemical laser, hydrogen fluoride ( HF ), was built in 1965, producing 1 kW. It was then that DoD became...energy laser (HEL) weapons. In industry, the more powerful CO2 lasers are used for weld - ing, drilling, and cutting. There are many different types

  6. Los Alamos neutron science center nuclear weapons stewardship and unique national scientific capabilities

    Energy Technology Data Exchange (ETDEWEB)

    Schoenberg, Kurt F [Los Alamos National Laboratory

    2010-12-15

    This presentation gives an overview of the Los Alamos Neutron Science Center (LANSCE) and its contributions to science and the nuclear weapons program. LANSCE is made of multiple experimental facilities (the Lujan Center, the Weapons Neutron Research facility (WNR), the Ultra-Cold Neutron facility (UCN), the proton Radiography facility (pRad) and the Isotope Production Facility (IPF)) served by the its kilometer long linear accelerator. Several research areas are supported, including materials and bioscience, nuclear science, materials dynamics, irradiation response and medical isotope production. LANSCE is a national user facility that supports researchers worldwide. The LANSCE Risk Mitigation program is currently in progress to update critical accelerator equipment to help extend the lifetime of LANSCE as a key user facility. The Associate Directorate of Business Sciences (ADBS) plays an important role in the continued success of LANSCE. This includes key procurement support, human resource support, technical writing support, and training support. LANSCE is also the foundation of the future signature facility MARIE (Matter-Radiation Interactions in Extremes).

  7. Chemical weapons detection by fast neutron activation analysis techniques

    Science.gov (United States)

    Bach, P.; Ma, J. L.; Froment, D.; Jaureguy, J. C.

    1993-06-01

    A neutron diagnostic experimental apparatus has been tested for nondestructive verification of sealed munitions. Designed to potentially satisfy a significant number of van-mobile requirements, this equipment is based on an easy to use industrial sealed tube neutron generator that interrogates the munitions of interest with 14 MeV neutrons. Gamma ray spectra are detected with a high purity germanium detector, especially shielded from neutrons and gamma ray background. A mobile shell holder has been used. Possible configurations allow the detection, in continuous or in pulsed modes, of gamma rays from neutron inelastic scattering, from thermal neutron capture, and from fast or thermal neutron activation. Tests on full scale sealed munitions with chemical simulants show that those with chlorine (old generation materials) are detectable in a few minutes, and those including phosphorus (new generation materials) in nearly the same time.

  8. Historical fencing and scientific research medieval weapons: common ground

    Directory of Open Access Journals (Sweden)

    B. V. Hrynchyshyn

    2015-07-01

    We considered various approaches to the reconstruction of the historical fencing. It is proved that the activities of such societies has a positive effect on the process research of features of medieval weapons, fighting tactics of different periods The various approaches to the reconstruction of the historical fencing. Proved that the activities of such societies has a positive effect on the process research of features of medieval weapons, fighting tactics of different periods.

  9. Instruments and accessories for neutron scattering research

    Energy Technology Data Exchange (ETDEWEB)

    Ishii, Yoshinobu; Morii, Yukio [eds.] [Advanced Science Research Center (Tokai Site), Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

    2000-04-01

    This report describes neutron scattering instruments and accessories installed by four neutron scattering research groups at the ASRC (Advanced Science Research Center) of the JAERI and the recent topics of neutron scattering research using these instruments. The specifications of nine instruments (HRPD, BIX-I, TAS-1 and PNO in the reactor hall, RESA, BIX-II, TAS-2, LTAS and SANS-J in the guide hall of the JRR-3M) are summarized in this booklet. (author)

  10. CURRENT ISSUES IN THE RESEARCH OF COLD STEEL ARMS AND THROWING WEAPONS AND THEIR TRACES

    Directory of Open Access Journals (Sweden)

    Meretukov G. M.

    2016-05-01

    Full Text Available The authors of the article point out that the research of cold steel arms and their traces has been considered in detail in the studies of different criminologists. Unfortunately, many scientists, examining cold steel arms as the item of expertise, mainly paid attention to the knives, swords, daggers, etc., but few researchers considered crossbows as cold steel weapon. In accordance with part. 4 Art. 223 of the Criminal Code of Russia for illegal manufacture, alteration or repair of throwing weapons, as well as the illegal sale of throwing weapons (Art. 4, Art. 222 of the Criminal Code, criminal liability is stipulated. Thus, the authors agree with the opinions expressed in the literature according to which attention should be paid to the fuzzy wording of p. 4 Art. 222 of the Criminal Code and p. 4 Art. 223 of the Criminal Code of the Russian Federation: "Cold steel weapons, including throwing weapons". Throwing weapons are not included in the number of cold steel arms; it is an independent type of weapon that is different from the cold steel by its technical characteristics. The common feature of cold steel arms and throwing weapons is striking of a target due to the muscle power of a man. The main difference is that there is no projectile with directional movement in cold steel arms and striking occurs due to the direct contact with the object. The definitions of these types of weapons are contained in the Federal Act "About Weapons"

  11. Chemistry and materials science progress report. Weapons-supporting research and laboratory directed research and development: FY 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-04-01

    This report covers different materials and chemistry research projects carried out a Lawrence Livermore National Laboratory during 1995 in support of nuclear weapons programs and other programs. There are 16 papers supporting weapons research and 12 papers supporting laboratory directed research.

  12. Polarized neutrons for Australian scientific research

    Science.gov (United States)

    Kennedy, Shane J.

    2005-02-01

    Polarized neutron scattering has been a feature at ANSTO's HIFAR research reactor since the first polarization analysis (PA) spectrometer Longpol began operation over 30 years ago. Since that time, we have improved performance of Longpol and added new capabilities in several reincarnations of the instrument. Most of the polarized neutron experiments have been in the fields of magnetism and superconductivity, and most of that research has involved PA. Now as we plan our next generation neutron beam facility, at the Replacement Research Reactor (RRR), we intend to continue the tradition of PA but with a far broader scope in mind. Our new capabilities will combine PA and energy analysis with both cold and thermal neutron source spectra. We will also provide capabilities for research with polarized neutrons in small-angle neutron scattering and in neutron reflectometry. The discussion includes a brief historical account of the technical developments with a summary of past and present applications of polarized neutrons at HIFAR, and an outline of the polarized neutron capabilities that will be included in the first suite of instruments, which will begin operation at the new reactor in 2006.

  13. Defense, basic, and industrial research at the Los Alamos Neutron Science Center: Proceedings

    Energy Technology Data Exchange (ETDEWEB)

    Longshore, A.; Salgado, K. [comps.

    1995-10-01

    The Workshop on Defense, Basic, and Industrial Research at the Los Alamos Neutron Science Center gathered scientists from Department of Energy national laboratories, other federal institutions, universities, and industry to discuss the use of neutrons in science-based stockpile stewardship, The workshop began with presentations by government officials, senior representatives from the three weapons laboratories, and scientific opinion leaders. Workshop participants then met in breakout sessions on the following topics: materials science and engineering; polymers, complex fluids, and biomaterials; fundamental neutron physics; applied nuclear physics; condensed matter physics and chemistry; and nuclear weapons research. They concluded that neutrons can play an essential role in science-based stockpile stewardship and that there is overlap and synergy between defense and other uses of neutrons in basic, applied, and industrial research from which defense and civilian research can benefit. This proceedings is a collection of talks and papers from the plenary, technical, and breakout session presentations. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

  14. Research in boron neutron capture synovectomy

    Science.gov (United States)

    Binello, E.; Shortkroff, S.; Jones, A.; Viveiros, C.; Ly, A.; Sledge, C. B.; Davison, A.; Shefer, Ruth E.; Yanch, Jacquelyn C.

    1997-02-01

    Boron Neutron Capture Synovectomy (BNCS) is a novel application of the 10B(n, (alpha) )7Li reaction for the treatment of Rheumatoid Arthritis. This potential treatment modality is in its developmental stages; in this paper results of research in two aspects of BNCS are presented. First, quantification of 10B-uptake in samples of human arthritic tissue by Prompt Gamma Neutron Activation Analysis is presented. 10B concentrations from 1625 to 2726 ppm are readily achieved. Second, ideal neutron beam studies have been undertaken and indicate that neutrons from thermal energies to 1 keV are useful for BNCS. This information is of use in designing practical therapy beams should this treatment modality be realized.

  15. Mode Research on Space Weapons Systems Innovation Based Quality Function Deployment

    Directory of Open Access Journals (Sweden)

    Wang Xiuhong

    2011-06-01

    Full Text Available in the aviation industry, experts are enthusiastic over the research of sophisticated weapons. Little specialist pays attention to the innovation modes and methods. Up to now little quantization method suitable for aviation weapon systems innovation is presented. Base on the deep analysis and study on features of aviation weapon systems innovation and different innovation mode from the mass production, we have designed process model and quality chain model of aviation weapon systems innovation. Compared with the process model of large-scale innovation, the process models are more complex including many feedbacks and adding five steps: task decomposition, analysis of knowledge gap, accumulation of key knowledge, outsourcing selection, system integration. Meanwhile manufacturing process and R&D process are preformed simultaneously, and are involved in the process of module development. Technology application and diffusion are preformed with delivering the final innovation product to user. Quality function deployment and quality house are adopted to deal with the quality transfer among nodes. Quality demands of one node are converted into the technique features of another node in the quality house. We designed the top-down technique features transfer model and bottom-up demands transfer model to solve the quality transfer problems among nodes. At last an example is given to illustrate that this approach can accelerate to blaze the aviation weapon systems trails more than the existing methods and effectively reach quality management of aviation weapon systems innovation.

  16. Neutron scattering at Australia's replacement research reactor

    Science.gov (United States)

    Robinson, R. A.; Kennedy, S. J.

    2002-01-01

    On August 25 1999, the Australian government gave final approval to build a research reactor to replace the existing HIFAR reactor at Lucas Heights. The replacement reactor, which will commence operation in 2005, will be multipurpose in function, with capabilities for both neutron-beam research and radioisotope production. Regarding beams, cold and thermal neutron sources are to be installed and the intent is to use supermirror guides, with coatings with critical angles up to 3 times that of natural Ni, to transport cold and thermal neutron beams into a large modern guide hall. The reactor and all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by INVAP, SE and subcontractors in a turnkey contract. The goal is to have at least eight leading-edge neutron-beam instruments ready in 2005, and they will be developed by ANSTO and other contracted organisations, in consultation with the Australian user community and interested overseas parties. A review of the planned scientific capabilities, a description of the facility and a status report on the activities so far is given.

  17. National facility for neutron beam research

    Indian Academy of Sciences (India)

    K R Rao

    2004-07-01

    In this talk, the growth of neutron beam research (NBR) in India over the past five decades is traced beginning with research at Apsara. A range of problems in condensed matter physics could be studied at CIRUS, followed by sophisticated indegenous instrumentation and research at Dhruva. The talk ends with an overview of current scenario of NBR world-wide and future of Indian activities.

  18. Biological effectiveness of neutrons: Research needs

    Energy Technology Data Exchange (ETDEWEB)

    Casarett, G.W.; Braby, L.A.; Broerse, J.J.; Elkind, M.M.; Goodhead, D.T.; Oleinick, N.L.

    1994-02-01

    The goal of this report was to provide a conceptual plan for a research program that would provide a basis for determining more precisely the biological effectiveness of neutron radiation with emphasis on endpoints relevant to the protection of human health. This report presents the findings of the experts for seven particular categories of scientific information on neutron biological effectiveness. Chapter 2 examines the radiobiological mechanisms underlying the assumptions used to estimate human risk from neutrons and other radiations. Chapter 3 discusses the qualitative and quantitative models used to organize and evaluate experimental observations and to provide extrapolations where direct observations cannot be made. Chapter 4 discusses the physical principles governing the interaction of radiation with biological systems and the importance of accurate dosimetry in evaluating radiation risk and reducing the uncertainty in the biological data. Chapter 5 deals with the chemical and molecular changes underlying cellular responses and the LET dependence of these changes. Chapter 6, in turn, discusses those cellular and genetic changes which lead to mutation or neoplastic transformation. Chapters 7 and 8 examine deterministic and stochastic effects, respectively, and the data required for the prediction of such effects at different organizational levels and for the extrapolation from experimental results in animals to risks for man. Gaps and uncertainties in this data are examined relative to data required for establishing radiation protection standards for neutrons and procedures for the effective and safe use of neutron and other high-LET radiation therapy.

  19. Basic to industrial research on neutron platform in Japan

    Indian Academy of Sciences (India)

    Yasuhiko Fujii

    2008-10-01

    The co-location of reactor- and accelerator-based neutron sources offers a great opportunity for complementary use of steady and pulsed neutron beams in a wide variety of neutron science and technology areas ranging from basic research to industrial applications. In Japan, such a balance of two kinds of neutron sources has a long tradition and now we are entering into a new era with the commissioning of the world’s most intense pulsed neutron beams at JSNS/J-PARC plus the existing JRR-3 reactor both co-located within 1 km of each other in Tokai. The joint operation of these neutron facilities in close proximity under a program called `neutron platform', will allow neutron beam access not only to professional users, familiar with both pulsed and steady state techniques but also to first-time academics and industrial researchers to neutron scattering.

  20. Fundamental physics research and neutron interferometry

    Energy Technology Data Exchange (ETDEWEB)

    Ioffe, A. [Hahn-Meitner-Institut Berlin GmbH (Germany)

    1996-08-01

    The possibility of the use of an extremely sensitive neutron interferometry technique for the study of electromagnetic structure of the neutron and the parity non-conservative effects in neutron spin rotation is discussed. (author)

  1. Chemistry {ampersand} Materials Science program report, Weapons Resarch and Development and Laboratory Directed Research and Development FY96

    Energy Technology Data Exchange (ETDEWEB)

    Chase, L.

    1997-03-01

    This report is the annual progress report for the Chemistry Materials Science Program: Weapons Research and Development and Laboratory Directed Research and Development. Twenty-one projects are described separately by their principal investigators.

  2. A polyethylene-B4C based concrete for enhanced neutron shielding at neutron research facilities

    Science.gov (United States)

    DiJulio, D. D.; Cooper-Jensen, C. P.; Perrey, H.; Fissum, K.; Rofors, E.; Scherzinger, J.; Bentley, P. M.

    2017-07-01

    We present the development of a specialized concrete for neutron shielding at neutron research facilities, based on the addition of hydrogen atoms in the form of polyethylene and also B4C for enhancing the neutron capture properties of the concrete. We show information on the mechanical properties of the concrete and the neutronics, in particular its relevance to modern spallation neutron sources, such as the European Spallation Source (ESS), currently under construction in Lund, Sweden. The new concrete exhibits a 15% lower mass density, a compressible strength of 50% relative to a standard concrete and a significant increase in performance of shielding against MeV neutrons and lower energies. The concrete could find application at the ESS in for example common shielding components, individual beamline shielding and instrument caves. Initial neutronic tests of the concrete, carried out at Lund University, have also verified the performance in the MeV neutron energy range and the results are presented.

  3. Reconversion of nuclear weapons

    CERN Document Server

    Kapitza, Sergei P

    1993-01-01

    The nuclear predicament or nuclear option. Synopsis of three lectures : 1- The physical basis of nuclear technology. Physics of fission. Chain reaction in reactors and weapons. Fission fragments. Separration of isotopes. Radiochemistry.2- Nuclear reactors with slow and fast neutrons. Power, size, fuel and waste. Plutonium production. Dose rate, shielding and health hazard. The lessons of Chernobyl3- Nuclear weapons. Types, energy, blast and fallout. Fusion and hydrogen bombs. What to do with nuclear weapons when you cannot use them? Testing. Nonmilittary use. Can we get rid of the nuclear weapon? Nuclear proliferation. Is there a nuclear future?

  4. Research on Prompt Neutron Multiplicity Distribution at Thermal Neutrons

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The prompt neutron multiplicity distribution as a function of mass of fission fragments ν(A) was studied using the semi-empirical method of excitation energy distributions between the two fission

  5. Center for Neutron Research Project. Status report

    Energy Technology Data Exchange (ETDEWEB)

    West, C.D.; Primm, R.T. III; Copeland, G.L.; Difilippo, F.C.; Griess, J.C.; Gambill, W.R.; Moon, R.M.; Siman-Tov, I.I.

    1986-09-01

    The Center for Neutron Research (CNR) will provide the world's best facilities for the study of neutron scattering. The CNR will contain a very high flux reactor that will achieve an extremely high power density (between 4 and 8 MW/L). The reactor is to be fueled with uranium silicide and cooled, moderated, and reflected by D/sub 2/O. Initial reactor physics calculations indicate that a power level of 270 MW with a reactor core volume of 35 L will achieve a peak thermal flux in the reflector of 10/sup 20/ neutrons x m/sup -2/ x s/sup -1/. The reactor fuel will be contained in thin (1.3-mm) plates, similar to those employed in the very successful High-Flux Isotope Reactor, and will be graded in the axial and radial directions. Coolant velocity is to be 27 m/s, and core inlet pressure is to be 5.6 MPa. Maximum fuel centerline temperature will be approx.350/sup 0/C. Initial thermal-hydraulic studies indicate that some method of preventing the formation of aluminum oxide on the fuel clad is required if the highest performance is to be achieved. Tests to confirm these calculations are planned. One of the experimental facilities is to be a cold (10-MeV) neutron source. Calculations to determine the size of the source have been initiated, but additional cross-section data are needed. An abbreviated version of a tentative program plan for fiscal year 1987 and beyond is described. Total program expenditures are expected to be $40 million over 5 years.

  6. Basic Design of the Cold Neutron Research Facility in HANARO

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Hark Rho; Lee, K. H.; Kim, Y. K. (and others)

    2005-09-15

    The HANARO Cold Neutron Research Facility (CNRF) Project has been embarked in July 2003. The CNRF project has selected as one of the radiation technology development project by National Science and Technology Committee in June 2002. In this report, the output of the second project year is summarized as a basic design of cold neutron source and related systems, neutron guide, and neutron scattering instruments.

  7. The second workshop of neutron science research program

    Energy Technology Data Exchange (ETDEWEB)

    Yasuda, Hideshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tone, Tatsuzo [eds.

    1997-11-01

    The Japan Atomic Energy Research Institute(JAERI) has been proposing the Neutron Science Research Program to explore a broad range of basic research and the nuclear technology including actinide transmutation with use of powerful spallation neutron sources. For this purpose, the JAERI is conducting the research and development of an intense proton linac, the development of targets, as well as the conceptual design study of experimental facilities required for applications of spallation neutrons and secondary particle beams. The Special Task Force for Neutron Science Initiative was established in May 1996 to promote aggressively and systematically the Neutron Science Research Program. The second workshop on neutron science research program was held at the JAERI Tokai Research Establishment on 13 and 14 March 1997 for the purpose of discussing the results obtained since the first workshop in March 1996. The 27 of the presented papers are indexed individually. (J.P.N.)

  8. The second workshop of neutron science research program

    Energy Technology Data Exchange (ETDEWEB)

    Yasuda, Hideshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Tone, Tatsuzo [eds.

    1997-11-01

    The Japan Atomic Energy Research Institute(JAERI) has been proposing the Neutron Science Research Program to explore a broad range of basic research and the nuclear technology including actinide transmutation with use of powerful spallation neutron sources. For this purpose, the JAERI is conducting the research and development of an intense proton linac, the development of targets, as well as the conceptual design study of experimental facilities required for applications of spallation neutrons and secondary particle beams. The Special Task Force for Neutron Science Initiative was established in May 1996 to promote aggressively and systematically the Neutron Science Research Program. The second workshop on neutron science research program was held at the JAERI Tokai Research Establishment on 13 and 14 March 1997 for the purpose of discussing the results obtained since the first workshop in March 1996. The 27 of the presented papers are indexed individually. (J.P.N.)

  9. United States Air Force Weapons Laboratory Research Scholar Program, 1983-1984.

    Science.gov (United States)

    1984-10-01

    1983 Electromagnetic Compatibility -’"Symposium, p.47-,51, 1983. P Ricketts , L.W., J.E. Bridges, J. Milletta, EMP Radiation and Protective Techniques...to the Weapons Laboratory were established. These included nuclear physics, radiation effects, electramagnetics, laser optics and related applied...research opportunity. He wishes to thank the AFWL for its sponsorship and hospitality . He wishes to thank Major Raymond L. Bell for suggesting this

  10. Development of neutron detectors and neutron radiography at Bhabha Atomic Research Centre

    Indian Academy of Sciences (India)

    A M Shaikh

    2008-10-01

    Design and development of neutron detectors and R&D work in neutron radiography (NR) for non-destructive evaluation are important parts of the neutron beam and allied research programme of Solid State Physics Division (SSPD) of Bhabha Atomic Research Centre (BARC). The detectors fabricated in the division not only meet the in-house requirement of neutron spectrometers but also the need of other divisions in BARC, Department of Atomic Energy units and some universities and research institutes in India and abroad for a variety of applications. The NR facility set up by SSPD at Apsara reactor has been used for a variety of applications in nuclear, aerospace, defense and metallurgical industries. The work done in the development of neutron detectors and neutron radiography is reported in this article.

  11. Neutron beam facilities at the Australian Replacement Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, Shane; Robinson, Robert; Hunter, Brett [Physics Division, ANSTO, Lucas Heights (Australia)

    2001-03-01

    Australia is building a research reactor to replace the HIFAR reactor at Lucas Heights by the end of 2005. Like HIFAR, the Replacement Research Reactor will be multipurpose with capabilities for both neutron beam research and radioisotope production. It will be a pool-type reactor with thermal neutron flux (unperturbed) of 4 x 10{sup 14} n/cm{sup 2}/sec and a liquid D{sub 2} cold neutron source. Cold and thermal neutron beams for neutron beam research will be provided at the reactor face and in a large neutron guide hall. Supermirror neutron guides will transport cold and thermal neutrons to the guide hall. The reactor and the associated infrastructure, with the exception of the neutron beam instruments, is to be built by INVAP S.E. under contract. The neutron beam instruments will be developed by ANSTO, in consultation with the Australian user community. This status report includes a review the planned scientific capabilities, a description of the facility and a summary of progress to date. (author)

  12. Controlled research utilizing a basic all-metal detector in the search for buried firearms and miscellaneous weapons.

    Science.gov (United States)

    Rezos, Mary M; Schultz, John J; Murdock, Ronald A; Smith, Stephen A

    2010-02-25

    Incorporating geophysical technologies into forensic investigations has become a growing practice. Oftentimes, forensic professionals rely on basic metal detectors to assist their efforts during metallic weapons searches. This has created a need for controlled research in the area of weapons searches, specifically to formulate guidelines for geophysical methods that may be appropriate for locating weapons that have been discarded or buried by criminals attempting to conceal their involvement in a crime. Controlled research allows not only for testing of geophysical equipment, but also for updating search methodologies. This research project was designed to demonstrate the utility of an all-metal detector for locating a buried metallic weapon through detecting and identifying specific types of buried metal targets. Controlled testing of 32 buried targets which represented a variety of sizes and metallic compositions included 16 decommissioned street-level firearms, 6 pieces of assorted scrap metals, and 10 blunt or bladed weapons. While all forensic targets included in the project were detected with the basic all-metal detector, the size of the weapon and surface area were the two variables that affected maximum depth of detection, particularly with the firearm sample. For example, when using a High setting the largest firearms were detected at a maximum depth of 55 cm, but the majority of the remaining targets were only detected at a maximum depth of 40 cm or less. Overall, the all-metal detector proved to be a very good general purpose metal detector best suited for detecting metallic items at shallow depths.

  13. Survey of the research on dynamic weapon-target assignment problem

    Institute of Scientific and Technical Information of China (English)

    Cai Huaiping; Liu Jingxu; Chen Yingwu; Wang Hao

    2006-01-01

    The basic concepts and models of weapon-target assignment (WTA) are introduced and the mathematical nature of the WTA models is also analyzed. A systematic survey of research on WTA problem is provided. The present research on WTA is focused on models and algorithms. In the research on models of WTA, the static WTA models are mainly studied and the dynamic WTA models are not fully studied in deed. In the research on algorithms of WTA, the intelligent algorithms are often used to solve the WTA problem. The small scale of static WTA problems has been solved very well, however, the large scale of dynamic WTA problems has not been solved effectively so far. Finally, the characteristics of dynamic WTA are analyzed and directions for the future research on dynamic WTA are discussed.

  14. Experimental research on the THGEM-based thermal neutron detector

    CERN Document Server

    Lei, Yang; Zhi-Jia, Sun; Ying, Zhang; Chao-Qiang, Huang; Guang-Ai, Sun; Yan-Feng, Wang; Gui-An, Yang; Hong, Xu; Yu-Guang, Xie; Yuan-Bo, Chen

    2014-01-01

    A new thermal neutron detector with the domestically produced THGEM (THick Gas Electron Multiplier) was developed as an alternative to 3He to meet the needs of the next generation of neutron facilities. One type of Au-coated THGEM was designed specifically for the neutron detection. A detector prototype had been developed and the preliminary experimental tests were presented, including the performance of the Au-coated THGEM working in the Ar/CO2 gas mixtures and the neutron imaging test with 252CF source, which would provide the reference of experimental data for the research in future.

  15. Recent neutron scattering research and development in India

    Indian Academy of Sciences (India)

    S L Chaplot

    2006-07-01

    A national facility for neutron beam research is operated at the research reactor Dhruva at Trombay in India. The research activities involve various nanoscale structural, dynamical and magnetic investigations on materials of scientific interest and technological importance. Thermal neutron has certain special properties that enable, e.g., selective viewing of parts of an organic molecule, hydrogen or water in materials, investigations on minerals and ceramics, and microscopic and mesoscopic characterization of bulk samples. The national facility comprises of eight neutron-scattering spectrometers in the reactor hall, and another four spectrometers in the neutron-guide laboratory. In addition, a neutron radiography facility and a detector development laboratory are located at APSARA reactor. All the instruments including the detectors and electronics have been developed within BARC. A new powder diffractometer (PD-3) is being developed by UGC-DAE-CSR. The national facility is utilized in collaboration with various universities and other institutions.

  16. Research of Fast Neutron Radiation Effect on Rats

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    In order to research the fast neutron radiation effect on rats,the 8 weeks Wistar male rats were wholly irradiated by 14 MeV fast neutron with 5 Gy. In the experiment,the rats were divided into normal and irradiation group, and killed

  17. Cold Neutron Research Facility begins operating at NIST

    Energy Technology Data Exchange (ETDEWEB)

    Zeman, E.J.

    1991-09-01

    Steady-state neutron beams are generally produced by fission in a nuclear reactor, whereas pulsed beams come from spallation neutron sources. Beams from a reactor have a distribution of wavelengths that is roughly Maxwellian, with a peak wavelength that depends on the temperature of the moderator that surrounds the fuel. Cold neutrons can be selected from the low-energy tail of the distribution, but the flux drops as 1/{lambda}{sup 4}. However, by shifting the whole spectrum to longer wavelengths one can dramatically increase the cold neutron flux. This is achieved by replacing part of the core moderator with a cold moderator, or cold source,' such as liquid deuterium (at about 30 K) or D{sub 2}O ice (at about 40 K). Neutrons lose energy to the moderator through collisions, producing a shifted spectrum from which one can select lower-energy neutrons with a roughly ten-fold improvement in the flux. Neutrons exhibit optical behavior such as refraction and total reflection. Thus one can use neutron guides - analogous to optical fibers - to conduct intense beams of neutrons from the reactor into a large experimental hall, dubbed a guide hall,' where background radiation is low. The Cold Neutron Research Facility was finally funded in 1987 and opened its doors this past June. CNRF is located at the 20-MW NIST research reactor, which began continuous operation in 1969. With some foresight, the designers of the original reactor allowed space for the addition of a cryogenic moderator, which is only now being exploited. NIST will develop 10 experimental stations for use by the research science community. Additional help in financing the facility comes from participating research teams made up of groups from industry, academe and government.

  18. Application of Neutron Tomography in Culture Heritage research.

    Science.gov (United States)

    Mongy, T

    2014-02-01

    Neutron Tomography (NT) investigation of Culture Heritages (CH) is an efficient tool for understanding the culture of ancient civilizations. Neutron imaging (NI) is a-state-of-the-art non-destructive tool in the area of CH and plays an important role in the modern archeology. The NI technology can be widely utilized in the field of elemental analysis. At Egypt Second Research Reactor (ETRR-2), a collimated Neutron Radiography (NR) beam is employed for neutron imaging purposes. A digital CCD camera is utilized for recording the beam attenuation in the sample. This helps for the detection of hidden objects and characterization of material properties. Research activity can be extended to use computer software for quantitative neutron measurement. Development of image processing algorithms can be used to obtain high quality images. In this work, full description of ETRR-2 was introduced with up to date neutron imaging system as well. Tomographic investigation of a clay forged artifact represents CH object was studied by neutron imaging methods in order to obtain some hidden information and highlight some attractive quantitative measurements. Computer software was used for imaging processing and enhancement. Also the Astra Image 3.0 Pro software was employed for high precise measurements and imaging enhancement using advanced algorithms. This work increased the effective utilization of the ETRR-2 Neutron Radiography/Tomography (NR/T) technique in Culture Heritages activities.

  19. Kartini Research Reactor prospective studies for neutron scattering application

    Energy Technology Data Exchange (ETDEWEB)

    Widarto [Yogyakarta Nuclear Research Center, BATAN (Indonesia)

    1999-10-01

    The Kartini Research Reactor (KRR) is located in Yogyakarta Nuclear Research Center, Yogyakarta - Indonesia. The reactor is operated for 100 kW thermal power used for research, experiments and training of nuclear technology. There are 4 beam ports and 1 column thermal are available at the reactor. Those beam ports have thermal neutron flux around 10{sup 7} n/cm{sup 2}s each other and used for sub critical assembly, neutron radiography studies and Neutron Activation Analysis (NAA). Design of neutron collimator has been done for piercing radial beam port and the calculation result of collimated neutron flux is around 10{sup 9} n/cm{sup 2}s. This paper describes experiment facilities and parameters of the Kartini research reactor, and further more the prospective studies for neutron scattering application. The purpose of this paper is to optimize in utilization of the beam ports facilities and enhance the manpower specialty. The special characteristic of the beam ports and preliminary studies, pre activities regarding with neutron scattering studies for KKR is presented. (author)

  20. Application Research of Developed Drummed Nuclear Waste Neutron Counting System

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The application researches such as variety of factors affecting the measurement, calibrating etc. are need before the drummed nuclear waste neutron counting system (WNC) can be really put into use after installed at the site.

  1. Application of inertial confinement fusion to weapon technology

    Energy Technology Data Exchange (ETDEWEB)

    Toepfer, A.J.; Posey, L.D.

    1978-12-01

    This report reviews aspects of the military applications of the inertial confinement fusion (ICF) program at Sandia Laboratories. These applications exist in the areas of: (1) weapon physics research, and (2) weapon effects simulation. In the area of weapon physics research, ICF source technology can be used to study: (1) equations-of-state at high energy densities, (2) implosion dynamics, and (3) laboratory simulation of exoatmospheric burst phenomena. In the area of weapon effects simulation, ICF technology and facilities have direct near, intermediate, and far term applications. In the near term, short pulse x-ray simulation capabilities exist for electronic component effects testing. In the intermediate term, capabilities can be developed for high energy neutron exposures and bremsstrahlung x-ray exposures of components. In the far term, system level exposures of full reentry vehicles will be possible if sufficiently high pellet gains are achieved.

  2. The NIST NBSR and Cold Neutron Research Facility

    Energy Technology Data Exchange (ETDEWEB)

    Rush, J.J. [National Inst. of Standards and Technology, Guthersburg, MD (United States)

    1994-12-31

    The 20 MW Neutron Beam Split-Core Reactor (NBSR) has nine radial thermal beam tubes, and a large, highly accessible (35cm) cold source serving an extensive network of eight guide tubes. In operation or under construction are twenty-five neutron beam instruments (20 for neutron scattering) and about a dozen other facilities for neutron trace analysis, dosimetry and irradiation. The 6 x 15cm cold neutron guides are coated with {sup 58}Ni, and the last three being installed this fall are coated top and bottom with supermirrors for further increases in intensity. The new semi-spherical liquid hydrogen source will be described, along with the eight scattering instruments (reflectometry, SANS and high-resolution spectroscopy) which have, or will have, an extensive use in biological research. These instruments will likely provide the best overall capability in the U.S. for the next decade for a number of applications in biomolecular structure and dynamics.

  3. The neutron texture diffractometer at the China Advanced Research Reactor

    Science.gov (United States)

    Li, Mei-Juan; Liu, Xiao-Long; Liu, Yun-Tao; Tian, Geng-Fang; Gao, Jian-Bo; Yu, Zhou-Xiang; Li, Yu-Qing; Wu, Li-Qi; Yang, Lin-Feng; Sun, Kai; Wang, Hong-Li; Santisteban, J. r.; Chen, Dong-Feng

    2016-03-01

    The first neutron texture diffractometer in China has been built at the China Advanced Research Reactor, due to strong demand for texture measurement with neutrons from the domestic user community. This neutron texture diffractometer has high neutron intensity, moderate resolution and is mainly applied to study texture in commonly used industrial materials and engineering components. In this paper, the design and characteristics of this instrument are described. The results for calibration with neutrons and quantitative texture analysis of zirconium alloy plate are presented. The comparison of texture measurements with the results obtained in HIPPO at LANSCE and Kowari at ANSTO illustrates the reliability of the texture diffractometer. Supported by National Nature Science Foundation of China (11105231, 11205248, 51327902) and International Atomic Energy Agency-TC program (CPR0012)

  4. European neutron research prepares for future challenges

    CERN Multimedia

    Antonella Del Rosso

    2013-01-01

    Neutrons are among the fundamental building blocks of matter. Some of the processes in which they are involved are responsible for energy generation in nuclear power plants. In this context, CERN’s n_TOF and other facilities participating in the ERINDA EU-funded programme help the community integrate all the scientific efforts needed to produce high-quality nuclear data for future nuclear technologies.   The 4π calorimeter inside the n_TOF experimental area. Image courtesy of the n_TOF Collaboration. Accurate measurements of the interactions between neutrons and each of the elements present in nuclear reactors are vital tools enabling scientists to explore solutions – other than simple protected storage – for the treatment of radioactive waste deriving from a number of applications, ranging from energy production to the medical field. Particularly valuable is the contribution provided by the 13 accelerator-based neutron sources, which the ERINDA EU-funded...

  5. Research on Computer Aided Innovation Model of Weapon Equipment Requirement Demonstration

    Science.gov (United States)

    Li, Yong; Guo, Qisheng; Wang, Rui; Li, Liang

    Firstly, in order to overcome the shortcoming of using only AD or TRIZ solely, and solve the problems currently existed in weapon equipment requirement demonstration, the paper construct the method system of weapon equipment requirement demonstration combining QFD, AD, TRIZ, FA. Then, we construct a CAI model frame of weapon equipment requirement demonstration, which include requirement decomposed model, requirement mapping model and requirement plan optimization model. Finally, we construct the computer aided innovation model of weapon equipment requirement demonstration, and developed CAI software of equipment requirement demonstration.

  6. Low Prevalence of Chronic Beryllium Disease among Workers at a Nuclear Weapons Research and Development Facility

    Energy Technology Data Exchange (ETDEWEB)

    Arjomandi, M; Seward, J P; Gotway, M B; Nishimura, S; Fulton, G P; Thundiyil, J; King, T E; Harber, P; Balmes, J R

    2010-01-11

    To study the prevalence of beryllium sensitization (BeS) and chronic beryllium disease (CBD) in a cohort of workers from a nuclear weapons research and development facility. We evaluated 50 workers with BeS with medical and occupational histories, physical examination, chest imaging with HRCT (N=49), and pulmonary function testing. Forty of these workers also underwent bronchoscopy for bronchoalveolar lavage (BAL) and transbronchial biopsies. The mean duration of employment at the facility was 18 yrs and the mean latency (from first possible exposure) to time of evaluation was 32 yrs. Five of the workers had CBD at the time of evaluation (based on histology or HRCT); three others had evidence of probable CBD. These workers with BeS, characterized by a long duration of potential Be exposure and a long latency, had a low prevalence of CBD.

  7. Neutron flux optimization in irradiation channels at NUR research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Meftah, B. [Division Reacteur, Centre de Recherche Nucleaire Draria (CRND), BP 43 Sebala DRARIA, Alger (Algeria)]. E-mail: b_meftah@yahoo.com; Zidi, T. [Division Reacteur, Centre de Recherche Nucleaire Draria (CRND), BP 43 Sebala DRARIA, Alger (Algeria); Bousbia-Salah, A. [Dipartimento di Ingegneria Meccanica, Nucleari e della Produzione, Facolta di Ingegneria, Universita di Pisa, Via Diotisalvi, 2 - 56126 Pisa (Italy)

    2006-09-15

    Optimization of neutron fluxes in experimental channels is of great concern in research reactor utilization. The general approach used at the NUR research reactor for neutron flux optimization in irradiation channels is presented. The approach is essentially based upon a judicious optimization of the core configuration combined with the improvement of reflector characteristics. The method allowed to increase the thermal neutron flux for radioisotope production purposes by more than 800%. Increases of up to 60% are also observed in levels of useful fluxes available for neutron diffraction experiments (small angle neutron scattering (SANS), neutron reflectometry, etc.). Such improvements in the neutronic characteristics of the NUR reactor opened new perspectives in terms of its utilization. More particularly, it is now possible to produce at industrial scales major radio-isotopes for medicine and industry and to perform, for the first time, material testing experiments. The cost of the irradiations in the optimized configuration is generally small when compared to those performed in the old configuration and an average reduction factor of about of 10 is expected in the case of production of Molybdenum-99 (isotope required for the manufacturing of Technetium-99 medical kits). In addition to these important results, safety analysis studies showed that the more symmetrical nature of the core geometry leads to a more adequately balanced reactivity control system and contributes quite efficiently to the operational safety of the NUR reactor. Results of comparisons between calculations and measurements for a series of parameters of importance in reactor operation and safety showed good agreement.

  8. Neutron Scattering Collimation Wheel Instrument for Imaging Research

    Science.gov (United States)

    Van Every, E.; Deyhim, A.

    2016-09-01

    The design of a state-of-the-art selector wheel instrument to support the area of neutron imaging research (neutron radiography/ tomography) is discussed. The selector wheel is installed on the DINGO Radiography instrument at the Bragg Institute HB2 beamline at ANSTO in Sidney Aus. The selector wheel consists of a single axis drum filled with a wax/steel shielding mixture and six square cutouts for neutron optics and a larger solid shielding sector to act as a shutter. This paper focuses on the details of design and shielding of the selector wheel.

  9. Computational characterization and experimental validation of the thermal neutron source for neutron capture therapy research at the University of Missouri

    Energy Technology Data Exchange (ETDEWEB)

    Broekman, J. D. [University of Missouri, Research Reactor Center, 1513 Research Park Drive, Columbia, MO 65211-3400 (United States); Nigg, D. W. [Idaho National Laboratory, PO Box 1625, Idaho Falls, ID 83415 (United States); Hawthorne, M. F. [University of Missouri, International Institute of Nano and Molecular Medicine, 1514 Research Park Dr., Columbia, MO 65211-3450 (United States)

    2013-07-01

    Parameter studies, design calculations and neutronic performance measurements have been completed for a new thermal neutron beamline constructed for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The computational models used for the final beam design and performance evaluation are based on coupled discrete-ordinates and Monte Carlo techniques that permit detailed modeling of the neutron transmission properties of the filtering crystals with very few approximations. Validation protocols based on neutron activation spectrometry measurements and rigorous least-square adjustment techniques show that the beam produces a neutron spectrum that has the anticipated level of thermal neutron flux and a somewhat higher than expected, but radio-biologically insignificant, epithermal neutron flux component. (authors)

  10. Neutron fluence depth profiles in water phantom on epithermal beam of LVR-15 research reactor.

    Science.gov (United States)

    Viererbl, L; Klupak, V; Lahodova, Z; Marek, M; Burian, J

    2010-01-01

    Horizontal channel with epithermal neutron beam at the LVR-15 research reactor is used mainly for boron neutron capture therapy. Neutron fluence depth profiles in a water phantom characterise beam properties. The neutron fluence (approximated by reaction rates) depth profiles were measured with six different types of activation detectors. The profiles were determined for thermal, epithermal and fast neutrons.

  11. Neutron scattering at Australia's replacement research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kennedy, S.J.; Robinson, R.A.; Hunter, B.A. [Physics Division, ANSTO, Lucas Heights, NSW (Australia)

    2001-03-01

    On August 25{sup th} 1999, the Australian government gave final approval to build a research reactor to replace the existing HIFAR reactor at Lucas Heights. The replacement reactor, which will commence operation in 2005, will be multipurpose with capabilities for both neutron beam research and radioisotope production. Cold, and thermal neutron sources are to be installed and supermirror guides will transport cold and thermal neutron beams into a large modern guide hall. The reactor and associated infrastructure is to be built by INVAP, SE and subcontractors under contract. The neutron beam instruments will be developed by ANSTO in consultation with the Australian user community and interested overseas parties. We review the planned scientific capabilities, give a description of the facility and a status report on the activities so far. (author)

  12. A neutron tomography facility at a low power research reactor

    CERN Document Server

    Körner, S; Von Tobel, P; Rauch, H

    2001-01-01

    Neutron radiography (NR) provides a very efficient tool in the field of non-destructive testing as well as for many applications in fundamental research. A neutron beam penetrating a specimen is attenuated by the sample material and detected by a two-dimensional (2D) imaging device. The image contains information about materials and structure inside the sample because neutrons are attenuated according to the basic law of radiation attenuation. Contrary to X-rays, neutrons can be attenuated by some light materials, as for example, hydrogen and boron, but penetrate many heavy materials. Therefore, NR can yield important information not obtainable by more traditional methods. Nevertheless, there are many aspects of structure, both quantitative and qualitative, that are not accessible from 2D transmission images. Hence, there is an interest in three-dimensional neutron imaging. At the 250 kW TRIGA Mark II reactor of the Atominstitut in Austria a neutron tomography facility has been installed. The neutron flux at ...

  13. Measurement of in-phantom neutron flux and gamma dose in Tehran research reactor boron neutron capture therapy beam line

    OpenAIRE

    Elham Bavarnegin; Alireza Sadremomtaz; Hossein Khalafi; Yaser Kasesaz

    2016-01-01

    Aim: Determination of in-phantom quality factors of Tehran research reactor (TRR) boron neutron capture therapy (BNCT) beam. Materials and Methods: The doses from thermal neutron reactions with 14N and 10B are calculated by kinetic energy released per unit mass approach, after measuring thermal neutron flux using neutron activation technique. Gamma dose is measured using TLD-700 dosimeter. Results: Different dose components have been measured in a head phantom which has been designed an...

  14. Research needs for neutron capture therapy

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-12-01

    Key issues and questions addressed by the workshop related to optimization of Boron Neutron Capture Therapy (BNCT), in general, and to the possibility of success of the present BNCT trials at Brookhaven National Laboratory (BNL) and Massachusetts Institute of Technology (MIT), in particular. Both trials use nuclear fission reactors as neutron sources for BNCT of glioblastoma multiforme (BNL) and of deep seated melanoma (MIT). Presentations and discussions focussed on optimal boron-labeled compounds, mainly for brain tumors such as glioblastoma multiforme, and the best mode of compound delivery to the tumor. Also, optimizing neutron irradiation with dose delivery to the tumor cells and the issues of dosimetry of BNCT especially in the brain were discussed. Planning of treatment and of follow-up of patients, coordination of BNCT at various treatment sites, and the potential of delivering BNCT to various types of cancer with an appropriately tailored protocol were additional issues. The need for multicentric interdisciplinary cooperation among the different medical specialties was highlighted.

  15. Research opportunities with compact accelerator-driven neutron sources

    Science.gov (United States)

    Anderson, I. S.; Andreani, C.; Carpenter, J. M.; Festa, G.; Gorini, G.; Loong, C.-K.; Senesi, R.

    2016-10-01

    Since the discovery of the neutron in 1932 neutron beams have been used in a very broad range of applications, As an aging fleet of nuclear reactor sources is retired the use of compact accelerator-driven neutron sources (CANS) is becoming more prevalent. CANS are playing a significant and expanding role in research and development in science and engineering, as well as in education and training. In the realm of multidisciplinary applications, CANS offer opportunities over a wide range of technical utilization, from interrogation of civil structures to medical therapy to cultural heritage study. This paper aims to provide the first comprehensive overview of the history, current status of operation, and ongoing development of CANS worldwide. The basic physics and engineering regarding neutron production by accelerators, target-moderator systems, and beam line instrumentation are introduced, followed by an extensive discussion of various evolving applications currently exploited at CANS.

  16. Epithermal neutron beam for BNCT research at the Washington State University TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nigg, D.W.; Venhuizen, J.R.; Wheeler, F.J.; Wemple, C.A. [Idaho National Engineering and Environmental Laboratory, Idaho Falls, ID (United States); Tripard, G.E.; Gavin, P.R. [Washington State University, Pullman, WA (United States)

    2000-10-01

    A new epithermal-neutron beam facility for BNCT (Boron Neutron Capture Therapy) research and boronated agent screening in animal models is in the final stages of construction at Washington State University (WSU). A key distinguishing feature of the design is the incorporation of a new, high-efficiency, neutron moderating and filtering material, Fluental, developed by the Technical Research Centre of Finland. An additional key feature is the provision for adjustable filter-moderator thickness to systematically explore the radiobiological consequences of increasing the fast-neutron contamination above the nominal value associated with the baseline system. (author)

  17. 对抗高超声速武器的机载激光武器发展研究%Research on the Development of Airborne Laser Weapons Against Hypersonic Weapons

    Institute of Scientific and Technical Information of China (English)

    张同鑫; 李权

    2016-01-01

    The military threat of hypersonic weapon to current air defense system, and the potential military value of airborne laser weapon confronted to the hypersonic weapon were illustrated. Detailed introduction was made on the technical barriers of airborne laser weapon and the state of the art research progress. It is emphasized that now to research airborne laser weapon, its weight and size must be decreased, beam control system and aiming and tracking system in dynamic environments must be researched, special aerodynamic layout must be designed and smart energy sources management must be established.%介绍了高超声速武器对现有军事防御系统的威胁,机载激光武器对抗高超声速武器的军事价值。详细描述了国外机载激光武器的研究进展以及研究机载激光武器的技术难点,指出当前研究机载激光武器必须进一步降低激光武器的重量和体积,研发动态环境的光束控制与瞄准跟踪系统,开展特殊气动布局设计研究,建立周密的能源管理系统。

  18. Spectromicroscopy in Boron Neutron Capture Therapy Research

    Science.gov (United States)

    Gilbert, Benjamin; Redondo, Jose; Andres, Roger; Suda, Takashi; Neumann, Michael; Steen, Steffi; Gabel, Detlef; Mercanti, Delio; Ciotti, Teresa; Perfetti, Paolo; Margaritondo, Giorgio; de Stasio, Gelsomina

    1998-03-01

    The MEPHISTO synchrotron imaging spectromicroscope can analyse ashed cells or tissue sections to reveal the microdistribution of trace elements. MEPHISTO performs core level x-ray absorption spectroscopy with synchrotron radiation, and uses an electron optics system to provide magnified photoelectron images. An application of the MEPHISTO spectromicroscope is in boron neutron capture therapy (BNCT). BNCT is a binary cancer therapy that will selectively destroy cancer cells provided that compounds containing a boron isotope are selectively accumulated in tumor tissue. Important factors for the success of BNCT include the ability to target every cancer cell, and the distribution of boron inside the cell. To investigate the boron distribution in tissue, sections of human glioblastoma containing a BNCT compound, and stained with nickel against a protein found in the nuclei of proliferating (cancer) cells, were studied with MEPHISTO.

  19. Activity report on neutron scattering research

    Energy Technology Data Exchange (ETDEWEB)

    Nagao, M.; Tawata, N.; Fujii, Y. [eds.] [Tokyo Univ. (Japan). Inst. for Solid State Physics

    1998-12-31

    The experiments performed on the thirteen university-owned spectrometers installed at JRR-3M of JAERI in the fiscal year of 1997 were described in this report. The latest ``Neutron News`` (vol. 9, issue 3, 1998) has featured highlights of the activities based on the JRR-3M and its cover displays a graph showing an endless increase of the number of proposals to the users program in the fiscal 1997. The university-owned spectrometers are available for general users all over Japan. The users` requirement for a higher flux beam reactor became larger and larger with time. Thus, JAERI has refurbished JRR-3 to satisfy these demands. In 1997, a joint project between Chiba University and Institute for Solid State Physics (ISSP) started to build a new 4-cycle diffractometer for crystal physics/chemistry at T{sub 2-2} beam port on a thermal guide. (M.N.)

  20. A research plan based on high intensity proton accelerator Neutron Science Research Center

    Energy Technology Data Exchange (ETDEWEB)

    Mizumoto, Motoharu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    A plan called Neutron Science Research Center (NSRC) has been proposed in JAERI. The center is a complex composed of research facilities based on a proton linac with an energy of 1.5GeV and an average current of 10mA. The research facilities will consist of Thermal/Cold Neutron Facility, Neutron Irradiation Facility, Neutron Physics Facility, OMEGA/Nuclear Energy Facility, Spallation RI Beam Facility, Meson/Muon Facility and Medium Energy Experiment Facility, where high intensity proton beam and secondary particle beams such as neutron, pion, muon and unstable radio isotope (RI) beams generated from the proton beam will be utilized for innovative researches in the fields on nuclear engineering and basic sciences. (author)

  1. Current status of neutron activation analysis in HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Sohn, Jae Min [Korea Atomic Energy Research Institute, Daejeon (Korea)

    2003-03-01

    The facilities for neutron activation analysis in the HANARO (Hi-flux Advanced Neutron Application Research Reactor) are described and the main applications of NAA (Neutron Activation Analysis) are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system were installed at three irradiation holes of HANARO at the end of 1995. The performance of the NAA facility was examined to identify the characteristics of the tube transfer system, irradiation sites and custom-made polyethylene irradiation capsule. The available thermal neutron fluxes at irradiation sites are in the range of 3 x 10{sup 13} - 1 x 10{sup 14} n/cm{sup 2}{center_dot}s and cadmium ratios are in 15 - 250. For an automatic sample changer for gamma-ray counting, a domestic product was designed and manufactured. An integrated computer program (Labview) to analyse the content was developed. In 2001, PGNAA (Prompt Gamma Neutron Activation Analysis) facility has been installed using a diffracted neutron beam of ST1. NAA has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials, and various polymers for research and development. The improvement of analytical procedures and establishment of an analytical quality control and assurance system were studied. Applied research and development for the environment, industry and human health by NAA and its standardization were carried out. For the application of the KOLAS (Korea Laboratory Accreditation Scheme), evaluation of measurement uncertainty and proficiency testing of reference materials were performed. Also to verify the reliability and to validate analytical results, intercomparison studies between laboratories were carried out. (author)

  2. Simulations of neutron multiplicity measurements of a weapons-grade plutonium sphere with MCNP-PoliMi.

    Energy Technology Data Exchange (ETDEWEB)

    Mattingly, John K.; Pozzi, Sara A. (University of Michigan, Ann Arbor, MI); Clarke, Shaun D. (University of Michigan, Ann Arbor, MI); Dennis, Ben D. (University of Michigan, Ann Arbor, MI); Miller, Eric C. (University of Michigan, Ann Arbor, MI); Padovani, E. (Polytechnic of Milan, Italy)

    2010-06-01

    With increasing concern over the ability to detect and characterize special nuclear materials, the need for computer codes that can successfully predict the response of detector systems to various measurement scenarios is extremely important. These computer algorithms need to be benchmarked against a variety of experimental configurations to ensure their accuracy and understand their limitations. The Monte Carlo code MCNP-PoliMi is a modified version of the MCNP-4c code. Recently these modifications have been ported into the new MCNPX 2.6.0 code, which gives the new MCNPX-PoliMi a wider variety of options and abilities, taking advantage of the improvements made to MCNPX. To verify the ability of the MCNPX-PoliMi code to simulate the response of a neutron multiplicity detector simulated results were compared to experimental data. The experiment consisted of a 4.5-kg sphere of alpha-phase plutonium that was moderated with various thicknesses of polyethylene. The results showed that our code system can simulate the multiplicity distributions with relatively good agreement with measured data. The enhancements made to MCNP since the release of MCNP-4c have had little to no effect on the ability of the MCNP-PoliMi to resolve the discrepancies observed in the simulated neutron multiplicity distributions when compared experimental data.

  3. Applied research of environmental monitoring using instrumental neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Young Sam; Moon, Jong Hwa; Chung, Young Ju

    1997-08-01

    This technical report is written as a guide book for applied research of environmental monitoring using Instrumental Neutron Activation Analysis. The contents are as followings; sampling and sample preparation as a airborne particulate matter, analytical methodologies, data evaluation and interpretation, basic statistical methods of data analysis applied in environmental pollution studies. (author). 23 refs., 7 tabs., 9 figs.

  4. Upgrading of neutron radiography/tomography facility at research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Abd El Bar, Waleed; Mongy, Tarek [Atomic Energy Authority, Cairo (Egypt). ETRR-2; Kardjilov, Nikolay [Helmholtz Zentrum Berlin (HZB) for Materials and Energy, Berlin (Germany)

    2014-03-15

    A state-of-the-art neutron tomography imaging system was set up at the neutron radiography beam tube at the Egypt Second Research Reactor (ETRR-2) and was successfully commissioned in 2013. This study presents a set of tomographic experiments that demonstrate a high quality tomographic image formation. A computer technique for data processing and 3D image reconstruction was used to see inside a copy module of an ancient clay article provided by the International Atomic Energy Agency (IAEA). The technique was also able to uncover tomographic imaging details of a mummified fish and provided a high resolution tomographic image of a defective fire valve. (orig.)

  5. Special Weapons

    Data.gov (United States)

    Federal Laboratory Consortium — Supporting Navy special weapons, the division provides an array of engineering services, technical publication support services, logistics support services, safety...

  6. The review of the application of neutron radiography to thermal hydraulic research

    CERN Document Server

    Mishima, K; Saitô, Y; Nakamura, H; Matsubayashi, M

    1999-01-01

    This paper is concerned with the establishment of thermal neutron radiography as a high accuracy measurement method. This paper reviews the present status on the development of high-frame-rate neutron radiography with a steady thermal neutron beam and its application to multiphase flow research performed at the Research Reactor Institute of Kyoto University in collaboration with the Japan Atomic Energy Research Institute.

  7. Research and Analytical Evaluation of the Soviet Union and Modernization of Nuclear Weapons Forces in Europe.

    Science.gov (United States)

    1982-04-01

    Ministry "expert," Major General Anatoly Kuntsevich , and other Soviet officials held a press conference in Moscow on chemical weapons in which he stated...among other thinqs, that "the United Stated model of war is to fight on another’s territory and spill others’ blood." In reply to a question, Kuntsevich

  8. The Swedish National Defence Research Establishment and the plans for Swedish nuclear weapons; Foersvarets forskningsanstalt och planerna paa svenska kaernvapen

    Energy Technology Data Exchange (ETDEWEB)

    Jonter, Thomas [Uppsala Univ. (Sweden). Dept. of History

    2001-03-01

    This study analyses the Swedish nuclear weapons research since 1945 carried out by the Swedish National Defence Research Establishment (FOA). The most important aspect of this research was dealing with protection in broad terms against nuclear weapons attacks. However, another aspect was also important from early on - to conduct research aiming at a possible production of nuclear weapons. FOA performed an extended research up to 1968, when the Swedish Government signed the Non-Proliferation Treaty (NPT), which meant the end of these production plans. Up to this date, five main investigations about the technical conditions were made, 1948, 1953, 1955, 1957 and 1965, which all together expanded the Swedish know-how to produce a bomb. The Swedish plans to procure nuclear weapons were not an issue in the debate until the mid 50's. The reason for this was simple, prior to 1954 the plans were secretly held within a small group of involved politicians, military and researchers. The change of this procedure did take place when the Swedish Supreme Commander in a public defence report in 1954 favoured a Swedish Nuclear weapons option. In 1958 FOA had reached a technical level that allowed the Parliament to make a decision. Two programs were proposed - the L-programme (the Loading Programme), to be used if the parliament would say yes to a production of nuclear weapons, and the S-programme (the Protection Programme), if the Parliament would say no. The debate on the issue had now created problems for the Social Democratic Government. The Prime Minister, Tage Erlander, who had earlier defended a procurement of nuclear weapons, was now forced to reach a compromise. The compromise was presented to the parliament in a creative manner that meant that only the S-programme would be allowed. The Government argued that the technical level did allow a 'freedom of action' up to at least the beginning of the 60's when Sweden was mature to make a decision on the issue

  9. [Biological weapons].

    Science.gov (United States)

    Kerwat, K; Becker, S; Wulf, H; Densow, D

    2010-08-01

    Biological weapons are weapons of mass destruction that use pathogens (bacteria, viruses) or the toxins produced by them to target living organisms or to contaminate non-living substances. In the past, biological warfare has been repeatedly used. Anthrax, plague and smallpox are regarded as the most dangerous biological weapons by various institutions. Nowadays it seems quite unlikely that biological warfare will be employed in any military campaigns. However, the possibility remains that biological weapons may be used in acts of bioterrorism. In addition all diseases caused by biological weapons may also occur naturally or as a result of a laboratory accident. Risk assessment with regard to biological danger often proves to be difficult. In this context, an early identification of a potentially dangerous situation through experts is essential to limit the degree of damage. Georg Thieme Verlag KG Stuttgart * New York.

  10. Hafnium as a neutron absorber in research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Jatuff, F.E.; Villarino, E.A. [INVAP S.E., S.C. de Bariloche (Argentina)

    1995-12-31

    Research reactors usually require the periodic replacement of control rods because of the burnup of the neutron absorber material, even if devices have been mainly withdrawn. The purpose of this paper is the study of the reactivity worth of hafnium as a neutron absorber in the multi-purpose-type research reactor (MPTRR). The MPTRR design develops 20 MW, and it is configured by five rows of six low-enriched uranium (200% enrichment) materials test reactor fuels inside a Zircaloy chimney. The standard control plates are given by two rows of three plates of silver-indium-cadmium alloy (85% silver, 10% indium, and 5% cadmium, in weight percents; 0.26 cm of maximum absorber width), separating the central three rows of fuel elements from the peripheral first and fifth rows. The burnup of control plates decreases the reactivity worth below the licensing criteria in {approximately}6 months.

  11. Design, construction and characterization of a new neutron beam for neutron radiography at the Tehran Research Reactor

    Science.gov (United States)

    Choopan Dastjerdi, M. H.; Khalafi, H.; Kasesaz, Y.; Mirvakili, S. M.; Emami, J.; Ghods, H.; Ezzati, A.

    2016-05-01

    To obtain a thermal neutron beam for neutron radiography applications, a neutron collimator has been designed and implemented at the Tehran Research Reactor (TRR). TRR is a 5 MW open pool light water moderated reactor with seven beam tubes. The neutron collimator is implemented in the E beam tube of the TRR. The design of the neutron collimator was performed using MCNPX Monte Carlo code. In this work, polycrystalline bismuth and graphite have been used as a gamma filter and an illuminator, respectively. The L/D parameter of the facility was chosen in the range of 150-250. The thermal neutron flux at the image plane can be varied from 2.26×106 to 6.5×106 n cm-2 s-1. Characterization of the beam was performed by ASTM standard IQI and foil activation technique to determine the quality of neutron beam. The results show that the obtained neutron beam has a good quality for neutron radiography applications.

  12. Neurotoxic Weapons and Syndromes.

    Science.gov (United States)

    Carota, Antonio; Calabrese, Pasquale; Bogousslavsky, Julien

    2016-01-01

    The modern era of chemical and biological warfare began in World War I with the large-scale production and use of blistering and choking agents (chlorine, phosgene and mustard gases) in the battlefield. International treaties (the 1925 Geneva Protocol, the 1975 Biological and Toxin Weapons Convention and the 1993 Chemical Weapons Convention) banned biological and chemical weapons. However, several countries are probably still engaged in their development. Hence, there is risk of these weapons being used in the future. This chapter will focus on neurotoxic weapons (e.g. nerve agents, chemical and biological neurotoxins, psychostimulants), which act specifically or preeminently on the central nervous system and/or the neuromuscular junction. Deeply affecting the function of the nervous system, these agents either have incapacitating effects or cause clusters of casualties who manifest primary symptoms of encephalopathy, seizures, muscle paralysis and respiratory failure. The neurologist should be prepared both to notice patterns of symptoms and signs that are sufficiently consistent to raise the alarm of neurotoxic attacks and to define specific therapeutic interventions. Additionally, extensive knowledge on neurotoxic syndromes should stimulate scientific research to produce more effective antidotes and antibodies (which are still lacking for most neurotoxic weapons) for rapid administration in aerosolized forms in the case of terrorist or warfare scenarios. © 2016 S. Karger AG, Basel.

  13. Multipurpose epithermal neutron beam on new research station at MARIA research reactor in Swierk-Poland

    Energy Technology Data Exchange (ETDEWEB)

    Gryzinski, M.A.; Maciak, M. [National Centre for Nuclear Research, Andrzeja Soltana 7, 05-400 Otwock-Swierk (Poland)

    2015-07-01

    MARIA reactor is an open-pool research reactor what gives the chance to install uranium fission converter on the periphery of the core. It could be installed far enough not to induce reactivity of the core but close enough to produce high flux of fast neutrons. Special design of the converter is now under construction. It is planned to set the research stand based on such uranium converter in the near future: in 2015 MARIA reactor infrastructure should be ready (preparation started in 2013), in 2016 the neutron beam starts and in 2017 opening the stand for material and biological research or for medical training concerning BNCT. Unused for many years, horizontal channel number H2 at MARIA research rector in Poland, is going to be prepared as a part of unique stand. The characteristics of the neutron beam will be significant advantage of the facility. High flux of neutrons at the level of 2x10{sup 9} cm{sup -2}s{sup -1} will be obtainable by uranium neutron converter located 90 cm far from the reactor core fuel elements (still inside reactor core basket between so called core reflectors). Due to reaction of core neutrons with converter U{sub 3}Si{sub 2} material it will produce high flux of fast neutrons. After conversion neutrons will be collimated and moderated in the channel by special set of filters and moderators. At the end of H2 channel i.e. at the entrance to the research room neutron energy will be in the epithermal energy range with neutron intensity at least at the level required for BNCT (2x10{sup 9} cm{sup -2}s{sup -1}). For other purposes density of the neutron flux could be smaller. The possibility to change type and amount of installed filters/moderators which enables getting different properties of the beam (neutron energy spectrum, neutron-gamma ratio and beam profile and shape) is taken into account. H2 channel is located in separate room which is adjacent to two other empty rooms under the preparation for research laboratories (200 m2). It is

  14. Chemistry and Materials Science Weapons-Supporting Research and Laboratory-Directed Research and Development. Second half progress report, FY 1993

    Energy Technology Data Exchange (ETDEWEB)

    1994-02-01

    Thrust areas of the weapons-supporting research are surface research, uranium research, physics and processing of metals, energetic materials. Group study areas included strength of Al and Al-Mg/alumina bonds, advanced synchrotron radiation study of materials, and theory, modeling, and computation. Individual projects were life prediction for composites and thermoelectric materials with exceptional figures of merit. The laboratory-directed R and D include director`s initiatives (aerogel-based electronic devices, molecular levels of energetic materials), individual projects, and transactinium institute studies. An author index is provided.

  15. Applied research and development of neutron activation analysis

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Bak, Sung Ryel; Park, Yong Chul; Kim, Young Ki; Chung, Hwan Sung; Park, Kwang Won; Kang, Sang Hun

    2000-05-01

    This report is written for results of research and development as follows : improvement of neutron irradiation facilities, counting system and development of automation system and capsules for NAA in HANARO ; improvement of analytical procedures and establishment of analytical quality control and assurance system; applied research and development of environment, industry and human health and its standardization. For identification and standardization of analytical method, environmental biological samples and polymer are analyzed and uncertainity of measurement are estimated. Also data intercomparison and proficency test were performed. Using airborne particulate matter chosen as a environmental indicators, trace elemental concentrations of sample collected at urban and rural site are determined and then the calculation of statistics and the factor analysis are carried out for investigation of emission source. International cooperation research project was carried out for utilization of nuclear techniques.

  16. Research of Multi Detectors of Neutron Spectrum in Mix Fields

    Institute of Scientific and Technical Information of China (English)

    LI; Wei; CHEN; Jun; WANG; Zhi-qiang; LI; Chun-juan; LIU; Yi-na; LUO; Hai-long; ZHANG; Wei-hua

    2013-01-01

    This neutron spectrometer can be used to measure neutron spectrum and neutron equivalent dosimetry.The range of neutron spectrum is thermal-20 MeV,and the range of neutron equivalent dosimetry is 1μSv·h-1-4 mSv·h-1.The sensor head of the neutron spectrum of multi detectors in mix fields houses five gas-filled sensors and a photo-scintillator column.There are two boron tri-fluoride(BF3)and three hydrogen

  17. Bright flash neutron radiography capability of the research reactor at the McClellan Nuclear Research Center

    Energy Technology Data Exchange (ETDEWEB)

    Tremsin, A.S., E-mail: ast@ssl.berkeley.edu [University of California at Berkeley, Berkeley, CA 94720 (United States); Lerche, M. [McClellan Nuclear Research Center, 5335 Price Avenue Building 258, McClellan, CA 95652 (United States); Schillinger, B. [Forschungsreaktor FRM-II, Technische Universität München, D-85747 Garching (Germany); Feller, W.B. [NOVA Scientific, Inc., 10 Picker Road, Sturbridge, MA 01566 (United States)

    2014-06-01

    The capability to produce a bright, short neutron pulse at the McClellan Nuclear Research Center (MNRC) can be very attractive for some neutron imaging applications. Complementary to conventional thermal neutron radiography conducted at the reactor, operating at the average power of 1 MW, a short pulse of ∼25 ms FWHM duration can be produced at MNRC with the peak power exceeding 350 MW. Combination of a fast thermal neutron counting detector with a short neutron pulse at MNRC, enables high-resolution stroboscopic imaging to complement conventional neutron radiography. The results presented in this paper demonstrate the MNRC capabilities for conducting conventional thermal neutron radiography, demonstrating imaging spatial resolution below 100 μm, as well as bright flash neutron radiography with multiple nearly simultaneous events detected with microsecond timing resolution.

  18. Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor.

    Science.gov (United States)

    Yavar, A R; Sarmani, S B; Wood, A K; Fadzil, S M; Radir, M H; Khoo, K S

    2011-05-01

    Determination of thermal to fast neutron flux ratio (f(fast)) and fast neutron flux (ϕ(fast)) is required for fast neutron reactions, fast neutron activation analysis, and for correcting interference reactions. The f(fast) and subsequently ϕ(fast) were determined using the absolute method. The f(fast) ranged from 48 to 155, and the ϕ(fast) was found in the range 1.03×10(10)-4.89×10(10) n cm(-2) s(-1). These values indicate an acceptable conformity and applicable for installation of the fast neutron facility at the MNA research reactor.

  19. Use of cold neutrons for condensed matter research at the neutron guide laboratory ELLA in Juelich

    Energy Technology Data Exchange (ETDEWEB)

    Schaetzler, R.; Monkenbusch, M. [Research Centre Juelich, D-52425 Juelich (Germany)

    1998-07-01

    Cold neutrons produced in the FRJ-2 DIDO reactor are guided into the external hall ELLA. It hosts 10 instruments that are red by three major neutron guides. Cold neutrons allow for diffraction and small angle scattering experiments resolving mesoscopic structures (1 to 100 nm). Contrast variation by isotopic substitution in chemically identical species yields information uniquely accessible bi neutrons. Inelastic scattering of cold neutrons allows investigating slow molecular motions because the low neutron velocity results in large relative velocity changes even at small energy transfers. The SANS machines and the HADAS reflectometer serve as structure probes and the backscattering BSS1 and spin-echo spectrometers NSE as main dynamics probes. Besides this the diffuse scattering instrument DNS and the lattice parameter determination instrument LAP deal mainly with crystals and their defects. Finally the beta-NMR and the EKN position allow for methods other than scattering employing nuclear reactions for solid state physics, chemistry and biology/medicine. (author)

  20. Research of Methodocal Questions of Use of Albedo Personal Neutron Dosi-meter

    CERN Document Server

    Alekseev, A G

    2003-01-01

    In the paper the methods of reception of the correct use of neutron albedo dosimeters are considered. The methods of use such dosimeters in fields with different spectra of neutrons are presented. For testing the experi-mental research of sensitivity DVGN-01and DVN-A-01 dosimeters in reference neutron fields was formed on based of 1-st horizontal research channel of IRT MIPHI reactor.

  1. Progress report on neutron scattering research. April 1, 2001 - March 31, 2002

    Energy Technology Data Exchange (ETDEWEB)

    Katano, Susumu; Koizumi, Satoshi; Matsuda, Masaaki (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2002-11-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3M during the period between April 1, 2001 and March 31, 2002. (author)

  2. Progress report on neutron scattering research (April 1, 1998 - March 31, 1999)

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Jun-ichi; Fujiwara, Satoru; Aizawa, Kazuya [eds.] [Advanced Science Research Center (Tokai Site), Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2000-03-01

    The present issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1998 and March 31, 1999. (author)

  3. Progress report on neutron scattering research. April 1, 1999 - March 31, 2000

    Energy Technology Data Exchange (ETDEWEB)

    Fujiwara, Satoru; Aizawa, Kazuya; Katano, Susumu (eds.) [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2001-03-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1999 and March 31, 2000. (author)

  4. Progress report on neutron scattering research (April 1, 1998 - March 31, 1999)

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Jun-ichi; Fujiwara, Satoru; Aizawa, Kazuya [eds.] [Advanced Science Research Center (Tokai Site), Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)

    2000-03-01

    The present issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1998 and March 31, 1999. (author)

  5. Preliminary Research of Neutron Energy Spectrum of Thermal Neutron Beam Port for IHNI

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    IHNI with 30 kW is specially designed for Boron Neutron Capture Therapy (BNCT), it is the pool-tank reactor, UO2 with enrichment of 12.5% 235U as fuel, beryllium as reflector, light water as moderator and coolant. There are two neutron beams in the opposite side

  6. McCARD for Neutronics Design and Analysis of Research Reactor Cores

    Science.gov (United States)

    Shim, Hyung Jin; Park, Ho Jin; Kwon, Soonwoo; Seo, Geon Ho; Hyo Kim, Chang

    2014-06-01

    McCARD is a Monte Carlo (MC) neutron-photon transport simulation code developed exclusively for the neutronics design and analysis of nuclear reactor cores. McCARD is equipped with the hierarchical modeling and scripting functions, the CAD-based geometry processing module, the adjoint-weighted kinetics parameter and source multiplication factor estimation modules as well as the burnup analysis capability for the neutronics design and analysis of both research and power reactor cores. This paper highlights applicability of McCARD for the research reactor core neutronics analysis, as demonstrated for Kyoto University Critical Assembly, HANARO, and YALINA.

  7. Electronic imaging system for neutron radiography at a low power research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, F.J.O., E-mail: fferreira@ien.gov.b [Instituto de Engenharia Nuclear, Comissao Nacional de Energia Nuclear, Caixa Postal 68550, CEP 21945-970, Rio de Janeiro (Brazil); Silva, A.X.; Crispim, V.R. [PEN/COPPE-DNC/POLI CT, Universidade Federal do Rio de Janeiro, Ilha do Fundao, Caixa Postal 68509, 21945-970 Rio de Janeiro (Brazil)

    2010-08-15

    This paper describes an electronic imaging system for producing real time neutron radiography from a low power research reactor, which will allow inspections of samples with high efficiency, in terms of measuring time and result analysis. This system has been implanted because of its potential use in various scientific and industrial areas where neutron radiography with photographic film could not be applied. This real time system is installed in neutron radiography facility of Argonauta nuclear research reactor, at the Instituto de Engenharia Nuclear of the Comissao Nacional de Energia Nuclear, in Brazil. It is adequate to perform real time neutron radiography of static and dynamic events of samples.

  8. Status of neutron beam utilization at the Dalat nuclear research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dien, Nguyen Nhi; Hai, Nguyen Canh [Nuclear Research Institute, Dalat (Viet Nam)

    2003-03-01

    The 500-kW Dalat nuclear research reactor was reconstructed from the USA-made 250-kW TRIGA Mark II reactor. After completion of renovation and upgrading, the reactor has been operating at its nominal power since 1984. The reactor is used mainly for radioisotope production, neutron activation analysis, neutron beam researches and reactor physics study. In the framework of the reconstruction and renovation project of the 1982-1984 period, the reactor core, the control and instrumentation system, the primary and secondary cooling systems, as well as other associated systems were newly designed and installed by the former Soviet Union. Some structures of the reactor, such as the reactor aluminum tank, the graphite reflector, the thermal column, horizontal beam tubes and the radiation concrete shielding have been remained from the previous TRIGA reactor. As a typical configuration of the TRIGA reactor, there are four neutron beam ports, including three radial and one tangential. Besides, there is a large thermal column. Until now only two-neutron beam ports and the thermal column have been utilized. Effective utilization of horizontal experimental channels is one of the important research objectives at the Dalat reactor. The research program on effective utilization of these experimental channels was conducted from 1984. For this purpose, investigations on physical characteristics of the reactor, neutron spectra and fluxes at these channels, safety conditions in their exploitation, etc. have been carried out. The neutron beams, however, have been used only since 1988. The filtered thermal neutron beams at the tangential channel have been extracted using a single crystal silicon filter and mainly used for prompt gamma neutron activation analysis (PGNAA), neutron radiography (NR) and transmission experiments (TE). The filtered quasi-monoenergetic keV neutron beams using neutron filters at the piercing channel have been used for nuclear data measurements, study on

  9. LENS-a pulsed neutron source for education and research

    Energy Technology Data Exchange (ETDEWEB)

    Baxter, David V. [Physics Department, Indiana University, Bloomington, IN 47405 (United States)]. E-mail: baxterd@indiana.edu; Cameron, J.M. [Physics Department, Indiana University, Bloomington, IN 47405 (United States); Leuschner, M.B. [Physics Department, Indiana University, Bloomington, IN 47405 (United States); Meyer, H.O. [Physics Department, Indiana University, Bloomington, IN 47405 (United States); Nann, H. [Physics Department, Indiana University, Bloomington, IN 47405 (United States); Snow, W.M. [Physics Department, Indiana University, Bloomington, IN 47405 (United States)

    2005-04-21

    At the Indiana University Cyclotron Facility construction of a new source of cold neutrons has begun. Neutrons are generated by stopping 13 MeV protons in a beryllium target, located at the center of a moderator structure. Cold neutrons are emitted from a slab of frozen methane. Three beam lines deliver neutrons for scattering experiments, radiography and moderator studies. The purpose of the project is to develop a low-cost, small-scale facility, suitable for a university or an industrial setting, to provide a testing ground of instrumentation destined for use at a larger facility, to improve awareness of the use of neutron probes in a wide range of applications, and to offer a training opportunity for future neutron physicists.

  10. Nuclear physics with neutrons - fundamental and applied researches

    CERN Document Server

    Furman, V I

    2001-01-01

    The investigations in the field of the nuclear neutron physics in JINR are discussed briefly. The following problems are considered: realization of the project of a new source of resonance neutrons (IREN); development and testing the new perspective techniques for experiments at IREN; studying the symmetry breaking in fundamental interactions in nuclei and obtaining the actual technological nuclear data. The neutron energy is in the range of 10 sup - sup 9 eV-10 MeV

  11. Neutron Imaging at the Oak Ridge National Laboratory: Application to Biological Research

    Energy Technology Data Exchange (ETDEWEB)

    Bilheux, Hassina Z [ORNL; Cekanova, Maria [University of Tennessee, Knoxville (UTK); Bilheux, Jean-Christophe [ORNL; Bailey, William Barton [ORNL; Keener, Wylie S [ORNL; Davis, Larry E [ORNL; Herwig, Kenneth W [ORNL

    2014-01-01

    The Oak Ridge National Laboratory Neutron Sciences Directorate (NScD) has recently installed a neutron imaging beamline at the High Flux Isotope Reactor (HFIR) cold guide hall. The CG-1D beamline supports a broad range of user research spanning from engineering to material research, energy storage, additive manufacturing, vehicle technologies, archaeology, biology, and plant physiology. The beamline performance (spatial resolution, field of view, etc.) and its utilization for biological research are presented. The NScD is also considering a proposal to build the VENUS imaging beamline (beam port 10) at the Spallation Neutron Source (SNS). Unlike CG-1D which provides cold neutrons, VENUS will offer a broad range of neutron wavelengths, from epithermal to cold, and enhanced contrast mechanisms. This new capability will also enable the imaging of thicker biological samples than is currently available at CG-1D. A brief overview of the VENUS capability for biological research is discussed.

  12. Spectrum evaluation at the filter-modified neutron irradiation field for neutron capture therapy in Kyoto University Research Reactor

    Science.gov (United States)

    Sakurai, Yoshinori; Kobayashi, Tooru

    2004-10-01

    The Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor (KUR-HWNIF) was updated in March 1996, mainly to improve the facility for neutron capture therapy (NCT). In this facility, neutron beams with various energy spectra, from almost pure thermal to epithermal, are available. The evaluation of the neutron energy spectra by multi-activation-foil method was performed as a series of the facility characterization. The spectra at the normal irradiation position were evaluated for the combinations of heavy-water thickness of the spectrum shifter and the open-close condition of the cadmium and boral filters. The initial spectra were made mainly using a two-dimensional transport code, and the final spectra were obtained using an adjusting code. For the verification of the evaluated spectra, simulation calculations using a phantom were performed on the assumption of NCT-clinical-irradiation conditions. It resulted that the calculated data for the depth neutron-flux distributions were in good agreement with the experimental ones.

  13. Neutron flux from a 14-MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    Science.gov (United States)

    Rennhofer, H.; Pedersen, B.; Crochemore, J.-M.

    2009-12-01

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14-MeV (D-T) neutron generator and a large graphite mantle surrounding the sample cavity. By pulsing the neutron generator with a frequency in the range of 10 to 150 Hz, a sample may be interrogated first by fast neutrons and a few hundred micro-seconds later by a pure thermal neutron flux. The permanent detection systems incorporated in PUNITA include 3He neutrons detectors, HPGe gamma detectors, and lanthanum bromide scintillation detectors. We have studied the effects of placing a tungsten liner around the neutron generator target. The 14-MeV neutrons induce (n, 2n) and (n, 3n) reactions. In addition the mean neutron energy emitted from generator/tungsten assembly is reduced to about 1 MeV. Both of these effects increase the thermal neutron flux in the sample cavity. The paper describes the observed advantages of the tungsten liner with respect to increase in thermal flux, and better shielding capabilities of the nearby gamma and neutron detectors.

  14. Why Sexually Selected Weapons Are Not Ornaments.

    Science.gov (United States)

    McCullough, Erin L; Miller, Christine W; Emlen, Douglas J

    2016-10-01

    The elaboration and diversification of sexually selected weapons remain poorly understood. We argue that progress in this topic has been hindered by a strong bias in sexual selection research, and a tendency for weapons to be conflated with ornaments used in mate choice. Here, we outline how male-male competition and female choice are distinct mechanisms of sexual selection, and why weapons and ornaments are fundamentally different types of traits. We call for research on the factors contributing to weapon divergence, the potential for male-male competition to drive speciation, and the specific use of weapons in the context of direct fights versus displays. Given that weapons are first and foremost fighting structures, biomechanical approaches are an especially promising direction for understanding weapon design. Copyright © 2016 Elsevier Ltd. All rights reserved.

  15. Filtered epithermal quasi-monoenergetic neutron beams at research reactor facilities.

    Science.gov (United States)

    Mansy, M S; Bashter, I I; El-Mesiry, M S; Habib, N; Adib, M

    2015-03-01

    Filtered neutron techniques were applied to produce quasi-monoenergetic neutron beams in the energy range of 1.5-133keV at research reactors. A simulation study was performed to characterize the filter components and transmitted beam lines. The filtered beams were characterized in terms of the optimal thickness of the main and additive components. The filtered neutron beams had high purity and intensity, with low contamination from the accompanying thermal emission, fast neutrons and γ-rays. A computer code named "QMNB" was developed in the "MATLAB" programming language to perform the required calculations.

  16. Design of the cold neutron triple-axis spectrometer at the China Advanced Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Cheng, P.; Zhang, Hongxia; Bao, W. [Department of Physics, Beijing Key Laboratory of Opto-electronic Functional Materials & Micro-nano Devices, Renmin University of China, Beijing 100872 (China); Schneidewind, A. [Jülich Center for Neutron Science (JCNS), Forschungszentrum Jülich GmbH, Outstation at Heinz MaierCLeibnitz Zentrum (MLZ), D-85747 Garching (Germany); Link, P. [Heinz Maier-Leibnitz Zentrum, Technische Universität München, D-85748 Garching (Germany); Grünwald, A.T.D. [II. Physikalisches Institut, Universität zu Köln, D-50937 Köln (Germany); Georgii, R. [Heinz Maier-Leibnitz Zentrum, Technische Universität München, D-85748 Garching (Germany); Hao, L.J.; Liu, Y.T. [China Institute of Atomic Energy, PO Box-275-30, Beijing 102413 (China)

    2016-06-11

    The design of the first cold neutron triple-axis spectrometer at the China Advanced Research Reactor is presented. Based on the Monte Carlo simulations using neutron ray-tracing program McStas, the parameters of major neutron optics in this instrument are optimized. The neutron flux at sample position is estimated to be 5.6 ×10{sup 7} n/cm{sup 2}/s at neutron incident energy E{sub i}=5 meV when the reactor operates normally at the designed 60 MW power. The performances of several neutron supermirror polarizing devices are compared and their critical parameters are optimized for this spectrometer. The polarization analysis will be realized with a flexible switch from the unpolarized experimental mode.

  17. Design of the cold neutron triple-axis spectrometer at the China Advanced Research Reactor

    Science.gov (United States)

    Cheng, P.; Zhang, Hongxia; Bao, W.; Schneidewind, A.; Link, P.; Grünwald, A. T. D.; Georgii, R.; Hao, L. J.; Liu, Y. T.

    2016-06-01

    The design of the first cold neutron triple-axis spectrometer at the China Advanced Research Reactor is presented. Based on the Monte Carlo simulations using neutron ray-tracing program McStas, the parameters of major neutron optics in this instrument are optimized. The neutron flux at sample position is estimated to be 5.6 ×107 n/cm2/s at neutron incident energy Ei=5 meV when the reactor operates normally at the designed 60 MW power. The performances of several neutron supermirror polarizing devices are compared and their critical parameters are optimized for this spectrometer. The polarization analysis will be realized with a flexible switch from the unpolarized experimental mode.

  18. Plastic fiber scintillator response to fast neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Danly, C. R.; Sjue, S.; Wilde, C. H.; Merrill, F. E.; Haight, R. C. [Los Alamos National Laboratory, Los Alamos, New Mexico 87544 (United States)

    2014-11-15

    The Neutron Imaging System at NIF uses an array of plastic scintillator fibers in conjunction with a time-gated imaging system to form an image of the neutron emission from the imploded capsule. By gating on neutrons that have scattered from the 14.1 MeV DT energy to lower energy ranges, an image of the dense, cold fuel around the hotspot is also obtained. An unmoderated spallation neutron beamline at the Weapons Neutron Research facility at Los Alamos was used in conjunction with a time-gated imaging system to measure the yield of a scintillating fiber array over several energy bands ranging from 1 to 15 MeV. The results and comparison to simulation are presented.

  19. Current status of neutron activation analysis using the Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Nguyen Van Suc; Nguyen Mong Sinh [Nuclear Research Institute, Dalat (Viet Nam)

    1999-10-01

    Neutron activation analysis is one of the most sensitive, rapid, accurated methods for determination of trace elements in different materials. A review is made of the current status of the activities and the results in studying and developing NAA (Neutron Activation Analysis) at the Dalat Nuclear Research Institute and applying this method to different sectors of science and technology in Vietnam. (author)

  20. Characterization of the fast neutron irradiation facility of the Portuguese Research Reactor after core conversion.

    Science.gov (United States)

    Marques, J G; Sousa, M; Santos, J P; Fernandes, A C

    2011-08-01

    The fast neutron irradiation facility of the Portuguese Research Reactor was characterized after the reduction in uranium enrichment and rearrangement of the core configuration. In this work we report on the determination of the hardness parameter and the 1MeV equivalent neutron flux along the facility, in the new irradiation conditions, following ASTM E722 standard.

  1. Operational status of the Los Alamos neutron science center (LANSCE)

    Energy Technology Data Exchange (ETDEWEB)

    Jones, Kevin W [Los Alamos National Laboratory; Erickson, John L [Los Alamos National Laboratory; Schoenberg, Kurt F [Los Alamos National Laboratory

    2010-01-01

    The Los Alamos Neutron Science Center (LANSCE) accelerator and beam delivery complex generates the proton beams that serve three neutron production sources; the thermal and cold source for the Manuel Lujan Jr. Neutron Scattering Center, the Weapons Neutron Research (WNR) high-energy neutron source, and a pulsed Ultra-Cold Neutron Source. These three sources are the foundation of strong and productive multi-disciplinary research programs that serve a diverse and robust user community. The facility also provides multiplexed beams for the production of medical radioisotopes and proton radiography of dynamic events. The recent operating history of these sources will be reviewed and plans for performance improvement will be discussed, together with the underlying drivers for the proposed LANSCE Refurbishment project. The details of this latter project are presented in a separate contribution.

  2. Controllability of depth dose distribution for neutron capture therapy at the Heavy Water Neutron Irradiation Facility of Kyoto University Research Reactor.

    Science.gov (United States)

    Sakurai, Yoshinori; Kobayashi, Tooru

    2002-10-01

    The updating construction of the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor has been performed from November 1995 to March 1996 mainly for the improvement in neutron capture therapy. On the performance, the neutron irradiation modes with the variable energy spectra from almost pure thermal to epi-thermal neutrons became available by the control of the heavy-water thickness in the spectrum shifter and by the open-and-close of the cadmium and boral thermal neutron filters. The depth distributions of thermal, epi-thermal and fast neutron fluxes were measured by activation method using gold and indium, and the depth distributions of gamma-ray absorbed dose rate were measured using thermo-luminescent dosimeter of beryllium oxide for the several irradiation modes. From these measured data, the controllability of the depth dose distribution using the spectrum shifter and the thermal neutron filters was confirmed.

  3. Characterization of the Annular Core Research Reactor (ACRR Neutron Radiography System Imaging Plane

    Directory of Open Access Journals (Sweden)

    Kaiser Krista

    2016-01-01

    Full Text Available The Annular Core Research Reactor (ACRR at Sandia National Laboratories (SNL is an epithermal pool-type research reactor licensed up to a thermal power of 2.4 MW. The ACRR facility has a neutron radiography facility that is used for imaging a wide range of items including reactor fuel and neutron generators. The ACRR neutron radiography system has four apertures (65:1, 125:1, 250:1, and 500:1 available to experimenters. The neutron flux and spectrum as well as the gamma dose rate were characterized at the imaging plane for the ACRR's neutron radiography system for the 65:1, 125:1 and 250:1 apertures.

  4. Characterization of the Annular Core Research Reactor (ACRR) Neutron Radiography System Imaging Plane

    Science.gov (United States)

    Kaiser, Krista; Chantel Nowlen, K.; DePriest, K. Russell

    2016-02-01

    The Annular Core Research Reactor (ACRR) at Sandia National Laboratories (SNL) is an epithermal pool-type research reactor licensed up to a thermal power of 2.4 MW. The ACRR facility has a neutron radiography facility that is used for imaging a wide range of items including reactor fuel and neutron generators. The ACRR neutron radiography system has four apertures (65:1, 125:1, 250:1, and 500:1) available to experimenters. The neutron flux and spectrum as well as the gamma dose rate were characterized at the imaging plane for the ACRR's neutron radiography system for the 65:1, 125:1 and 250:1 apertures.

  5. Research for the concept of Hanaro cold neutron source

    Energy Technology Data Exchange (ETDEWEB)

    Choi, Chang Oong; Cho, M. S.; Lee, M. W.; Sohn, J. M.; Park, K. N.; Park, S. H.; Yang, S. Y.; Kang, S. H.; Yang, S. H.; Chang, J. H.; Lee, Y. W.; Chang, C. I.; Cho, Y. S.

    1997-09-01

    This report consists of two parts, one is the conceptual design performed on the collaboration work with PNPI Russia and another is review of Hanaro CNS conceptual design report by Technicatome France, both of which are contained at vol. I and vol. II. representatively. In the vol. I, the analysis for the status of technology development, the technical characteristics of CNS is included, and the conceptual design of Hanaro cold neutron source is contained to establish the concept suitable to Hanaro. The cold neutron experimental facilities, first of all, have been selected to propose the future direction of physics concerning properties of the matter at Korea. And neutron guide tubes, the experimental hall and cold neutron source appropriate to these devices have been selected and design has been reviewed in view of securing safety and installing at Hanaro. (author). 38 refs., 49 tabs., 17 figs.

  6. Neutron Ghost Imaging Technology Research on CARR Reactor

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Ghost imaging is also known as quantum imaging. Different from the classical imaging, the neutron ghost imaging is based on the quantum mechanics properties of light field and its intrinsic parallel characteristic, and developed by new optical

  7. Illegal Weapons Exports?

    Institute of Scientific and Technical Information of China (English)

    2006-01-01

    Amnesty International, a human rights organization, released a report on June 11 accusing China of facilitating regional conflicts and human rights violations by exporting a large quantity of weapons to Sudan, Nepal, Myanmar and the Great Lakes countries of Africa. Responding to such charges, Teng Jianqun, a researcher with the China Arms Control and Disarmament Association, told the official Xinhua News Agency that China has always put its limited arms exports under strict control and surveillance, deno...

  8. The Research Progress of the Liquid Scintillation Detectors on Neutron Measurement

    Institute of Scientific and Technical Information of China (English)

    CHENG; Yi-mei; XU; Xiao-ming; ZHU; Li-qun; BAI; Lei; XU; Zhen; HE; Li-xia; YIN; Hong-he

    2012-01-01

    <正>The research for liquid scintillation detectors on neutron measurement is one of the study objects of technique research on neutron measurement. According to the task requirements, we accomplished the purchase of some detectors and related performance testing. The purchased liquid scintillation detectors BC-501A is produced by Saint-Gobain Company. According to the formulated performance testing outlines for liquid scintillation detectors, we conducted

  9. Preventing biological weapon development through the governance of life science research.

    Science.gov (United States)

    Epstein, Gerald L

    2012-03-01

    The dual-use dilemma in the life sciences-that illicit applications draw on the same science and technology base as legitimate applications-makes it inherently difficult to control one without inhibiting the other. Since before the September 11 attacks, the science and security communities in the United States have struggled to develop governance processes that can simultaneously minimize the risk of misuse of the life sciences, promote their beneficial applications, and protect the public trust. What has become clear over that time is that while procedural steps can be specified for assessing and managing dual-use risks in the review of research proposals, oversight of ongoing research, and communication of research results, the actions or decisions to be taken at each of these steps to mitigate dual-use risk defy codification. Yet the stakes are too high to do nothing, or to be seen as doing nothing. The U.S. government should therefore adopt an oversight framework largely along the lines recommended by the National Science Advisory Board for Biosecurity almost 5 years ago-one that builds on existing processes, can gain buy-in from the scientific community, and can be implemented at modest cost (both direct and opportunity), while providing assurance that a considered and independent examination of dual-use risks is being applied. Without extraordinary visibility into the actions of those who would misuse biology, it may be impossible to know how well such an oversight system will actually succeed at mitigating misuse. But maintaining the public trust will require a system to be established in which reasonably foreseeable dual-use consequences of life science research are anticipated, evaluated, and addressed.

  10. Determination of fast neutron flux distribution in irradiation sites of the Malaysian Nuclear Agency research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Yavar, A.R. [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Sarmani, S.B. [School of Chemical Sciences and Food Technology, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Wood, A.K. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, 43000 Kajang, Selangor (Malaysia); Fadzil, S.M. [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia); Radir, M.H. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, 43000 Kajang, Selangor (Malaysia); Khoo, K.S., E-mail: khoo@ukm.m [School of Applied Physics, Faculty of Science and Technology, National University of Malaysia (UKM), 43600 Bangi, Selangor (Malaysia)

    2011-05-15

    Determination of thermal to fast neutron flux ratio (f{sub fast}) and fast neutron flux ({phi}{sub fast}) is required for fast neutron reactions, fast neutron activation analysis, and for correcting interference reactions. The f{sub fast} and subsequently {phi}{sub fast} were determined using the absolute method. The f{sub fast} ranged from 48 to 155, and the {phi}{sub fast} was found in the range 1.03x10{sup 10}-4.89x10{sup 10} n cm{sup -2} s{sup -1}. These values indicate an acceptable conformity and applicable for installation of the fast neutron facility at the MNA research reactor.

  11. Bright Flash Neutron Radiography at the McClellan Nuclear Research Reactor

    Science.gov (United States)

    Lerche, M.; Tremsin, A. S.; Schillinger, B.

    The University of California, Davis McClellan Nuclear Research Center (MNRC) operates a 2 MW TRIGATM reactor, which is currently the highest power TRIGATM reactor in the United States. The Center was originally build by the US Air Force to detect hidden defects in aircraft structures using neutron radiography; the Center can accommodate samples as large as 10.00 m long, 3.65 m high, and weighing up to 2,270 kg. The MNRC reactor can be pulsed to 350 MW for about 30 ms (FWHM). The combination of a short neutron pulse with a fast microchannel plate based neutron detector enables high-resolution flash neutron radiography to complement conventional neutron radiography

  12. Comparison of neutron spectrum measurement methods used for the epithermal beam of the LVR-15 research reactor.

    Science.gov (United States)

    Viererbl, L; Klupák, V; Lahodová, Z; Marek, M

    2012-07-01

    The LVR-15 research reactor's horizontal channel with its epithermal neutron beam is used mainly for boron neutron capture therapy. Neutrons from the reactor core pass through a special filter before the collimator and the beam outlet. Neutron fluence and spectrum are the basic characteristics of an epithermal neutron beam. Three methods used to measure the beam's neutron spectrum are described: the activation method, a Bonner sphere spectrometer with gold activation detectors and a Bonner sphere spectrometer with LiI(Eu) scintillation detector. Examples of results are compared and discussed.

  13. Calibration of NIF neutron detectors in the energy region E<14 MeV

    Energy Technology Data Exchange (ETDEWEB)

    Schmid, G J; Moran, M J; Koch, J A; Phillips, T W; Glebov, V Y; Sangster, T C; Stoeckl, C; Wender, S A; Morse, E C

    2004-04-09

    We examine various options for calibration of NIF neutron detectors in the energy region E<14 MeV. These options include: downscatter of D-T fusion neutrons using plastic targets; nuclear reactions at a Tandem Van de Graaf accelerator; and ''white'' neutrons from a pulsed spallation source. As an example of the spallation option, we present some calibration data that was recently obtained with a single crystal CVD diamond detector at the Weapons Neutron Research facility (WNR) at LANL.

  14. The Prospect of Neutron Scattering In the 21st Century: A Powerful Tool for Materials Research

    Directory of Open Access Journals (Sweden)

    E. Kartini

    2007-07-01

    Full Text Available Over the last 60 years research reactors (RRs have played an important role in technological and socio-economical development of mankind, such as radioisotope production for medicine, industry, research and education. Neutron scattering has been widely used for research and development in materials science. The prospect of neutron scattering as a powerful tool for materials research is increasing in the 21st century. This can be seen from the investment of several new neutron sources all over the world such as the Spallation Neutron Source (SNS in USA, the Japan Proton Accelerator Complex (JPARC in Japan, the new OPAL Reactor in Australia, and some upgrading to the existing sources at ISIS, Rutherford Appleton Laboratory, UK; Institute of Laue Langevin (ILL in Grenoble, France and Berlin Reactor, Germany. Developing countries with moderate flux research reactor have also been involved in this technique, such as India, Malaysia and Indonesia. The Siwabessy Multipurpose Reactor in Serpong, Indonesia that also produces thermal neutron has contributed to the research and development in the Asia Pacific Region. However, the international joint research among those countries plays an important role on optimizing the results.

  15. Neutron flux from a 14‐MeV neutron generator with tungsten filter for research in NDA methods for nuclear safeguards and security

    OpenAIRE

    2009-01-01

    The Joint Research Centre has taken into operation a new experimental device designed for research in the fields of nuclear safeguards and security applications. The research projects currently undertaken include detection of shielded contraband materials, detection of fissile materials, and mass determination of small fissile materials in shielded containers. The device, called the Pulsed Neutron Interrogation Test Assembly (PUNITA), incorporates a pulsed 14‐MeV (D‐T) neutron generator and a...

  16. Progress report on neutron scattering research (April 1, 1997 - March 31, 1998)

    Energy Technology Data Exchange (ETDEWEB)

    Suzuki, Jun-ichi; Fujiwara, Satoru; Aizawa, Kazuya [eds.

    1999-02-01

    The present issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) during the period between April 1, 1997 and March 31, 1998. The 76 papers are indexed individually. (J.P.N.)

  17. Progress report on neutron scattering research (April 1, 1996 - March 31, 1997)

    Energy Technology Data Exchange (ETDEWEB)

    Ishii, Yoshinobu; Suzuki, Jun-ichi; Fujiwara, Satoru [eds.

    1997-10-01

    This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor (JRR-3M) mainly during the period between April 1, 1996 and March 31, 1997. The 57 of the presented papers are indexed individually. (J.P.N.)

  18. Monte Carlo methods of neutron beam design for neutron capture therapy at the MIT Research Reactor (MITR-II).

    Science.gov (United States)

    Clement, S D; Choi, J R; Zamenhof, R G; Yanch, J C; Harling, O K

    1990-01-01

    Monte Carlo methods of coupled neutron/photon transport are being used in the design of filtered beams for Neutron Capture Therapy (NCT). This method of beam analysis provides segregation of each individual dose component, and thereby facilitates beam optimization. The Monte Carlo method is discussed in some detail in relation to NCT epithermal beam design. Ideal neutron beams (i.e., plane-wave monoenergetic neutron beams with no primary gamma-ray contamination) have been modeled both for comparison and to establish target conditions for a practical NCT epithermal beam design. Detailed models of the 5 MWt Massachusetts Institute of Technology Research Reactor (MITR-II) together with a polyethylene head phantom have been used to characterize approximately 100 beam filter and moderator configurations. Using the Monte Carlo methodology of beam design and benchmarking/calibrating our computations with measurements, has resulted in an epithermal beam design which is useful for therapy of deep-seated brain tumors. This beam is predicted to be capable of delivering a dose of 2000 RBE-cGy (cJ/kg) to a therapeutic advantage depth of 5.7 cm in polyethylene assuming 30 micrograms/g 10B in tumor with a ten-to-one tumor-to-blood ratio, and a beam diameter of 18.4 cm. The advantage ratio (AR) is predicted to be 2.2 with a total irradiation time of approximately 80 minutes. Further optimization work on the MITR-II epithermal beams is expected to improve the available beams.

  19. A feasibility study of the Tehran research reactor as a neutron source for BNCT.

    Science.gov (United States)

    Kasesaz, Yaser; Khalafi, Hossein; Rahmani, Faezeh; Ezati, Arsalan; Keyvani, Mehdi; Hossnirokh, Ashkan; Shamami, Mehrdad Azizi; Monshizadeh, Mahdi

    2014-08-01

    Investigation on the use of the Tehran Research Reactor (TRR) as a neutron source for Boron Neutron Capture Therapy (BNCT) has been performed by calculating and measuring energy spectrum and the spatial distribution of neutrons in all external irradiation facilities, including six beam tubes, thermal column, and the medical room. Activation methods with multiple foils and a copper wire have been used for the mentioned measurements. The results show that (1) the small diameter and long length beam tubes cannot provide sufficient neutron flux for BNCT; (2) in order to use the medical room, the TRR core should be placed in the open pool position, in this situation the distance between the core and patient position is about 400 cm, so neutron flux cannot be sufficient for BNCT; and (3) the best facility which can be adapted for BNCT application is the thermal column, if all graphite blocks can be removed. The epithermal and fast neutron flux at the beginning of this empty column are 4.12×10(9) and 1.21×10(9) n/cm(2)/s, respectively, which can provide an appropriate neutron beam for BNCT by designing and constructing a proper Beam Shaping Assembly (BSA) structure.

  20. Neutron radigoraphy of fluid flow for geothermal energy research

    Energy Technology Data Exchange (ETDEWEB)

    Bingham, Philip R [ORNL; Polsky, Yarom [ORNL; Anovitz, Lawrence {Larry} M [ORNL; Carmichael, Justin R [ORNL; Bilheux, Hassina Z [ORNL; Hussey, Dan [NIST Center for Neutron Research (NCRN), Gaithersburg, MD; Jacobson, David [National Institute of Standards and Technology (NIST)

    2015-01-01

    Enhanced geothermal systems seek to expand the potential for geothermal energy by engineering heat exchange systems within the earth. A neutron radiography imaging method has been developed for the study of fluid flow through rock under environmental conditions found in enhanced geothermal energy systems. For this method, a pressure vessel suitable for neutron radiography was designed and fabricated, modifications to imaging instrument setups were tested, multiple contrast agents were tested, and algorithms developed for tracking of flow. The method has shown success for tracking of single phase flow through a manufactured crack in a 3.81 cm (1.5 inch) diameter core within a pressure vessel capable of confinement up to 69 MPa (10,000 psi) using a particle tracking approach with bubbles of fluorocarbon-based fluid as the “particles” and imaging with 10 ms exposures.

  1. Exploring matter with neutrons. highlights in research at the ILL

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2000-07-01

    Neutrons are excellent probes of all kinds of matter. They are more penetrating than X-rays and provide complementary information on structure and dynamics. There are many variations of the neutron scattering process which gives the technique its wide applicability to many kinds of materials. This report briefly reviews the latest uses of this technique applied to: (i) Biology (cellulose, biological membranes and lipid membranes), (ii) Soft matter (ultrathin polymer films, the flowing of detergents and pastes), (iii) Liquids and glasses (glass transition, sound propagation in water), (iv) Chemistry and structure (the many phases of water), (v) Materials (alloys, helium bubbles in steel), (vi) Thin films (magnetic spirals in very thin films, giant magnetoresistance), (vii) Magnetism (molecular magnets, magnetic phase transitions, glassy magnets), and (viii) superfluid helium in porous media. (A.C.)

  2. Nuclear weapons modernizations

    Energy Technology Data Exchange (ETDEWEB)

    Kristensen, Hans M. [Federation of American Scientists, Washington, DC (United States)

    2014-05-09

    This article reviews the nuclear weapons modernization programs underway in the world's nine nuclear weapons states. It concludes that despite significant reductions in overall weapons inventories since the end of the Cold War, the pace of reductions is slowing - four of the nuclear weapons states are even increasing their arsenals, and all the nuclear weapons states are busy modernizing their remaining arsenals in what appears to be a dynamic and counterproductive nuclear competition. The author questions whether perpetual modernization combined with no specific plan for the elimination of nuclear weapons is consistent with the nuclear Non-Proliferation Treaty and concludes that new limits on nuclear modernizations are needed.

  3. Spectral performance of a composite single-crystal filtered thermal neutron beam for BNCT research at the University of Missouri.

    Science.gov (United States)

    Brockman, J; Nigg, D W; Hawthorne, M F; McKibben, C

    2009-07-01

    Parameter studies, design calculations and initial neutronic performance measurements have been completed for a new thermal neutron beamline to be used for neutron capture therapy cell and small-animal radiobiology studies at the University of Missouri Research Reactor. The beamline features the use of single-crystal silicon and bismuth sections for neutron filtering and for reduction of incident gamma radiation. The calculated and measured thermal neutron fluxes produced at the irradiation location are 9.6 x 10(8) and 8.8 x 10(8)neutrons/cm(2)s, respectively. Calculated and measured cadmium ratios (Au foils) are 217 and 132. These results indicate a well-thermalized neutron spectrum with sufficient thermal neutron flux for a variety of small animal BNCT studies.

  4. Detecting necessary and sufficient parts for assembling a functional weapon

    Science.gov (United States)

    Hempelmann, Christian F.; Solomon, Divya; Arslan, Abdullah N.; Attardo, Salvatore; Blount, Grady P.; Adkins, Tracy; Sirakov, Nikolay M.

    2017-05-01

    Continuing our previous research to visually extract and visually and conceptually match weapons, this study develops a method to determine whether a set of weapon parts visually extracted from images taken from different scenes can be assembled as a firing weapon. This new approach identifies potential weapons in the ontology via tracing detected necessary and sufficient parts through their meronymic relation to the whole weapon. A fast algorithm for identifying potential weapons that can be assembled from a given set of detected parts is presented.

  5. Research on demonstration methodology for system of systems on weapon and equipment%关于武器装备体系论证方法的思考

    Institute of Scientific and Technical Information of China (English)

    魏继才; 崔颢; 任庭光; 董杰

    2011-01-01

    Characteristic of development and demonstration for system of systems on weapon and equipment were analyzed. Issue of demonstration was also analyzed. Demonstration methodology for system of systems on weapon and equipment was built based on the analysis means and methods. This could be adapted for development of system of systems on weapon and equipment in information age. The essential characteristics of stratagem research are discussed and the stratagem research methodology is brought forward and constructed. Then under the guidance of the combination of qualitative and quantitative methods, the meta-synthetic integrated environment of stratagem research is designed, realized and applied to solve the stratagem research problem.%针对武器装备体系建设的特点,简述了目前武器装备体系论证特点和存在的方法问题.通过分析武器装备体系论证手段,剖析武器装备体系论证方法,提出应合理建立武器装备体系论证方法体系,形成武器装备体系论证方法论,以适应在信息化条件下武器装备体系建设的论证要求.依据上述方法论结合武器装备体系论证的特点,建立了软件综合集成环境,环境中每个软件工具或软件分系统,可根据不同论证任务,灵活形成针对该论证任务的软件环境,以满足相应论证任务的需要,体现定性分析与定量评估相结合.

  6. Standard Practice for Application and Analysis of Nuclear Research Emulsions for Fast Neutron Dosimetry

    CERN Document Server

    American Society for Testing and Materials. Philadelphia

    2006-01-01

    1.1 Nuclear Research Emulsions (NRE) have a long and illustrious history of applications in the physical sciences, earth sciences and biological sciences (1,2) . In the physical sciences, NRE experiments have led to many fundamental discoveries in such diverse disciplines as nuclear physics, cosmic ray physics and high energy physics. In the applied physical sciences, NRE have been used in neutron physics experiments in both fission and fusion reactor environments (3-6). Numerous NRE neutron experiments can be found in other applied disciplines, such as nuclear engineering, environmental monitoring and health physics. Given the breadth of NRE applications, there exist many textbooks and handbooks that provide considerable detail on the techniques used in the NRE method. As a consequence, this practice will be restricted to the application of the NRE method for neutron measurements in reactor physics and nuclear engineering with particular emphasis on neutron dosimetry in benchmark fields (see Matrix E706). 1...

  7. Neutron flux optimization in irradiation facilities at Peruvian research reactor RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Vela, M.; Arrieta, R.; Salazar, A.; Urcia, A.; Canaza, D.; Felix, J; Veramendi, E.; Ovalle, E.; Giol, R.; Zapata, L.; Ramos, F.; Tordocillo, J. [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru). Direccion de Instalaciones. Dept. de Reactores]. E-mail: mvela@ipen.gob.pe; rarrieta@ipen.gob.pe

    2005-07-01

    In this work we show the values distribution of the neutron flux at Peruvian Research Reactor RP-10, determined under two different safety and control rods configurations. The method applied was to irradiate small gold foils in irradiation facilities of the core to carry out the nuclear reaction {sup 197}Au(n, {gamma}){sup 198}Au; then using a gamma spectrometry system and the Westcott formalism we obtained the neutron flux. The results confirm the favorable effect of such configurations, increasing the neutron flux, both thermal and epithermal. These results have consistency with the weekly activity reports of radioisotopes lots given by the Radioisotopes Production Plant and Neutron Activation Analysis Group. (author)

  8. Chemistry and Materials Science progress report, first half FY 1992. Weapons-Supporting Research and Laboratory Directed Research and Development

    Energy Technology Data Exchange (ETDEWEB)

    1992-07-01

    This report contains sections on: Fundamentals of the physics and processing of metals; interfaces, adhesion, and bonding; energetic materials; plutonium research; synchrotron radiation-based materials science; atomistic approach to the interaction of surfaces with the environment: actinide studies; properties of carbon fibers; buried layer formation using ion implantation; active coherent control of chemical reaction dynamics; inorganic and organic aerogels; synthesis and characterization of melamine-formaldehyde aerogels; structural transformation and precursor phenomena in advanced materials; magnetic ultrathin films, surfaces, and overlayers; ductile-phase toughening of refractory-metal intermetallics; particle-solid interactions; electronic structure evolution of metal clusters; and nanoscale lithography induced chemically or physically by modified scanned probe microscopy.

  9. Neutron tomography of particulate filters: a non-destructive investigation tool for applied and industrial research

    Energy Technology Data Exchange (ETDEWEB)

    Toops, Todd J., E-mail: toopstj@ornl.gov [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Bilheux, Hassina Z.; Voisin, Sophie [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Gregor, Jens [University of Tennessee, Knoxville, TN (United States); Walker, Lakeisha; Strzelec, Andrea; Finney, Charles E.A.; Pihl, Josh A. [Oak Ridge National Laboratory, Oak Ridge, TN (United States)

    2013-11-21

    This research describes the development and implementation of high-fidelity neutron imaging and the associated analysis of the images. This advanced capability allows the non-destructive, non-invasive imaging of particulate filters (PFs) and how the deposition of particulate and catalytic washcoat occurs within the filter. The majority of the efforts described here were performed at the High Flux Isotope Reactor (HFIR) CG-1D neutron imaging beamline at Oak Ridge National Laboratory; the current spatial resolution is approximately 50 μm. The sample holder is equipped with a high-precision rotation stage that allows 3D imaging (i.e., computed tomography) of the sample when combined with computerized reconstruction tools. What enables the neutron-based image is the ability of some elements to absorb or scatter neutrons where other elements allow the neutron to pass through them with negligible interaction. Of particular interest in this study is the scattering of neutrons by hydrogen-containing molecules, such as hydrocarbons (HCs) and/or water, which are adsorbed to the surface of soot, ash and catalytic washcoat. Even so, the interactions with this adsorbed water/HC is low and computational techniques were required to enhance the contrast, primarily a modified simultaneous iterative reconstruction technique (SIRT). This effort describes the following systems: particulate randomly distributed in a PF, ash deposition in PFs, a catalyzed washcoat layer in a PF, and three particulate loadings in a SiC PF.

  10. Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor *

    Directory of Open Access Journals (Sweden)

    Parma Edward J.

    2016-01-01

    Full Text Available Characterization of the neutron environment in the central cavity of the Sandia National Laboratories' Annular Core Research Reactor (ACRR is important in order to provide experimenters with the most accurate spectral information and maintain a high degree of fidelity in performing reactor experiments. Characterization includes both modeling and experimental efforts. Building accurate neutronic models of the ACRR and the central cavity “bucket” environments that can be used by experimenters is important in planning and designing experiments, as well as assessing the experimental results and quantifying uncertainties. Neutron fluence characterizations of two bucket environments, LB44 and PLG, are presented. These two environments are used frequently and represent two extremes in the neutron spectrum. The LB44 bucket is designed to remove the thermal component of the neutron spectrum and significantly attenuate the gamma-ray fluence. The PLG bucket is designed to enhance the thermal component of the neutron spectrum and attenuate the gamma-ray fluence. The neutron characterization for each bucket was performed by irradiating 20 different activation foil types, some of which were cadmium covered, resulting in 37 different reactions at the peak axial flux location in each bucket. The dosimetry results were used in the LSL-M2 spectrum adjustment code with a 640-energy group MCNP-generated trial spectrum, self-shielding correction factors, the SNLRML or IRDFF dosimetry cross-section library, trial spectrum uncertainty, and trial covariance matrix, to generate a least-squares adjusted neutron spectrum, spectrum uncertainty, and covariance matrix. Both environment character-izations are well documented and the environments are available for use by experimenters.

  11. Neutron Environment Characterization of the Central Cavity in the Annular Core Research Reactor

    Science.gov (United States)

    Parma, Edward J.; Naranjo, Gerald E.; Lippert, Lance L.; Vehar, David W.

    2016-02-01

    Characterization of the neutron environment in the central cavity of the Sandia National Laboratories' Annular Core Research Reactor (ACRR) is important in order to provide experimenters with the most accurate spectral information and maintain a high degree of fidelity in performing reactor experiments. Characterization includes both modeling and experimental efforts. Building accurate neutronic models of the ACRR and the central cavity "bucket" environments that can be used by experimenters is important in planning and designing experiments, as well as assessing the experimental results and quantifying uncertainties. Neutron fluence characterizations of two bucket environments, LB44 and PLG, are presented. These two environments are used frequently and represent two extremes in the neutron spectrum. The LB44 bucket is designed to remove the thermal component of the neutron spectrum and significantly attenuate the gamma-ray fluence. The PLG bucket is designed to enhance the thermal component of the neutron spectrum and attenuate the gamma-ray fluence. The neutron characterization for each bucket was performed by irradiating 20 different activation foil types, some of which were cadmium covered, resulting in 37 different reactions at the peak axial flux location in each bucket. The dosimetry results were used in the LSL-M2 spectrum adjustment code with a 640-energy group MCNP-generated trial spectrum, self-shielding correction factors, the SNLRML or IRDFF dosimetry cross-section library, trial spectrum uncertainty, and trial covariance matrix, to generate a least-squares adjusted neutron spectrum, spectrum uncertainty, and covariance matrix. Both environment character-izations are well documented and the environments are available for use by experimenters. Work supported by the United States Department of Energy at Sandia National Laboratories. Sandia National Laboratories is a multi-program laboratory managed and operated by Sandia Corporation, a wholly owned

  12. Characteristics of the WNR: a pulsed spallation neutron source

    Energy Technology Data Exchange (ETDEWEB)

    Russell, G.J.; Lisowski, P.W.; Howe, S.D.; King, N.S.P.; Meier, M.M.

    1982-01-01

    The Weapons Neutron Research facility (WNR) is a pulsed spallation neutron source in operation at the Los Alamos National Laboratory. The WNR uses part of the 800-MeV proton beam from the Clinton P. Anderson Meson Physics Facility accelerator. By choosing different target and moderator configurations and varying the proton pulse structure, the WNR can provide a white neutron source spanning the energy range from a few MeV to 800 MeV. The neutron spectrum from a bare target has been measured and is compared with predictions using an Intranuclear Cascade model coupled to a Monte Carlo transport code. Calculations and measurements of the neutronics of WNR target-moderator assemblies are presented.

  13. 7 CFR 501.12 - Weapons and explosives.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Weapons and explosives. 501.12 Section 501.12... OF AGRICULTURE CONDUCT ON U.S. MEAT ANIMAL RESEARCH CENTER, CLAY CENTER, NEBRASKA § 501.12 Weapons... arrows, darts, other dangerous or deadly weapons, or explosives, either openly or concealed, except as...

  14. A CONCEPTUAL DESIGN OF NEUTRON COLLIMATOR IN THE THERMAL COLUMN OF KARTINI RESEARCH REACTOR FOR IN VITRO AND IN VIVO TEST OF BORON NEUTRON CAPTURE THERAPY

    OpenAIRE

    Nina Fauziah; Andang Widiharto; Yohannes Sardjono

    2015-01-01

    Studies were carried out to design a collimator which results in epithermal neutron beam for IN VITRO and IN VIVO of Boron Neutron Capture Therapy (BNCT) at the Kartini research reactor by means of Monte Carlo N-Particle (MCNP) codes. Reactor within 100 kW of thermal power was used as the neutron source. The design criteria were based on recommendation from the International Atomic Energy Agency (IAEA). All materials used were varied in size, according to the value of mean free path for each ...

  15. Analytical capabilities of the new thermal neutron prompt gamma-ray activation analysis instrument at the National Institute of Standards and Technology Center for Neutron Research

    Energy Technology Data Exchange (ETDEWEB)

    Mackey, E.A. [National Institute of Standards and Technology, Analytical Chemistry Division, Gaithersburg, MD (United States); Anderson, D.L. [US Food and Drug Administration, Elemental Research Branch, College Park, MD (United States)

    2004-07-01

    A new thermal neutron prompt gamma-ray activation analysis (PGAA) instrument was designed and built to replace the original PGAA system at the National Institute of Standards and Technology's Center for Neutron Research. The new PGAA instrument was constructed to achieve a reduction of the fast neutron beam component, a reduction of background gamma-radiation (including gamma-ray lines that directly interfere with element analyses, low-energy scattered gamma rays, and Compton scattered gamma rays), improvement in element sensitivities and limits of detection (LODs), and a simplified instrument set-up procedure. (orig.)

  16. Paul Scherrer Institute Scientific Report 2000. Volume III: Condensed Matter Research with Neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Schefer, Juerg; Castellazzi, Denise; Shea-Braun, Margit [eds.

    2001-07-01

    This year started with a highlight for the Swiss Spallation Neutron Source SINQ located at PSI: The thermal neutron flux exceeded the value of 10{sup 14} n cm{sup -2} s{sup 1} which may be considered as the critical limit for an advanced medium-flux neutron source. The excellent performance attracted a large number of external users to participate at the neutron scattering programme. The major part of this annual report gives an overview on the scientific activities of the staff members of the Laboratory of Neutron Scattering (jointly operated with the Swiss Federal Institute of Technology, ETH Zurich). The research topics covered diverse areas such as strongly correlated electron systems including high-temperature superconductors, low-dimensional and quantum magnetism, materials research on soft and hard matter including multilayers. Progress in 2000 in these topical areas as well as the activities of the Condensed Matter Theory Group, and the Group for Low Temperature Facilities, is described in this report. A list of scientific publications in 2000 is also provided.

  17. A CONCEPTUAL DESIGN OF NEUTRON COLLIMATOR IN THE THERMAL COLUMN OF KARTINI RESEARCH REACTOR FOR IN VITRO AND IN VIVO TEST OF BORON NEUTRON CAPTURE THERAPY

    Directory of Open Access Journals (Sweden)

    Nina Fauziah

    2015-03-01

    Full Text Available Studies were carried out to design a collimator which results in epithermal neutron beam for IN VITRO and IN VIVO of Boron Neutron Capture Therapy (BNCT at the Kartini research reactor by means of Monte Carlo N-Particle (MCNP codes. Reactor within 100 kW of thermal power was used as the neutron source. The design criteria were based on recommendation from the International Atomic Energy Agency (IAEA. All materials used were varied in size, according to the value of mean free path for each material. MCNP simulations indicated that by using 5 cm thick of Ni as collimator wall, 60 cm thick of Al as moderator, 15 cm thick of 60Ni as filter, 2 cm thick of Bi as γ-ray shielding, 3 cm thick of 6Li2CO3-polyethylene as beam delimiter, with 1 to 5 cm varied aperture size, epithermal neutron beam with maximum flux of 7.65 x 108 n.cm-2.s-1 could be produced. The beam has minimum fast neutron and γ-ray components of, respectively, 1.76 x 10-13 Gy.cm2.n-1 and 1.32 x 10-13 Gy.cm2.n-1, minimum thermal neutron per epithermal neutron ratio of 0.008, and maximum directionality of 0.73. It did not fully pass the IAEA’s criteria, since the epithermal neutron flux was below the recommended value, 1.0 x 109 n.cm-2.s-1. Nonetheless, it was still usable with epithermal neutron flux exceeding 5.0 x 108 n.cm-2.s-1. When it was assumed that the graphite inside the thermal column was not discharged but only the part which was going to be replaced by the collimator, the performance of the collimator became better within the positive effect from the surrounding graphite that the beam resulted passed all criteria with epithermal neutron flux up to 1.68 x 109 n.cm-2.s-1. Keywords: design, collimator, epithermal neutron beam, BNCT, MCNP, criteria   Telah dilakukan penelitian tentang desain kolimator yang menghasilkan radiasi netron epitermal untuk uji in vitro dan in vivo pada Boron Neutron Capture Therapy (BNCT di Reaktor Riset Kartini dengan menggunakan program Monte

  18. Awareness, Preference, Utilization, and Messaging Research for the Spallation Neutron Source and High Flux Isotope Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bryant, Rebecca [Bryant Research, LLC; Kszos, Lynn A [ORNL

    2011-03-01

    Oak Ridge National Laboratory (ORNL) offers the scientific community unique access to two types of world-class neutron sources at a single site - the Spallation Neutron Source (SNS) and the High Flux Isotope Reactor (HFIR). The 85-MW HFIR provides one of the highest steady-state neutron fluxes of any research reactor in the world, and the SNS is one of the world's most intense pulsed neutron beams. Management of these two resources is the responsibility of the Neutron Sciences Directorate (NScD). NScD commissioned this survey research to develop baseline information regarding awareness of and perceptions about neutron science. Specific areas of investigative interest include the following: (1) awareness levels among those in the scientific community about the two neutron sources that ORNL offers; (2) the level of understanding members of various scientific communities have regarding benefits that neutron scattering techniques offer; and (3) any perceptions that negatively impact utilization of the facilities. NScD leadership identified users of two light sources in North America - the Advanced Photon Source (APS) at Argonne National Laboratory and the National Synchrotron Light Source (NSLS) at Brookhaven National Laboratory - as key publics. Given the type of research in which these scientists engage, they would quite likely benefit from including the neutron techniques available at SNS and HFIR among their scientific investigation tools. The objective of the survey of users of APS, NSLS, SNS, and HFIR was to explore awareness of and perceptions regarding SNS and HFIR among those in selected scientific communities. Perceptions of SNS and FHIR will provide a foundation for strategic communication plan development and for developing key educational messages. The survey was conducted in two phases. The first phase included qualitative methods of (1) key stakeholder meetings; (2) online interviews with user administrators of APS and NSLS; and (3) one

  19. Accelerator-driven sub-critical research facility with low-enriched fuel in lead matrix: Neutron flux calculation

    Directory of Open Access Journals (Sweden)

    Avramović Ivana

    2007-01-01

    Full Text Available The H5B is a concept of an accelerator-driven sub-critical research facility (ADSRF being developed over the last couple of years at the Vinča Institute of Nuclear Sciences, Belgrade, Serbia. Using well-known computer codes, the MCNPX and MCNP, this paper deals with the results of a tar get study and neutron flux calculations in the sub-critical core. The neutron source is generated by an interaction of a proton or deuteron beam with the target placed inside the sub-critical core. The results of the total neutron flux density escaping the target and calculations of neutron yields for different target materials are also given here. Neutrons escaping the target volume with the group spectra (first step are used to specify a neutron source for further numerical simulations of the neutron flux density in the sub-critical core (second step. The results of the calculations of the neutron effective multiplication factor keff and neutron generation time L for the ADSRF model have also been presented. Neutron spectra calculations for an ADSRF with an uranium tar get (highest values of the neutron yield for the selected sub-critical core cells for both beams have also been presented in this paper.

  20. Neutron research on condensed matter: a study of the facilities and scientific opportunities in the United States

    Energy Technology Data Exchange (ETDEWEB)

    1977-01-01

    An in-depth review of the present status and future potential of the applications of low-energy neutron scattering to research in the condensed-matter sciences, including physics, chemistry, biology, and metallurgy is presented. The study shows that neutron scattering technology has proven to be of enormous importance to research in the above areas and especially to those of solid-state physics and chemistry. The main emphasis is on the scattering of low-energy neutrons by condensed matter. Since the same type of neutron source facilities can be used for the study of radiation damage, this related topic has also been included. (GHT)

  1. Research activities on structure materials of spallation neutron source at SINQ

    Energy Technology Data Exchange (ETDEWEB)

    Bauer, G.S.; Dai, Y. [Paul Scherrer Inst. (PSI), Villigen (Switzerland)

    1997-09-01

    With the growing interests on powerful spallation neutron sources, especially with liquid metal targets, and accelerator driven energy systems, spallation materials science and technology have been received wide attention. At SINQ, material research activities are focused on: a) liquid metal corrosion; b) radiation damage; and c) interaction of corrosion and radiation damage. (author) 1 fig., refs.

  2. Paul Scherrer Institute Scientific Report 1998. Volume III: Condensed Matter Research with Neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Schefer, Juerg; Castellazzi, Denise; Bucher-Zimmermann, Claudia [eds.

    1999-09-01

    As a consequence of a major reorganisation at PSI, a new department has been formed with the groups focussing on research of condensed matter. The activities of the Laboratory of Neutron Scattering (jointly operated with the Swiss Federal Institute of Technology, ETH Zuerich), the Condensed Matter Theory Group, and the Group for Low Temperature Facilities, are described in this annual report figs., tabs., refs.

  3. Neutron spectrometry and dosimetry study at two research nuclear reactors using Bonner sphere spectrometer (BSS), rotational spectrometer (ROSPEC) and cylindrical nested neutron spectrometer (NNS).

    Science.gov (United States)

    Atanackovic, J; Matysiak, W; Hakmana Witharana, S S; Aslam, I; Dubeau, J; Waker, A J

    2013-01-01

    Neutron spectrometry and subsequent dosimetry measurements were undertaken at the McMaster Nuclear Reactor (MNR) and AECL Chalk River National Research Universal (NRU) Reactor. The instruments used were a Bonner sphere spectrometer (BSS), a cylindrical nested neutron spectrometer (NNS) and a commercially available rotational proton recoil spectrometer. The purposes of these measurements were to: (1) compare the results obtained by three different neutron measuring instruments and (2) quantify neutron fields of interest. The results showed vastly different neutron spectral shapes for the two different reactors. This is not surprising, considering the type of the reactors and the locations where the measurements were performed. MNR is a heavily shielded light water moderated reactor, while NRU is a heavy water moderated reactor. The measurements at MNR were taken at the base of the reactor pool, where a large amount of water and concrete shielding is present, while measurements at NRU were taken at the top of the reactor (TOR) plate, where there is only heavy water and steel between the reactor core and the measuring instrument. As a result, a large component of the thermal neutron fluence was measured at MNR, while a negligible amount of thermal neutrons was measured at NRU. The neutron ambient dose rates at NRU TOR were measured to be between 0.03 and 0.06 mSv h⁻¹, while at MNR, these values were between 0.07 and 2.8 mSv h⁻¹ inside the beam port and <0.2 mSv h⁻¹ between two operating beam ports. The conservative uncertainty of these values is 15 %. The conservative uncertainty of the measured integral neutron fluence is 5 %. It was also found that BSS over-responded slightly due to a non-calibrated response matrix.

  4. Neutron Calibration Facilities of the Irsn Research Laboratory in External Dosimetry

    Science.gov (United States)

    van Ryckeghem, L.; Lacoste, V.; Pelcot, G.; Pochat, J.-L.

    2003-06-01

    The Laboratory of Studies and Research in External Dosimetry (LRDE) associated to the National Office for Metrology (BNM) has to maintain the traceability of the French references for the calibration of neutron dosimeters. The LRDE owns a facility which provides some conventional neutron spectra from sources of 241Am-Be, 252Cf, and (252Cf + D2O)/Cd recommended by ISO standards. These ISO spectra appear not appropriated to simulate some kind of workplace spectra. In order to have similar radiation conditions between the calibration and the use of the device, LRDE has built facilities ("SIGMA" and "CANEL") providing some neutron spectra from thermal to fast energies reproducing those encountered in workplaces.

  5. The Modular Network Organization in Scientific Research and Production of Weapons and Equipment and Its Construction%武器装备科研生产模块化网络组织模式及其构建

    Institute of Scientific and Technical Information of China (English)

    杜人淮; 熊飞

    2011-01-01

    武器装备科研生产模块化网络组织是基于模块化分工的新型组织模式.在推动武器装备科研生产发展方面,模块化网络组织模式具有速度、创新和协同等优势.为构建我国的武器装备科研生产模块化网络组织,需把握构建武器装备科研生产模块化网络组织的基础,明确构建武器装备科研生产模块化网络组织的程序,制定加快构建我国武器装备科研生产模块化网络组织的政策措施.%The modular network organization in scientific research and production of weapons and equipment is based on the new organizational mode in modular division. The modular network organization have advantages of speed, innovation, collaborative and etc. In promoting development of scientific research and production of weapons and equipment. For the construction of Chinese characteristics modular network organization in scientific research and production of weapons and equipment, it needs to grasp constructing base in the modular network organization in scientific research and production of weapons and equipment, clear the constructing program in the modular network organization in scientific research and production of weapons and equipment, and formulates constructing policy measures in the modular network organization in scientific research and production of weapons and equipment.

  6. Basic Physics Data: Measurement of Neutron Multiplicity from Induced Fission

    Energy Technology Data Exchange (ETDEWEB)

    Pozzi, Sara [Univ. of Michigan, Ann Arbor, MI (United States); Haight, Robert [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-05-04

    From October 1 to October 17 a team of researchers from UM visited the LANSCE facility for an experiment during beam-time allotted from October 4 to October 17. A total of 24 detectors were used at LANSCE including liquid organic scintillation detectors (EJ-309), NaI scintillation detectors, and Li-6 enriched glass detectors. It is a double time-offlight (TOF) measurement using spallation neutrons generated by a target bombarded with pulsed high-energy protons. The neutrons travel to an LLNL-manufactured parallel plate avalanche chamber (PPAC) loaded with thin U-235 foils in which fission events are induced. The generated fission neutrons and photons are then detected in a detector array designed and built at UM and shipped to LANSCE. Preparations were made at UM, where setup and proposed detectors were tested. The UM equipment was then shipped to LANSCE for use at the 15L beam of the weapons neutron research (WNR) facility.

  7. Physics design for the Brookhaven Medical Research Reactor epithermal neutron source.

    Science.gov (United States)

    Wheeler, F J; Parsons, D K; Nigg, D W; Wessol, D E; Miller, L G; Fairchild, R G

    1990-01-01

    A collaborative effort by researchers at the Idaho National Engineering Laboratory and the Brookhaven National Laboratory has resulted in the design and implementation of an epithermal-neutron source at the Brookhaven Medical Research Reactor (BMRR). Large aluminum containers, filled with aluminum oxide tiles and aluminum spacers, were tailored to pre-existing compartments on the animal side of the reactor facility. A layer of cadmium was used to minimize the thermal-neutron component. Additional bismuth was added to the pre-existing bismuth shield to minimize the gamma component of the beam. Lead was also added to reduce gamma streaming around the bismuth. The physics design methods are outlined in this paper. Information available to date shows close agreement between calculated and measured beam parameters. The neutron spectrum is predominantly in the intermediate energy range (0.5 eV - 10 keV). The peak flux intensity is 6.4E + 12 n/(m2.s.MW) at the center of the beam on the outer surface of the final gamma shield. The corresponding neutron current is 3.8E + 12 n/(m2.s.MW). Presently, the core operates at a maximum of 3 MW. The fast-neutron KERMA is 3.6E-15 cGy/(n/m2) and the gamma KERMA is 5.0E-16 cGY/(n/m2) for the unperturbed beam. The neutron intensity falls off rapidly with distance from the outer shield and the thermal flux realized in phantom or tissue is strongly dependent on the beam-delimiter and target geometry.

  8. Research on Inferring ELECTRE-III’s Parameters with Fuzzy information and A Case on Naval Gun Weapon System Integration

    Directory of Open Access Journals (Sweden)

    Sun Shi Yan

    2016-01-01

    Full Text Available Multiple attributes decision making (MADM method is an important measure for system integration. Robustness analysis on MADM is a hotspot in these years which wins academe’s great attention, and is supposed to be an effective way when countering imperfect information. Setting parameters in ELECTRE-III’s is a vital and difficult step. In this paper, a method of inferring ELECTRE-III’s parameters with fuzzy information based on robustness analysis is presented. First, ELECTRE-III is transformed into a continuous smooth function of each parameter vector. Then, robustness analysis structure and a parameters inferring algorithm are provided by maximizing robustness margin based on mathematics programming. Moreover, how to resolve the programming problem is also discussed. At last, a illustrative example of Naval Gun Weapon System Integration is put forward.

  9. Reality theory: A means to control the public`s fear of chemical weapons use. Research report

    Energy Technology Data Exchange (ETDEWEB)

    Pate, B.E.

    1997-04-01

    On 20 March 1995 terrorists released the chemical nerve agent sarin into the Tokyo subway system, killing 10 commuters and changing the public`s attitude about the most basic aspect of their lives: the air they breathe and the daily ritual of their commute to work. This is the new threat the United States must face: terrorism and its attack on the will of the people forcing governments to yield to the terrorists` position. Yet there is a different public response in warfare compared with a peacetime terrorist attack. This paper examines the psychological response of people in wartime and applies this description to chemical weapons use in war and in peace. The public`s response can be predicted if one uses reality theory, a concept leaders can use to mitigate responses that would prevent the execution of national strategy.

  10. Comparison of polystyrene scintillator fiber array and monolithic polystyrene for neutron imaging and radiography

    Science.gov (United States)

    Simpson, R.; Cutler, T. E.; Danly, C. R.; Espy, M. A.; Goglio, J. H.; Hunter, J. F.; Madden, A. C.; Mayo, D. R.; Merrill, F. E.; Nelson, R. O.; Swift, A. L.; Wilde, C. H.; Zocco, T. G.

    2016-11-01

    The neutron imaging diagnostic at the National Ignition Facility has been operating since 2011 generating neutron images of deuterium-tritium (DT) implosions at peak compression. The current design features a scintillating fiber array, which allows for high imaging resolution to discern small-scale structure within the implosion. In recent years, it has become clear that additional neutron imaging systems need to be constructed in order to provide 3D reconstructions of the DT source and these additional views need to be on a shorter line of sight. As a result, there has been increased effort to identify new image collection techniques that improve upon imaging resolution for these next generation neutron imaging systems, such as monolithic deuterated scintillators. This work details measurements performed at the Weapons Neutron Research Facility at Los Alamos National Laboratory that compares the radiographic abilities of the fiber scintillator with a monolithic scintillator, which may be featured in a future short line of sight neutron imaging systems.

  11. Nonstrategic Nuclear Weapons

    Science.gov (United States)

    2014-01-03

    William Potter , and Nikolai Sokov, Reducing and Regulating Tactical (Nonstrategic) Nuclear Weapons in Europe, The James Martin Center For...See William C. Potter and Nikolai Sokov, “Nuclear Weapons that People Forget,” International Herald Tribune, May 31, 2000. 87 Sam Nunn, Igor...their security.97 94 Kent Harris , “NATO Allies Want U.S. Nuclear Weapons out of Europe

  12. The medical-irradiation characteristics for neutron capture therapy at the Heavy Water Neutron Irradiation Facility of Kyoto University Research Reactor.

    Science.gov (United States)

    Sakurai, Yoshinori; Kobayashi, Tooru

    2002-10-01

    At the Heavy Water Neutron Irradiation Facility of the Kyoto University Research Reactor, the mix irradiation of thermal and epi-thermal neutrons, and the solo irradiation of epi-thermal neutrons are available additionally to the thermal neutron irradiation, and then the neutron capture therapy (NCT) at this facility became more flexible, after the update in 1996. The estimation of the depth dose distributions in NCT clinical irradiation, were performed for the standard irradiation modes of thermal, mixed and epi-thermal neutrons, from the both sides of experiment and calculation. On the assumption that the 10B concentration in tumor part was 40 ppm and the ratio of tumor to normal tissue was 3.5, the advantage depth were estimated to 5.4, 6.0, and 8.0, for the respective standard irradiation modes. It was confirmed that the various irradiation conditions can be selected according to the target-volume conditions, such as size, depth, etc. Besides, in the viewpoint of the radiation shielding for patient, it was confirmed that the whole-body exposure is effectively reduced by the new clinical collimators, compared with the old one.

  13. 一种航空武器数据链MAC协议设计与研究%Design and Research of Aeronautical Weapon Data Link MAC Protocol

    Institute of Scientific and Technical Information of China (English)

    段荣; 吕娜; 王翔

    2011-01-01

    MAC协议是航空武器数据链组网通信的重要技术,网络的性能依赖于所采用的多址接入协议,也是航空武器数据链研究的难点之一.固定分配、竞争和预约三大类MAC协议各有优缺点以及适应场景,需要根据应用需求设计对应的多址接入协议,以满足通信网络的战术和技术性能指标.在分析数字化战场通信网络——战术数据链组网通信应用的主要MAC协议的基础上,结合航空武器数据链的通信特点和体系结构,提出一种基于固定分配TDMA的航空武器数据链MAC协议—ODTCFMA协议,并对协议的时延性能进行了仿真和分析.分析结果表明,该协议能够同时满足编队战术协同和武器制导的低时延要求,对航空武器数据链的研究具有一定的借鉴意义.%MAC protocol is an important technology in communication network of aeronautical weapon data link, Depending on the used MAC protocol, network performance is also one of the main technical difficulties in the research of AWDL. The three kinds of MAC protocols, fixed allocation, reservation and competition, have advantages, disadvantages and adaption scene. The corresponding multiple access protocol is designed based on application requirements to meet the requirements of the tactical and technical communication network performance. The digital battlefield communications network MAC protocol is analyzed based on the combined characteristics and architecture of AWDL, and a TDM A based on fixed allocation MAC of aeronautical weapon data link;ODTCFMA protocol is proposed, then the protocol performance is simulated and analyzed. The analysis shows the MAC meets the requirements of both the for-mational tactical cooperation and the weapon guidance of low delay, which has reference significance for the research of AWDL.

  14. Biophysics and medical effects of enhanced radiation weapons.

    Science.gov (United States)

    Reeves, Glen I

    2012-08-01

    Enhanced radiation weapons (ERW) are fission-fusion devices where the massive numbers of neutrons generated during the fusion process are intentionally allowed to escape rather than be confined to increase yield (and fallout products). As a result, the energy partition of the weapon output shifts from blast and thermal energies toward prompt radiation. The neutron/gamma output ratio is also increased. Neutrons emitted from ERW are of higher energy than the Eave of neutrons from fission weapons. These factors affect the patterns of injury distribution; delay wound healing in combined injuries; reduce the therapeutic efficacy of medical countermeasures; and increase the dose to radiation-only casualties, thus potentiating the likelihood of encountering radiation-induced incapacitation. The risk of radiation-induced carcinogenesis is also increased. Radiation exposure to first responders from activation products is increased over that expected from a fission weapon of similar yield. However, the zone of dangerous fallout is significantly reduced in area. At least four nations have developed the potential to produce such weapons. Although the probability of detonation of an ERW in the near future is very small, it is nonzero, and clinicians and medical planners should be aware of the medical effects of ERW.

  15. Optimization of the epithermal neutron beam for Boron Neutron Capture Therapy at the Brookhaven Medical Research Reactor.

    Science.gov (United States)

    Hu, Jih-Perng; Reciniello, Richard N; Holden, Norman E

    2004-05-01

    The use of epithermal neutron beam in clinical trials of Boron Neutron Capture Therapy for patients with malignant brain tumors had been carried out for half a decade at the Brookhaven's Medical Reactor. The decision to permanently close this reactor in 2000 cut short the efforts to implement a new conceptual design to optimize this beam in preparation for use with possible new BNCT protocols. Details of the conceptual design to produce a highly intensified and focused neutron beam with less gamma and neutron contamination in tissues are presented here for their potential applicability to other reactor facilities. Neutron-photon coupled Monte Carlo calculations were used to predict the flux, current, heating, and absorbed dose produced by the proposed design. The results were benchmarked by the dose rate and flux measurements taken at the facility then in use.

  16. Neutron spectrometric methods for core inventory verification in research reactors

    CERN Document Server

    Ellinger, A; Hansen, W; Knorr, J; Schneider, R

    2002-01-01

    In consequence of the Non-Proliferation Treaty safeguards, inspections are periodically made in nuclear facilities by the IAEA and the EURATOM Safeguards Directorate. The inspection methods are permanently improved. Therefore, the Core Inventory Verification method is being developed as an indirect method for the verification of the core inventory and to check the declared operation of research reactors.

  17. Non-classical neutron beams for fundamental and solid state research

    Indian Academy of Sciences (India)

    H Rauch

    2008-10-01

    The curious dual nature of the neutron, sometimes a particle, sometimes a wave, is wonderfully manifested in the various non-local interference and quantum contextuality effects observed in neutron interferometry. Non-classical states may become useful for novel fundamental and solid state research. Here we discuss unavoidable quantum losses as they appear in neutron phase-echo and spin rotation experiments and we show how entanglement effects in a single particle system demonstrate quantum contextuality. In all cases of interactions, parasitic beams are produced which cannot be recombined completely with the original beam. This means that a complete reconstruction of the original state would, in principle, be impossible which causes a kind of intrinsic irreversibility. Even small interaction potentials can have huge effects when they are applied in quantum Zeno-like experiments. Recently, it has been shown that an entanglement between external and internal degrees of freedom exists even in single particle systems. This contextuality phenomenon also shows that a quantum system carries much more information than usually extracted. The path towards advanced neutron quantum optics will be discussed.

  18. Present status of neutron beam facilities at the research reactor, HANARO, and its future prospect

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang-Hee; Kang, Young-Hwan; Kuk, Il-Hiun [Korea Atomic Energy Research Institute, Taejon (Korea)

    2001-03-01

    Korea has been operating its new research reactor, HANARO, since its first criticality in 1995. It is an open-tank-in-pool type reactor using LEU fuel with thermal neutron flux of 2 x 10{sup 14} nominally at the nose in the D{sub 2}O reflector having 7 horizontal beam ports and a provision of vertical hole for cold neutron source installation. KAERI has pursued an extensive instrument development program since 1992 by the support of the nuclear long-term development program of the government and there are now 4 working instruments. A high resolution powder diffractometer and a neutron radiography facility has been operational since late 1997 and 1996, respectively. A four-circle diffractometer has been fully working since mid 1999 and a small angle neutron spectrometer is just under commissioning phase. With the development of linear position sensitive detector with delay-line readout electronics, we have developed a residual stress instrument as an optional machine to the HRPD for last two years. Around early 1998 informal users program started with friendly users and it became a formal users support program by the ministry of science and technology. Short description for peer group formation and users activities is given. (author)

  19. Design of a high-flux epithermal neutron beam using 235U fission plates at the Brookhaven Medical Research Reactor.

    Science.gov (United States)

    Liu, H B; Brugger, R M; Rorer, D C; Tichler, P R; Hu, J P

    1994-10-01

    Beams of epithermal neutrons are being used in the development of boron neutron capture therapy for cancer. This report describes a design study in which 235U fission plates and moderators are used to produce an epithermal neutron beam with higher intensity and better quality than the beam currently in use at the Brookhaven Medical Research Reactor (BMRR). Monte Carlo calculations are used to predict the neutron and gamma fluxes and absorbed doses produced by the proposed design. Neutron flux measurements at the present epithermal treatment facility (ETF) were made to verify and compare with the computed results where feasible. The calculations indicate that an epithermal neutron beam produced by a fission-plate converter could have an epithermal neutron intensity of 1.2 x 10(10) n/cm2.s and a fast neutron dose per epithermal neutron of 2.8 x 10(-11) cGy.cm2/nepi plus being forward directed. This beam would be built into the beam shutter of the ETF at the BMRR. The feasibility of remodeling the facility is discussed.

  20. NCTPlan application for neutron capture therapy dosimetric planning at MEPhI nuclear research reactor.

    Science.gov (United States)

    Elyutina, A S; Kiger, W S; Portnov, A A

    2011-12-01

    The results of modeling of two therapeutic beams HEC-1 and HEC-4 at the NRNU "MEPhI" research nuclear reactor exploitable for preclinical treatments are reported. The exact models of the beams are constructed as an input to the NCTPlan code used for planning Neutron Capture Therapy (NCT) procedure. The computations are purposed to improve the accuracy of prediction of a dose absorbed in tissue with the account of all components of radiation.

  1. A simple setup for neutron tomography at the Portuguese Nuclear Research Reactor

    CERN Document Server

    Pereira, M A Stanojev; Pugliesi, R

    2012-01-01

    A simple setup for neutron radiography and tomography was recently installed at the Portuguese Research Reactor. The objective of this work was to determine the operational characteristics of the installed setup, namely the irradiation time to obtain the best dynamic range for individual images and the spatial resolution. The performance of the equipment was demonstrated by imaging a fragment of a 17th century decorative tile.

  2. Progress report on neutron activation analysis at Dalat Nuclear Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Tuan, Nguyen Ngoc [Nuclear Research Institute, Dalat (Viet Nam)

    2003-03-01

    Neutron Activation Analysis (NAA) is one of most powerful techniques for the simultaneous multi-elements analysis. This technique has been studied and applied to analyze major, minor and trace elements in Geological, Biological and Environmental samples at Dalat Nuclear Research Reactor. At the sixth Workshop, February 8-11, 1999, Yojakarta, Indonesia we had a report on Current Status of Neutron Activation Analysis using Dalat Nuclear Research Reactor. Another report on Neutron Activation Analysis at the Dalat Nuclear Research Reactor also was presented at the seventh Workshop in Taejon, Korea from November 20-24, 2000. So in this report, we would like to present the results obtained of the application of NAA at NRI for one year as follows: (1) Determination of the concentrations of noble, rare earth, uranium, thorium and other elements in Geological samples according to requirement of clients particularly the geologists, who want to find out the mineral resources. (2) The analysis of concentration of radionuclides and nutrient elements in foodstuffs to attend the program on Asian Reference Man. (3) The evaluation of the contents of trace elements in crude oil and basement rock samples to determine original source of the oil. (4) Determination of the elemental composition of airborne particle in the Ho Chi Minh City for studying air pollution. The analytical data of standard reference material, toxic elements and natural radionuclides in seawater are also presented. (author)

  3. JPRS Report: Proliferation Issues. Russian Federation: Foreign Intelligence Service Report. A New Challenge After the Cold War: Proliferation of Weapons of Mass Destruction

    Science.gov (United States)

    2016-03-24

    properties of fuel, neutron beam and also the skilled personnel and material resources experiments, the improvement of nuclear reactor needed for the...positive development. 600,000 tonnes. There are plants for the manufacture of reactor fuel. In the Area of Chemical and Biological Weapons Nuclear activity...spokesman delivered the following statement in early 1993: "The 3. The 5 megawatt research nuclear reactor in Yongbyon. DPRK has never had any chemical

  4. Paul Scherrer Institut Scientific Report 2001. Volume III: Condensed Matter Research with Neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Schefer, J.; Castellazzi, D.; Shea-Braun, M. (eds.)

    2002-03-01

    The SINQ-facility stopped operation at the end of the year 2001 for the scheduled shut down. By that time the spallation target of the 'Cannelloni'-type (D{sub 2}O-cooled steel pins filled with lead) had received a total charge of more then 10 Ah at an average proton current higher than 1 mA. Thereby nearly 4 mols of neutrons had been released from this target. The two operational years with this target delivered the neutrons for about 300 experiments. During this operational period not one single interrupt caused by the spallation target has been recorded -indeed a convincing evidence for the reliability of this system. The probes inserted into the target and some of its parts will now soon be available to the materials scientists for careful investigation. SINQ as a continuous spallation neutron source was considered to be a 'high risk' project. Furthermore it was often accompanied with the suspicion to represent the 'worst of two worlds' - meaning that this facility would suffer from the disadvantages but not benefit from the advantage of a spallation neutron source - the pulse structure. According to our operational experience these fears are not justified provided the various concerns have been properly taken into consideration during design and construction. This report testifies what can be achieved at a continuous spallation neutron source. We believe that these research activities compare well with those from a beam-tube reactor of medium flux. A list of scientific publications in 2000 is also provided.

  5. Assessment of the reliability of neutronic parameters of Ghana Research Reactor-1 control systems

    Energy Technology Data Exchange (ETDEWEB)

    Amponsah-Abu, E.O., E-mail: edwardabu2002@yahoo.com [National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG. 80, Legon-Accra (Ghana); Gbadago, J.K. [National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG. 80, Legon-Accra (Ghana); Akaho, E.H.K.; Akoto-Bamford, S. [School of Nuclear and Allied Sciences, University of Ghana (Ghana); Gyamfi, K.; Asamoah, M.; Baidoo, I.K. [National Nuclear Research Institute, Ghana Atomic Energy Commission, P.O. Box LG. 80, Legon-Accra (Ghana)

    2015-01-15

    Highlights: • The reliability of neutronics parameters of GHARR-I was assessed. • The reactor was operated at different power levels of 5–30 kW. • The pre-set flux was compared with the flux in the inner irradiation site. • Decrease in the core reactivity caused difference in flux on the meters and site. • Neutronic parameters become reliable when operation is done at reactivity of 4 mk. - Abstract: The Ghana Research Reactor-1 (GHARR-1) has been in operation for the past 19 years using a Micro-Computer Closed Loop System (MCCLS) and Control Console (CC) as the control systems. The two control systems were each coupled separately with a micro-fission chamber to measure the current pulses of the neutron fluxes in the core at excess reactivity of 4 mk. The MCCLS and CC meter readings at a pre-set flux of 5.0 × 10{sup 11} n/cm{sup 2} s were 6.42 × 10{sup 11} n/cm{sup 2} s and 5.0 × 10{sup 11} n/cm{sup 2} s respectively. Due to ageing and obsolescence, the MCCLS and some components that control the sensitivity and the reading mechanism of the meters were replaced. One of the fission chambers was also removed and the two control systems were coupled to one fission chamber. The reliability of the neutronic parameters of the control systems was assessed after the replacement. The results showed that when the reactor is operated at different power levels of 5–30 kW using one micro-fission chamber, the pre-set neutron fluxes at the control systems is 1.6 times the neutron fluxes obtained using a flux monitor at the inner irradiation site two of the reactor. The average percentage deviations of the obtained fluxes from the pre-set values of 1.67 × 10{sup 11}–1.0 × 10{sup 12} n/cm{sup 2} s were 36.5%. This compares very well with the decrease in core excess reactivity of 36.3% of the nominal value of 4 mk, after operating the reactor at critical neutron flux of 1.0 × 10{sup 9} n/cm{sup 2} s.

  6. Optimization of the Epithermal Neutron Beam for Boron Neutron Capture Therapy at the Brookhaven Medical Research Reactor

    Science.gov (United States)

    Hu, Jih-Perng; Rorer, David C.; Reciniello, Richard N.; Holden, Norman E.

    2003-06-01

    Clinical trials of Boron Neutron Capture Therapy for patients with malignant brain tumor had been carried out for half a decade, using an epithermal neutron beam at the Brookhaven Medical Reactor. The decision to permanently close this reactor in 2000 cut short the efforts to implement a new conceptual design to optimize this beam in preparation for use with possible new protocols. Details of the conceptual design to produce a higher intensity, more forward-directed neutron beam with less contamination from gamma rays, fast and thermal neutrons are presented here for their potential applicability to other reactor facilities. Monte Carlo calculations were used to predict the flux and absorbed dose produced by the proposed design. The results were benchmarked by the dose rate and flux measurements taken at the facility then in use.

  7. High Brightness Neutron Source for Radiography

    Energy Technology Data Exchange (ETDEWEB)

    Cremer, J. T.; Piestrup, Melvin, A.; Gary, Charles, K.; Harris, Jack, L. Williams, David, J.; Jones, Glenn, E.; Vainionpaa, J. , H.; Fuller, Michael, J.; Rothbart, George, H.; Kwan, J., W.; Ludewigt, B., A.; Gough, R.., A..; Reijonen, Jani; Leung, Ka-Ngo

    2008-12-08

    of yield of two orders of magnitude. The first fast neutron radiographic images were obtained using neutron cameras and a new fast neutron generator. These early images demonstrated the feasibility of using fast neutrons for imaging and penetrating thick objects of high density and imaging. Fast neutrons can be used to image low atomic number materials (e.g. plastics, explosives, lubricants and ceramics) that are shielded by high density materials (e.g. lead, tungsten and uranium). Fast neutron radiography could be used as a means to screen weapons for flaws and chemical stability. X-ray radiography can not easily do this. Fast neutron imaging is technically difficult and, consequently, a completely undeveloped market. Two of the generators were designed to have small source size and high brightness, ideal for fast-neutron imaging. With these generators we successfully used two fast neutron cameras: one developed by us, and another developed by a collaborator, Commonwealth Scientific and Industrial Research Organization, CSIRO. We have successfully used these cameras to obtain low resolution images of various objects such as pipe fittings filled with water and other mechanical objects. Higher resolution and contrast images are expected by decreasing the source size and increasing generator yield.

  8. Paul Scherrer Institute Scientific Report 1999. Volume III: Condensed Matter Research with Neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Schefer, Juerg; Castellazzi, Denise; Shea-Braun, Margit [eds.

    2000-07-01

    This year was a period of consolidation of the operation at the spallation source of PSI and its scientific exploitation at an increasing number of instruments. The major part of this annual report gives an overview of the research activities in the Laboratory of Neutron Scattering (jointly operated with the Swiss Federal Institute of Technology, ETH Zurich) of our department, mainly emphasizing highly correlated electron systems and the investigation of magnetism. The activities on multilayers and surfaces, a basic research object by itself, is however also to a large extent motivated by the development of optical components for neutron- and X-ray instrumentation. While most of the solid-state work has been done with neutrons, some contributions deal with other probes, like muons and synchrotron light, exploiting the unique possibilities at PSI, to take advantage of the complementary nature of the different probes. Progress in 1999 in these topical areas as well as the activities of the Condensed Matter Theory Group, and the Group for Low Temperature Facilities, is described in this report. A list of scientific publications in 1999 is also provided.

  9. Design of Real-time Neutron Radiography at China Advanced Research Reactor

    Science.gov (United States)

    He, Linfeng; Han, Songbai; Wang, Hongli; Hao, Lijie; Wu, Meimei; Wei, Guohai; Wang, Yu; Liu, Yuntao; Sun, Kai; Chen, Dongfeng

    A real-time detector system for neutron radiography based on CMOS camera has been designed for the thermal neutron imaging facility under construction at China Advanced Research Reactor (CARR). This system is equipped with a new scientific CMOS camera with 5.5 million pixels and speed up to 100 fps at full frame. The readout noise is below 2.4 e/pixel. It is capable of providing images with much higher resolution and sensitivity at high frame rate. With optimized optical design and custom-built lens, the capture of quantitative information may be greatly enhanced. The maximum photon received by detector is calculated to be 2.1 × 103/pixel, while the camera resolution is 0.2 mm at 30 fps according to the expected flux (5 × 107 n/cm2/s) at the sample position.

  10. Inspection of domestic nuclear fuel rods using neutron radiography at the Tehran research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dastjerdi, Mohammad Hosein Choopan; Khalafi, Hossein; Kasesaz, Yaser [Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of); Movafeghi, Amir

    2016-11-01

    Three unused domestic fuel rods were investigated qualitatively and quantitatively by means of thermal neutron radiography. The neutron radiography tests were performed by the image plate method at Tehran research reactor in order to check the fuel properties. The pellets of these three fuel rods contained three different U-235 enrichments and different sizes that were filled into a zircalloy tube. In the qualitative investigations, the difference in size and enrichment between the pellets and the gaps between them were obviously recognized in the image of the fuel rods. In the quantitative investigations, data of the pellets compositions, their sizes (lengths and diameters) and the gaps between them were extracted from obtained images. It was found that the measured data and the manufacturer's specifications are in good agreement.

  11. Screening of Maritime Containers to Intercept Weapons of Mass Destruction

    Energy Technology Data Exchange (ETDEWEB)

    Manatt, D R; Sleaford, B; Schaffer, T; Accatino, M R; Slaughter, D; Mauger, J; Newmark, R; Prussin, S; Luke, J; Frank, M; Bernstein, A; Alford, O; Mattesich, G; Stengel, J; Hall, J; Descalle, M A; Wolford, J; Hall, H; Loshak, A; Sale, K; Trombino, D; Dougan, A D; Pohl, B; Dietrich, D; Weirup, D; Walling, R; Rowland, M; Johnson, D; Hagmann, C; Hankins, D

    2004-02-18

    The goal of our research was to address the problem of detection of weapons of mass destruction (WMD) materials within containers in common use on commercial cargo trafficking. LLNL has created an experimental test bed for researching potential solutions using (among other techniques) active interrogation with neutrons. Experiments and computational modeling were used to determine the effectiveness of the technique. Chemical weapons materials and high explosives can be detected using neutron activation and simple geometries with little or no intervening material. However in a loaded container there will be nuisance alarms from conflicting signatures resulting from the presence of material between the target and the detector (and the interrogation source). Identifying some elements may require long counting times because of the increased background. We performed some simple signature measurements and simulations of gamma-ray spectra from several chemical simulants. We identified areas where the nuclear data was inadequate to perform detailed computations. We concentrated on the detection of SNM in cargo containers, which will be emphasized here. The goal of the work reported here is to develop a concept for an active neutron interrogation system that can detect small targets of SNM contraband in cargo containers, roughly 5 kg HEU or 1 kg Pu, even when well shielded by a thick cargo. It is essential that the concept be reliable and have low false-positive and false-negative error rates. It also must be rapid to avoid interruption of commerce, completing the analysis in minutes. A potentially viable concept for cargo interrogation has been developed and its components have been evaluated experimentally. A new radiation signature unique to SNM has been identified that utilizes high-energy, fission-product gamma rays. That signature due to {gamma}-radiation in the range 3-6 MeV is distinct from normal background radioactivity that does not extend above 2.6 MeV. It

  12. Fusion neutronics

    CERN Document Server

    Wu, Yican

    2017-01-01

    This book provides a systematic and comprehensive introduction to fusion neutronics, covering all key topics from the fundamental theories and methodologies, as well as a wide range of fusion system designs and experiments. It is the first-ever book focusing on the subject of fusion neutronics research. Compared with other nuclear devices such as fission reactors and accelerators, fusion systems are normally characterized by their complex geometry and nuclear physics, which entail new challenges for neutronics such as complicated modeling, deep penetration, low simulation efficiency, multi-physics coupling, etc. The book focuses on the neutronics characteristics of fusion systems and introduces a series of theories and methodologies that were developed to address the challenges of fusion neutronics, and which have since been widely applied all over the world. Further, it introduces readers to neutronics design’s unique principles and procedures, experimental methodologies and technologies for fusion systems...

  13. Development of a new software tool, based on ANN technology, in neutron spectrometry and dosimetry research

    Energy Technology Data Exchange (ETDEWEB)

    Ortiz R, J.M.; Martinez B, M.R.; Vega C, H.R. [Universidad Autonoma de Zacatecas, Av. Ramon Lopez Velarde 801, A.P. 336, 98000 Zacatecas (Mexico)

    2007-07-01

    Artificial Intelligence is a branch of study which enhances the capability of computers by giving them human-like intelligence. The brain architecture has been extensively studied and attempts have been made to emulate it as in the Artificial Neural Network technology. A large variety of neural network architectures have been developed and they have gained wide-spread popularity over the last few decades. Their application is considered as a substitute for many classical techniques that have been used for many years, as in the case of neutron spectrometry and dosimetry research areas. In previous works, a new approach called Robust Design of Artificial Neural network was applied to build an ANN topology capable to solve the neutron spectrometry and dosimetry problems within the Mat lab programming environment. In this work, the knowledge stored at Mat lab ANN's synaptic weights was extracted in order to develop for first time a customized software application based on ANN technology, which is proposed to be used in the neutron spectrometry and simultaneous dosimetry fields. (Author)

  14. A new small-angle neutron scattering spectrometer at China Mianyang research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Peng, Mei, E-mail: pm740509@163.com; Sun, Liangwei; Chen, Liang; Sun, Guangai; Chen, Bo; Xie, Chaomei; Xia, Qingzhong; Yan, Guanyun; Tian, Qiang; Huang, Chaoqiang; Pang, Beibei; Zhang, Ying; Wang, Yun; Liu, Yaoguang; Kang, Wu; Gong, Jian

    2016-02-21

    A new pinhole small-angle neutron scattering (SANS) spectrometer, installed at the cold neutron source of the 20 MW China Mianyang Research Reactor (CMRR) in the Institute of Nuclear Physics and Chemistry, China Academy of Engineering Physics, has been put into use since 2014. The spectrometer is equipped with a multi-blade mechanical velocity selector, a multi-beam collimation system, and a two-dimensional He-3 position sensitive neutron detector. The q-range of the spectrometer covers from 0.01 nm{sup −1} to 5.0 nm{sup −1}. In this paper, the design and characteristics of the SANS spectrometer are described. The q-resolution calculations, together with calibration measurements of silver behenate and a dispersion of nearly monodisperse poly-methyl-methacrylate nanoparticles indicate that our SANS spectrometer has a good performance and is now in routine service. - Highlights: • A new SANS spectrometer has been put into use since 2014 in China. • One MBR selector possesses a higher resolution compared with traditional selector is used. • The spectrometer has a good performance and is now in routinely service.

  15. Virtual nuclear weapons

    Energy Technology Data Exchange (ETDEWEB)

    Pilat, J.F.

    1997-08-01

    The term virtual nuclear weapons proliferation and arsenals, as opposed to actual weapons and arsenals, has entered in recent years the American lexicon of nuclear strategy, arms control, and nonproliferation. While the term seems to have an intuitive appeal, largely due to its cyberspace imagery, its current use is still vague and loose. The author believes, however, that if the term is clearly delineated, it might offer a promising approach to conceptualizing certain current problems of proliferation. The first use is in a reference to an old problem that has resurfaced recently: the problem of growing availability of weapon-usable nuclear materials in civilian nuclear programs along with materials made `excess` to defense needs by current arms reduction and dismantlement. It is argued that the availability of these vast materials, either by declared nuclear-weapon states or by technologically advanced nonweapon states, makes it possible for those states to rapidly assemble and deploy nuclear weapons. The second use has quite a different set of connotations. It is derived conceptually from the imagery of computer-generated reality. In this use, one thinks of virtual proliferation and arsenals not in terms of the physical hardware required to make the bomb but rather in terms of the knowledge/experience required to design, assemble, and deploy the arsenal. Virtual weapons are a physics reality and cannot be ignored in a world where knowledge, experience, materials, and other requirements to make nuclear weapons are widespread, and where dramatic army reductions and, in some cases, disarmament are realities. These concepts are useful in defining a continuum of virtual capabilities, ranging from those at the low end that derive from general technology diffusion and the existence of nuclear energy programs to those at the high end that involve conscious decisions to develop or maintain militarily significant nuclear-weapon capabilities.

  16. Measuring Neutron Spectrum at MIT Research Reactor Utilizing He-3 Bonner Cylinder Approach with an Unfolding Analysis

    Science.gov (United States)

    Leder, Alexander; Ricochet Collaboration

    2016-03-01

    The Ricochet experiment seeks to measure Coherent (neutral-current) Elastic Neutrino-Nucleus Scattering (CENNS) using dark matter style detectors placed near a neutrino source, possibly the MIT research reactor (MITR), which offers a high continuous neutrino flux at high energies. Currently, Ricochet is characterizing the backgrounds at MITR. The main background is the neutrons emitted simultaneously from the core. To characterize this background, we wrapped a Bonner cylinder around a 3He thermal neutron detector, whose data was then unfolded to produce a neutron energy spectrum across several orders of magnitude. We discuss the resulting spectrum as well its implications for deploying Ricochet in the future.

  17. Application and facility of neutron activation analysis in HANARO research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y.S. [Korea Atomic Energy Research Institute, Taejon (Korea)

    2001-11-01

    The facilities for neutron activation analysis in the HANARO research reactor are described and the main applications of NAA in Korea are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system, were installed at three irradiation holes at the end of 1995. One irradiation hole is lined with a cadmium tube for epithermal NAA. The performance of the NAA facility was examined to identify the characteristics of tube transfer system, irradiation sites and custom made polythylene irradiation capsule. The available thermal neutron flux with each irradiation site are in the range of 3 x 10{sup 13} {approx} 1 x 10{sup 14} n/cm{sup 2}{center_dot}s and cadmium ratios are 15 {approx} 250. For an automatic sample changer for gamma-ray counting, a domestic product was designed and manufactured. An integrated computer program (Labview) for the calculation of content was developed. Neutron activation analysis has been applied in the trace component analysis of nuclear, geological, biological, environmental and high purity materials and various polymers for research and development. Improvement of analytical procedures and establishment of an analytical quality control and assurance system were studied. Applied research and development for the environment, industry and human health by NAA and its standardization was carried out. For the application of the Korea Laboratory Accreditation Scheme (KOLAS), evaluation of measurement uncertainty and proficiency testing of reference materials was performed. Also to verify the reliability and validity of analytical results, intercomparison studies between laboratories were carried out. In this paper, analytical services, national cooperation and the results of the researches are summarized. (author)

  18. The Relationship between Social Capital and Weapon Possession on Campus

    Science.gov (United States)

    Messer, Rachel H.; Bradley, Kristopher I.; Calvi, Jessica L.; Kennison, Shelia M.

    2012-01-01

    The present research focused on the problem of how college officials might be able to predict weapon possession on college campuses. We hypothesized that measures of social capital (i.e., trust and participation in society) may be useful in identifying individuals who are likely to possess weapons on campuses. Prior research has shown that those…

  19. Boron neutron capture therapy (BNCT) for glioblastoma multiforme using the epithermal neutron beam at the Brookhaven Medical Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Capala, J. [Brookhaven National Lab., Upton, NY (United States); Diaz, A.Z.; Chadha, M. [Univ. Hospital, State Univ. of New York, NY (United States)] [and others

    1997-12-31

    The abstract describes evaluation of boron neutron capture therapy (BNCT) for two groups of glioblastoma multiforme patients. From September 1994 to February 1996 15 patients have been treated. In September 1997 another 34 patients were examined. Authors determined a safe starting dose for BNCT using epithermal neutrons and BPA-F. They have also evaluated adverse effects of BNCT at this starting dose. Therapeutic effectiveness of this starting dose has been evaluated. No significant side effects from BPA-F infusion or BNCT treatment were observed in normal brains.

  20. Overall View of Chemical and Biochemical Weapons

    Science.gov (United States)

    Pitschmann, Vladimír

    2014-01-01

    This article describes a brief history of chemical warfare, which culminated in the signing of the Chemical Weapons Convention. It describes the current level of chemical weapons and the risk of using them. Furthermore, some traditional technology for the development of chemical weapons, such as increasing toxicity, methods of overcoming chemical protection, research on natural toxins or the introduction of binary technology, has been described. In accordance with many parameters, chemical weapons based on traditional technologies have achieved the limit of their development. There is, however, a big potential of their further development based on the most recent knowledge of modern scientific and technical disciplines, particularly at the boundary of chemistry and biology. The risk is even higher due to the fact that already, today, there is a general acceptance of the development of non-lethal chemical weapons at a technologically higher level. In the future, the chemical arsenal will be based on the accumulation of important information from the fields of chemical, biological and toxin weapons. Data banks obtained in this way will be hardly accessible and the risk of their materialization will persist. PMID:24902078

  1. Overall view of chemical and biochemical weapons.

    Science.gov (United States)

    Pitschmann, Vladimír

    2014-06-04

    This article describes a brief history of chemical warfare, which culminated in the signing of the Chemical Weapons Convention. It describes the current level of chemical weapons and the risk of using them. Furthermore, some traditional technology for the development of chemical weapons, such as increasing toxicity, methods of overcoming chemical protection, research on natural toxins or the introduction of binary technology, has been described. In accordance with many parameters, chemical weapons based on traditional technologies have achieved the limit of their development. There is, however, a big potential of their further development based on the most recent knowledge of modern scientific and technical disciplines, particularly at the boundary of chemistry and biology. The risk is even higher due to the fact that already, today, there is a general acceptance of the development of non-lethal chemical weapons at a technologically higher level. In the future, the chemical arsenal will be based on the accumulation of important information from the fields of chemical, biological and toxin weapons. Data banks obtained in this way will be hardly accessible and the risk of their materialization will persist.

  2. Overall View of Chemical and Biochemical Weapons

    Directory of Open Access Journals (Sweden)

    Vladimír Pitschmann

    2014-06-01

    Full Text Available This article describes a brief history of chemical warfare, which culminated in the signing of the Chemical Weapons Convention. It describes the current level of chemical weapons and the risk of using them. Furthermore, some traditional technology for the development of chemical weapons, such as increasing toxicity, methods of overcoming chemical protection, research on natural toxins or the introduction of binary technology, has been described. In accordance with many parameters, chemical weapons based on traditional technologies have achieved the limit of their development. There is, however, a big potential of their further development based on the most recent knowledge of modern scientific and technical disciplines, particularly at the boundary of chemistry and biology. The risk is even higher due to the fact that already, today, there is a general acceptance of the development of non-lethal chemical weapons at a technologically higher level. In the future, the chemical arsenal will be based on the accumulation of important information from the fields of chemical, biological and toxin weapons. Data banks obtained in this way will be hardly accessible and the risk of their materialization will persist.

  3. Experimental research in neutron physic and thermal-hydraulic at the CDTN Triga reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mesquita, Amir Z.; Souza, Rose Mary G.P.; Ferreira, Andrea V.; Pinto, Antonio J.; Costa, Antonio C.L.; Rezende, Hugo C., E-mail: amir@cdtn.b, E-mail: souzarm@cdtn.b, E-mail: avf@cdtn.b, E-mail: ajp@cdtn.b, E-mail: aclc@cdtn.b, E-mail: hcr@cdtn.b [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2011-07-01

    The IPR-R1 TRIGA (Training, Research, Isotopes production, General Atomics) at Nuclear Technology Development Center (CDTN) is a pool type reactor cooled by natural circulation of light water and an open surface. TRIGA reactors, developed by General Atomics (GA), are the most widely used research reactor in the world and characterized by inherent safety. The IPR-R1 is the only Brazilian nuclear research reactor available and able to perform experiments in which interaction between neutronic and thermal-hydraulic areas occurs. The IPR-R1 has started up on November 11th, 1960. At that time the maximum thermal power was 30 kW. The present forced cooling system was built in the 70th and the power was upgraded to 100 kW. Recently the core configuration and instrumentation was upgraded again to 250 kW at steady state, and is awaiting the license of CNEN to operate definitely at this new power. This paper describes the experimental research project carried out in the IPR-R1 reactor that has as objective evaluate the behaviour of the reactor operational parameters, and mainly to investigate the influence of temperature on the neutronic variables. The research was supported by Research Support Foundation of the State of Minas Gerais (FAPEMIG) and Brazilian Council for Scientific and Technological Development (CNPq). The research project meets the recommendations of the IAEA, for safety, modernization and development of strategic plan for research reactors utilization. This work is in line with the strategic objectives of Brazil, which aims to design and construct the Brazilian Multipurpose research Reactor (RMB). (author)

  4. Neutron spectrum measurements at a radial beam port of the NUR research reactor using a Bonner spheres spectrometer.

    Science.gov (United States)

    Mazrou, H; Nedjar, A; Seguini, T

    2016-08-01

    This paper describes the measurement campaign held around the neutron radiography (NR) facility of the Algerian 1MW NUR research reactor. The main objective of this work is to characterize accurately the neutron beam provided at one of the radial channels of the NUR research reactor taking benefit of the acquired CRNA Bonner spheres spectrometer (BSS). The specific objective was to improve the image quality of the NR facility. The spectrometric system in use is based on a central spherical (3)He thermal neutron proportional counter combined with high density polyethylene spheres of different diameters ranging from 3 to 12in. This counting system has good gamma ray discrimination and is able to cover an energy range from thermal to 20MeV. The measurements were performed at the sample distance of 0.6m from the beam port and at a height of 1.2m from the facility floor. During the BSS measurements, the reactor was operating at low power (100W) to avoid large dead times, pulse pileup and high level radiation exposures, in particular, during spheres handling. Thereafter, the neutron spectrum at the sample position was unfolded by means of GRAVEL and MAXED computer codes. The thermal, epithermal and fast neutron fluxes, the total neutron flux, the mean energy and the Cadmium ratio (RCd) were provided. A sensitivity analysis was performed taking into account various defaults spectra and ultimately a different response functions in the unfolding procedure. Overall, from the obtained results it reveals, unexpectedly, that the measured neutron spectrum at the sample position of the neutron radiography of the NUR reactor is being harder with a predominance of fast neutrons (>100keV) by about 60%. Finally, those results were compared to previous and more recent measurements obtained by activation foils detectors. The agreement was fairly good highlighting thereby the consistency of our findings.

  5. Numerical research on the anisotropic transport of thermal neutron in heterogeneous porous media with micron X-ray computed tomography

    OpenAIRE

    Yong Wang; Wenzheng Yue; Mo Zhang

    2016-01-01

    The anisotropic transport of thermal neutron in heterogeneous porous media is of great research interests in many fields. In this paper, it is the first time that a new model based on micron X-ray computed tomography (CT) has been proposed to simultaneously consider both the separation of matrix and pore and the distribution of mineral components. We apply the Monte Carlo method to simulate thermal neutrons transporting through the model along different directions, and meanwhile detect those ...

  6. Research on Prompt Neutron Multiplicity Distribution for the Neutron-Induced Fission of 235U at 14 MeV Neutrons

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>The prompt neutron multiplicity distribution ν(A) for the n+ 235U fission system at 14 MeV was studied using the distribution mode of the excitation energy and the averaged γ-ray energy in the two

  7. Review on use of neutron radiography at Saclay Nuclear Research Centre

    Energy Technology Data Exchange (ETDEWEB)

    Bayon, G. [Saclay Nuclear Research Centre DRE/SRO, Gif-sur-Yvette (France)

    1996-11-01

    The Commissariat a l`Energie Atomique (CEA) operates three research reactors at Saclay. Each of them is equipped with a Neutron Radiology facility. Osiris is involved in studies of nuclear fuel rod behaviour during accidental events. The underwater NR facility allows to obtain images of the rods before and after power ramp. The Orphee installation is devoted to industrial application of NR including non destructive testing and real time imaging. The main activity concerns the examination of the pyrotechnic devices of the Ariane launcher programmes. Other areas of interest are also described. (author) 2 figs., 1 tab., 5 refs.

  8. Status of spallation neutron source

    Energy Technology Data Exchange (ETDEWEB)

    Oyama, Yukio [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    Existing and planned facilities using proton accelerator driven spallation neutron source are reviewed. These include new project of neutron science proposed from Japan Atomic Energy Research Institute. The present status of facility requirement and accelerator technology leads us to new era of neutron science such as neutron scattering research and nuclear transmutation study using very intense neutron source. (author)

  9. ITHNA.SYS: An Integrated Thermal Hydraulic and Neutronic Analyzer SYStem for NUR research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Mazidi, S., E-mail: samirmazidi@gmail.com [Division Physique et Applications Nucléaires, Centre de Recherche Nucléaire de Draria (CRND), BP 43 Sebala, Draria, Alger (Algeria); Meftah, B., E-mail: b_meftah@yahoo.com [Division Physique et Applications Nucléaires, Centre de Recherche Nucléaire de Draria (CRND), BP 43 Sebala, Draria, Alger (Algeria); Belgaid, M., E-mail: belgaidm@yahoo.com [Faculté de Physique, Université Houari Boumediene, USTHB, BP 31, Bab Ezzouar, Alger (Algeria); Letaim, F., E-mail: fletaim@yahoo.fr [Faculté des Sciences et Technologies, Université d’El-oued, PO Box 789, El-oued (Algeria); Halilou, A., E-mail: hal_rane@yahoo.fr [Division Réacteur NUR, Centre de Recherche Nucléaire de Draria, BP 43 Sebala, Draria, Alger (Algeria)

    2015-08-15

    Highlights: • We develop a neutronic and thermal hydraulic MTR reactor analyzer. • The analyzer allows a rapid determination of the reactor core parameters. • Some NUR reactor parameters have been analyzed. - Abstract: This paper introduces the Integrated Thermal Hydraulic and Neutronic Analyzer SYStem (ITHNA.SYS) that has been developed for the Algerian research reactor NUR. It is used both as an operating aid tool and as a core physics engineering analysis tool. The system embeds three modules of the MTR-PC software package developed by INVAP SE: the cell calculation code WIMSD, the core calculation code CITVAP and the program TERMIC for thermal hydraulic analysis of a material testing reactor (MTR) core in forced convection. ITHNA.SYS operates both in on-line and off-line modes. In the on-line mode, the system is linked, via the computer parallel port, to the data acquisition console of the reactor control room and allows a real time monitoring of major physical and safety parameters of the NUR core. PC-based ITHNA.SYS provides a viable and convenient way of using an accumulated and often complex reactor physics stock of knowledge and frees the user from the intricacy of adequate reactor core modeling. This guaranties an accurate, though rapid, determination of a variety of neutronic and thermal hydraulic parameters of importance for the operation and safety analysis of the NUR research reactor. Instead of the several hours usually required, the processing time for the determination of such parameters is now reduced to few seconds. Validation of the system was performed with respect to experimental measurements and to calculations using reference codes. ITHNA.SYS can be easily adapted to accommodate other kinds of MTR reactors.

  10. New thermal neutron prompt {gamma}-ray activation analysis instrument at the National Institute of Standards and Technology Center for Neutron Research

    Energy Technology Data Exchange (ETDEWEB)

    Mackey, E.A. E-mail: lmackey@nist.gov; Anderson, D.L.; Liposky, P.J.; Lindstrom, R.M.; Chen-Mayer, H.; Lamaze, G.P

    2004-11-01

    A new thermal neutron prompt {gamma}-ray activation analysis (PGAA) instrument was designed and built to replace the original PGAA system at the NIST Center for Neutron Research. By placing a sapphire filter in the neutron beam shutter assembly, the fast neutron fluence rate was reduced by a factor of 5 and low-energy (50-200 keV) {gamma}-ray intensities were reduced by factors of 5-10. The thermal neutron fluence rate was reduced by only a factor of 1.13. A new external beam tube, sample chamber, beam stop, and support structure were built and a new detection system installed. The new beam tube is made of two cylindrical aluminum sections lined with a lithiated polymer. Both sections are kept under vacuum to reduce the number of neutrons scattered by air into the beam tube walls. The sample chamber is also fabricated from aluminum and lined with lithiated polymer, and may be evacuated to minimize the number of neutrons scattered and absorbed by air. The beam tube and sample chamber assembly is suspended from the aluminum support structure. The detection system consists of a 40% efficient (relative) germanium detector (resolution 2.0 at 1332.5 keV) and a bismuth germanate Compton suppressor. The detection system is shielded by lead, surrounded by borated and lithiated polyethylene, and placed on a table attached to the support structure. The new, more compact beam stop is welded to the support structure. Capture {gamma}-ray photopeaks from H, B, C, N, Na, Al, Fe, Ge, I and Pb in the background spectrum were either of lower intensity or eliminated with the new PGAA instrument. The more efficient detection system, positioned closer to the sample, yielded element sensitivity increases of 5-50%. Limits of detection have been greatly reduced compared with those of the original instrument due to reduced Compton and scattered {gamma}-ray backgrounds (especially in the low-energy region), increased sensitivities, and reduction of background {gamma}-ray photopeak

  11. Wounds and weapons

    Energy Technology Data Exchange (ETDEWEB)

    Vogel, H. [Asklepios Klinik St. Georg, Roentgenabteilung, Lohmuehlenstrasse 5, 20099 Hamburg (Germany)], E-mail: Hermann.vogel@ak-stgeorg.lbk-hh.de; Dootz, B. [Asklepios Klinik St. Georg, Roentgenabteilung, Lohmuehlenstrasse 5, 20099 Hamburg (Germany)

    2007-08-15

    Purpose: X-ray findings are described, which are typical for injuries due to conventional weapons. It is intended to demonstrate that radiographs can show findings characteristic for weapons. Material and method: The radiograms have been collected in Vietnam, Croatia, Serbia, Bosnia, Chad, Iran, Afghanistan, USA, Great Britain, France, Israel, Palestine, and Germany. Results: Radiograms of injuries due to hand grenades show their content (globes) and cover fragments. The globes are localized regionally in the victim's body. Survivors of cluster bombs show singular or few globes; having been hit by many globes would have been lethal. Shotguns produce characteristic distributions of the pallets and depth of penetration different from those of hand grenades and cluster bombs; cover fragments are lacking. Gunshot wounds (GSW) can be differentiated in those to low velocity bullets, high velocity projectiles, and projectiles, which disintegrate on impact. The radiogram furnishes the information about a dangerous shock and helps to recognize the weapon. Radiograms of victims of explosion show fragments and injuries due to the blast, information valid for therapy planning and prognosis. The radiogram shows details which can be used in therapy, forensic medicine and in war propaganda - examples could be findings typical for cluster bombs and for dumdum bullets; it shows the cruelty of the employment of weapons against humans and the conflict between the goal of medical care and those of military actions. Conclusion: Radiographs may show, which weapon has been employed; they can be read as war reports.

  12. Wounds and weapons.

    Science.gov (United States)

    Vogel, H; Dootz, B

    2007-08-01

    X-ray findings are described, which are typical for injuries due to conventional weapons. It is intended to demonstrate that radiographs can show findings characteristic for weapons. The radiograms have been collected in Vietnam, Croatia, Serbia, Bosnia, Chad, Iran, Afghanistan, USA, Great Britain, France, Israel, Palestine, and Germany. Radiograms of injuries due to hand grenades show their content (globes) and cover fragments. The globes are localized regionally in the victim's body. Survivors of cluster bombs show singular or few globes; having been hit by many globes would have been lethal. Shotguns produce characteristic distributions of the pallets and depth of penetration different from those of hand grenades and cluster bombs; cover fragments are lacking. Gunshot wounds (GSW) can be differentiated in those to low velocity bullets, high velocity projectiles, and projectiles, which disintegrate on impact. The radiogram furnishes the information about a dangerous shock and helps to recognize the weapon. Radiograms of victims of explosion show fragments and injuries due to the blast, information valid for therapy planning and prognosis. The radiogram shows details which can be used in therapy, forensic medicine and in war propaganda - examples could be findings typical for cluster bombs and for dumdum bullets; it shows the cruelty of the employment of weapons against humans and the conflict between the goal of medical care and those of military actions. Radiographs may show, which weapon has been employed; they can be read as war reports.

  13. Development of Pneumatic Transfer Irradiation Facility (PTS no.2) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-03-15

    A pneumatic transfer irradiation system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer irradiation system (PTS no.2) involving a manual system and an automatic system for delayed neutron activation analysis (DNAA) were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of PTS no.2 was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, automatic operation control by personal computer, delayed neutron counting system, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  14. Neutron flux parameters for k{sub 0}-NAA method at the Malaysian nuclear agency research reactor after core reconfiguration

    Energy Technology Data Exchange (ETDEWEB)

    Yavar, A.R. [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Sarmani, S. [School of Chemical Sciences and Food Technology, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Wood, A.K. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, Kajang, Selangor 43000 (Malaysia); Fadzil, S.M. [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia); Masood, Z. [Analytical Chemistry Application Group, Industrial Technology Division, Malaysian Nuclear Agency (MNA), Bangi, Kajang, Selangor 43000 (Malaysia); Khoo, K.S., E-mail: khoo@ukm.m [School of Applied Physics, Faculty of Science and Technology, University Kebangsaan Malaysia (UKM), Bangi, Selangor 43600 (Malaysia)

    2011-02-15

    The Malaysian Nuclear Agency (MNA) research reactor, commissioned in 1982, is a TRIGA Mark II swimming pool type reactor. When the core configuration changed in June 2009, it became essential to re-determine such neutron flux parameters as thermal to epithermal neutron flux ratio (f), epithermal neutron flux shape factor ({alpha}), thermal neutron flux ({phi}{sub th}) and epithermal neutron flux ({phi}{sub epi}) in the irradiation positions of MNA research reactor in order to guarantee accuracy in the application of k{sub 0}-neutron activation analysis (k{sub 0}-NAA).The f and {alpha} were determined using the bare bi-isotopic monitor and bare triple monitor methods, respectively; Au and Zr monitors were utilized in present study. The results for four irradiation positions are presented and discussed in the present work. The calculated values of f and {alpha} ranged from 33.49 to 47.33 and -0.07 to -0.14, respectively. The {phi}{sub th} and the {phi}{sub epi} were measured as 2.03 x 10{sup 12} (cm{sup -2} s{sup -1}) and 6.05 x 10{sup 10} (cm{sup -2} s{sup -1}) respectively. These results were compared to those of previous studies at this reactor as well as to those of reactors in other countries. The results indicate a good conformity with other findings.

  15. Postulated accident scenarios in weapons disassembly

    Energy Technology Data Exchange (ETDEWEB)

    Payne, S.S. [Dept. of Energy, Albuquerque, NM (United States)

    1997-06-01

    A very brief summary of three postulated accident scenarios for weapons disassembly is provided in the paper. The first deals with a tetrahedral configuration of four generic pits; the second, an infinite planar array of generic pits with varying interstitial water density; and the third, a spherical shell with internal mass suspension in water varying the size and mass of the shell. Calculations were performed using the Monte Carlo Neutron Photon transport code MCNP4A. Preliminary calculations pointed to a need for higher resolution of small pit separation regimes and snapshots of hydrodynamic processes of water/plutonium mixtures.

  16. Bioterrorism: toxins as weapons.

    Science.gov (United States)

    Anderson, Peter D

    2012-04-01

    The potential for biological weapons to be used in terrorism is a real possibility. Biological weapons include infectious agents and toxins. Toxins are poisons produced by living organisms. Toxins relevant to bioterrorism include ricin, botulinum, Clostridium perfrigens epsilson toxin, conotoxins, shigatoxins, saxitoxins, tetrodotoxins, mycotoxins, and nicotine. Toxins have properties of biological and chemical weapons. Unlike pathogens, toxins do not produce an infection. Ricin causes multiorgan toxicity by blocking protein synthesis. Botulinum blocks acetylcholine in the peripheral nervous system leading to muscle paralysis. Epsilon toxin damages cell membranes. Conotoxins block potassium and sodium channels in neurons. Shigatoxins inhibit protein synthesis and induce apoptosis. Saxitoxin and tetrodotoxin inhibit sodium channels in neurons. Mycotoxins include aflatoxins and trichothecenes. Aflatoxins are carcinogens. Trichothecenes inhibit protein and nucleic acid synthesis. Nicotine produces numerous nicotinic effects in the nervous system.

  17. Experimental Software Design of the Neutron Texture Diffractometer at China Advanced Research Reactor

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Neutron scattering lab is building our country's first neutron texture diffractometer, which will be used for the texture measurement and analysis in the materials science and engineering applications. The sample table and its measurement and control

  18. Progress in alternative neutron detection to address the helium-3 shortage

    Energy Technology Data Exchange (ETDEWEB)

    Kouzes, Richard T., E-mail: rkouzes@pnl.gov; Lintereur, Azaree T.; Siciliano, Edward R.

    2015-06-01

    One of the main uses for {sup 3}He is in gas proportional counters for neutron detection. Such detectors are used at neutron scattering science facilities and in radiation portal monitors deployed for homeland security and non-proliferation applications. Other uses of {sup 3}He are for research detectors, commercial instruments, well logging detectors, dilution refrigerators, lung imaging, for targets in nuclear research, and for basic research in condensed matter physics. The supply of {sup 3}He comes entirely from the decay of tritium produced for nuclear weapons in the U.S. and Russia. Due to the large increase in use of {sup 3}He for science and homeland security (since 2002), the supply could no longer meet the demand. This has led to the development of a number of alternative neutron detection schemes. - Highlights: • There is a shortage of {sup 3}He for gas proportional counters for neutron detection. • This has led to the development of alternative neutron detection schemes. • Both thermal and fast neutron detection approaches have been developed. • Thermal neutron solutions are mostly boron-based or lithium-based. • Fast neutron solutions include liquid/plastic scintillators, bubble chambers or {sup 4}He.

  19. Measurement of the thermal and fast neutron flux in a research reactor with a Li and Th loaded optical fibre detector

    CERN Document Server

    Yamane, Y; Misawa, T; Karlsson, J K H; Pázsit, I

    1999-01-01

    The spatial dependence of thermal and fast neutron flux was measured axially in the core of a 1 MW research reactor. The measurements were made by a thin optical fibre detector with a neutron sensitive ZnS(Ag) scintillation tip. For thermal neutrons sup 6 Li was used, whereas for fast neutrons sup 2 sup 3 sup 2 Th was used as neutron converter. The spatial dependence was measured by moving the fibre axially with a uniform speed. The measurement takes a few minutes, compared to up to 10 h with the conventional wire activation method. Comparison with traditional measurements shows a good agreement. (author)

  20. Weapon of the Weak?

    DEFF Research Database (Denmark)

    Amber, Van der Graaf; Otjes, Simon; Rasmussen, Anne

    2016-01-01

    Social media have the potential to offset existing inequalities in representation among interest groups and act as a ‘weapon of the weak’ by providing a technological infrastructure that allows even groups with limited resources to create content and interact across the globe. We expand on the sp......Social media have the potential to offset existing inequalities in representation among interest groups and act as a ‘weapon of the weak’ by providing a technological infrastructure that allows even groups with limited resources to create content and interact across the globe. We expand...

  1. The Optimum Replacement of Weapon

    Institute of Scientific and Technical Information of China (English)

    ZHANG Xiao; ZHANG Jin-chun

    2002-01-01

    The theory of LCC (Life Cycle Cost) is applied in this paper. The relation between the economic life of weapon and the optimum replacement is analyzed. The method to define the optimum replacement time of weapon is discussed.

  2. Multiple smart weapons employment mechanism

    Energy Technology Data Exchange (ETDEWEB)

    McGlynn, M.P.; Meiklejohn, W.D.

    1993-07-20

    A digital communications armament network adaptor is described for carrying multiple smart weapons on a single wing pylon station of an aircraft, comprising: an aircraft having a weapons controller configured in compliance with MIL-STD 1553; multiple wing-mounted pylons on said aircraft, each providing a weapons station with communications and ejection and release mechanisms electrically connected to said controller for the airborne launch of smart weapons; a multiple ejector rack affixed to at least one pylon, said rack holding a plurality of smart weapons; and an electronic digital network connected between the controller and said rack-mounted smart weapons, said network located in said rack and including circuitry which receives coded digital communications from said controller and selectively rebroadcasts said communications to one of said smart weapons on said rack designated by said coded communications, thereby controlling all required functions of said designated smart weapon.

  3. A Background-Free Direction-Sensitive Neutron Detector2 A Background-Free Direction-Sensitive Neutron Detector

    CERN Document Server

    Roccaro, Alvaro; Ahlen, S; Avery, D; Inglis, A; Battat, J; Dujmic, D; Fisher, P; Henderson, S; Kaboth, A; Kohse, G; Lanza, R; Monroe, J; Sciolla, G; Skvorodnev, N; Wellenstein, H; Yamamoto, R

    2009-01-01

    We show data from a new type of detector that can be used to determine neutron flux, energy distribution, and direction of neutron motion for both fast and thermal neutrons. Many neutron detectors are plagued by large backgrounds from x-rays and gamma rays, and most current neutron detectors lack single-event energy sensitivity or any information on neutron directionality. Even the best detectors are limited by cosmic ray neutron backgrounds. All applications (neutron scattering and radiography, measurements of solar and cosmic ray neutron flux, measurements of neutron interaction cross sections, monitoring of neutrons at nuclear facilities, oil exploration, and searches for fissile weapons of mass destruction) will benefit from the improved neutron detection sensitivity and improved measurements of neutron properties made possible by this detector. The detector is free of backgrounds from x-rays, gamma rays, beta particles, relativistic singely charged particles and cosmic ray neutrons. It is sensitive to th...

  4. Research on 14 MeV Neutron Induced Single-event-effects in SRAMs

    Institute of Scientific and Technical Information of China (English)

    FAN; Hui; GUO; Gang; SHEN; Dong-jun; LIU; Jian-cheng

    2013-01-01

    High energy neutrons are produced in nuclear cascade showers created by nuclear spallation reactions between cosmic rays(mainly protons)and atmospheric nuclei(nitrogen and oxygen).Atmospheric neutrons have been identified as the main cause of single-event-effects(SEE)at elevated altitudes.Avionics are vulnerable to atmospheric neutrons,which can easily produce SEE in

  5. Nuclear weapon detection categorization analysis

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This statement of work is for the Proof of Concept for nuclear weapon categories utility in Arms control. The focus of the project will be to collect, analyze and correlate Intrinsic Radiation (INRAD) calculation results for the purpose of defining measurable signatures that differentiate categories of nuclear weapons. The project will support START III negotiations by identifying categories of nuclear weapons. The categories could be used to clarify sub-limits on the total number of nuclear weapons.

  6. Collaborative Physical and Biological Dosimetry Studies for Neutron Capture Therapy at the RA-1 Research Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    Nigg, D.W.; Schwint, A.E.; Hartwell, J.K.; Heber, E.M.; Trivillin, V.; Castillo, J.; Wentzeis, L.; Sloan, P.; Wemple, C.A.

    2004-10-04

    Initial physical dosimetry measurements have been completed using activation spectrometry and thermoluminiscent dosimeters to characterize the BNCT irradiation facility developed at the RA-1 research reactor operated by the Argentine National Atomic Energy Commission in Buenos Aires. Some biological scoping irradiations have also been completed using a small-animal (hamster) oral mucosa tumor model. Results indicate that the RA-1 neutron source produces useful dose rates but that some improvements in the initial configuration will be needed to optimize the spectrum for thermal-neutron BNCT research applications.

  7. Collaborative Physical and Biological Dosimetry Studies for Neutron Capture Therapy at the RA-1 Research Reactor Facility

    Energy Technology Data Exchange (ETDEWEB)

    David W. Nigg; Amanda E. Schwint; John K. Hartwell; Elisa M. Heber; Veronica Trivillin; Jorge Castillo; Luis Wentzeis; Patrick Sloan; Charles A. Wemple

    2004-10-01

    Initial physical dosimetry measurements have been completed using activation spectrometry and thermoluminiscent dosimeters to characterize the BNCT irradiation facility developed at the RA-1 research reactor operated by the Argentine National Atomic Energy Commission in Buenos Aires. Some biological scoping irradiations have also been completed using a small-animal (hamster) oral mucosa tumor model. Results indicate that the RA-1 neutron source produces useful dose rates but that some improvements in the initial configuration will be needed to optimize the spectrum for thermal-neutron BNCT research applications.

  8. Neutronic study of SCR core for under-sea scientific research vessel

    Energy Technology Data Exchange (ETDEWEB)

    Odano, Naoteru; Ishida, Toshihisa [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Wada, Koji; Imai, Hiroshi [Hitachi Engineering Co., Ltd., Hitachi, Ibaraki (Japan)

    2001-07-01

    A very small reactor, SCR (Submersible Compact Reactor), whose thermal output is 1250 kW, is an integral-pressurized type reactor to be used as a power source for a scientific research vessel in medium region to approximately 300-m in depth of the Arctic Ocean. Neutronic study has been carried out for design of the SCR core of which could achieve continuous long-term operation without refueling for 10 years considering 50% of load factor of the core. In the present study, arrangement of fuel rods, {sup 235}U enrichment of UO{sub 2} fuel rods and reflector materials were surveyed. The {sup 235}U enrichment has been determined to be 9.5 wt% to satisfy design criteria. Design of the reflector as well as that of the fuel enrichment is one of important factors for determination of the core life because leakage of neutrons from a very small reactor is large. In the present study Be metal was adopted as a reflector material. The square and triangle arrangements of fuel rods were studied and the later one was adopted for the present design to make possible to reduce size of the core. Reactor physics parameters including reactivity coefficients and power distributions were evaluated for the determined core specifications. Reactor physics parameters related to core safety were also confirmed and the evaluated parameters indicated that the determined core specifications in this study satisfied design conditions. (author)

  9. Design and construction of a thermal neutron beam for BNCT at Tehran Research Reactor.

    Science.gov (United States)

    Kasesaz, Yaser; Khalafi, Hossein; Rahmani, Faezeh; Ezzati, Arsalan; Keyvani, Mehdi; Hossnirokh, Ashkan; Shamami, Mehrdad Azizi; Amini, Sepideh

    2014-12-01

    An irradiation facility has been designed and constructed at Tehran Research Reactor (TRR) for the treatment of shallow tumors using Boron Neutron Capture Therapy (BNCT). TRR has a thermal column which is about 3m in length with a wide square cross section of 1.2×1.2m(2). This facility is filled with removable graphite blocks. The aim of this work is to perform the necessary modifications in the thermal column structure to meet thermal BNCT beam criteria recommended by International Atomic Energy Agency. The main modifications consist of rearranging graphite blocks and reducing the gamma dose rate at the beam exit. Activation foils and TLD700 dosimeter have been used to measure in-air characteristics of the neutron beam. According to the measurements, a thermal flux is 5.6×10(8) (ncm(-2)s(-1)), a cadmium ratio is 186 for gold foils and a gamma dose rate is 0.57Gy h(-1).

  10. Applying Agile MethodstoWeapon/Weapon-Related Software

    Energy Technology Data Exchange (ETDEWEB)

    Adams, D; Armendariz, M; Blackledge, M; Campbell, F; Cloninger, M; Cox, L; Davis, J; Elliott, M; Granger, K; Hans, S; Kuhn, C; Lackner, M; Loo, P; Matthews, S; Morrell, K; Owens, C; Peercy, D; Pope, G; Quirk, R; Schilling, D; Stewart, A; Tran, A; Ward, R; Williamson, M

    2007-05-02

    This white paper provides information and guidance to the Department of Energy (DOE) sites on Agile software development methods and the impact of their application on weapon/weapon-related software development. The purpose of this white paper is to provide an overview of Agile methods, examine the accepted interpretations/uses/practices of these methodologies, and discuss the applicability of Agile methods with respect to Nuclear Weapons Complex (NWC) Technical Business Practices (TBPs). It also provides recommendations on the application of Agile methods to the development of weapon/weapon-related software.

  11. Research on HLA Distributing Interactive Simulation of Torpedo Weapon System%基于HLA的鱼雷武器系统分布交互仿真

    Institute of Scientific and Technical Information of China (English)

    魏静; 高立娥; 杜来毅; 王飞

    2011-01-01

    为避免传统意义上低层次、低效率的重复开发,通过对HIA联邦成员的仿真流程及内部接口关系的研究,构建了基于HLA标准的由鱼雷、发射艇、目标、对抗器材等联邦成员组成的鱼雷作战对抗分布交互仿真系统,给出了仿真系统的网络拓扑结构,完成了联邦成员的功能实现.介绍了水声对抗条件下的基本作战仿真流程,包括初始设定、仿真计算、搜索探测、决策方案、双方武器或干扰器材的对抗过程、仿真结束等六个阶段:完成了鱼雷武器系统在潜一潜,舰一潜对抗态势条件下的弹道仿真研究.%In order to ovoid low level and inefficient exploitation , by means of researching of simulation flow and inside interface of HLA federation member, based on HLA standard, torpedo warfare simulation system is established by federation members such as torpedo, launch ship, target and confront equipments.This paper introduces the principal campaign simulation flow under the different countermove.It consists of the initialization, searching, detecting, decision, and the countermine process for weapon and countermeasure, and it investigates the ballistic trajectory simulation under the submarine to submarine countermine situation.

  12. News UK public libraries offer walk-in access to research Atoms for Peace? The Atomic Weapons Establishment and UK universities Students present their research to academics: CERN@school Science in a suitcase: Marvin and Milo visit Ethiopia Inspiring telescopes A day for everyone teaching physics 2014 Forthcoming Events

    Science.gov (United States)

    2014-05-01

    UK public libraries offer walk-in access to research Atoms for Peace? The Atomic Weapons Establishment and UK universities Students present their research to academics: CERN@school Science in a suitcase: Marvin and Milo visit Ethiopia Inspiring telescopes A day for everyone teaching physics 2014 Forthcoming Events

  13. Nonstrategic Nuclear Weapons

    Science.gov (United States)

    2017-02-21

    have eased in recent years, with their nuclear tests in 1998 and continued animosity toward each other, India and Pakistan have joined the list of...could be complex, difficult, and very time- consuming . 137 Given the large disparity in the numbers of U.S. and Russian nonstrategic nuclear weapons

  14. Medicalized weapons & modern war.

    Science.gov (United States)

    Gross, Michael L

    2010-01-01

    "Medicalized" weapons--those that rely on advances in neuroscience, physiology, and pharmacology--offer the prospect of reducing casualties and protecting civilians. They could be especially useful in modern asymmetric wars in which conventional states are pitted against guerrilla or insurgent forces. But may physicians and other medical workers participate in their development?

  15. Neutrino Counter Nuclear Weapon

    CERN Document Server

    Tang, Alfred

    2008-01-01

    Radiations produced by neutrino-antineutrino annihilation at the Z0 pole can be used to heat up the primary stage of a thermonuclear warhead and can in principle detonate the device remotely. Neutrino-antineutrino annihilation can also be used as a tactical assault weapon to target hideouts that are unreachable by conventional means.

  16. Nuclear weapons in Europe

    CERN Document Server

    Calogero, F

    1981-01-01

    Information speech given by Prof. Calogero from the university of Roma to describe the actual situation of nuclear weapons in Europe, the strategical reasons or justifications for this deployment, the prospects of negociations, and what scientists could do and do on this issue.

  17. Pakistans Nuclear Weapons

    Science.gov (United States)

    2016-02-12

    Memorandum from Air Commodore Khalid Banuri, 2011. 84 Mahmud Ali Durrani, “Pakistan’s Strategic Thinking and the Role of Nuclear Weapons...Richard P. Cronin , K. Alan Kronstadt, and Sharon Squassoni. Also see CRS Report RL33498, Pakistan-U.S. Relations, by K. Alan Kronstadt. 168 For a

  18. Evaluation of neutron flux parameters in irradiation sites of research reactor using the Westcott-formalism for the k0 neutron activation analysis method

    Science.gov (United States)

    Kasban, H.; Hamid, Ashraf

    2015-12-01

    Instrumental Neutron Activation Analysis using k0 (k0-INAA) method has been used to determine a number of elements in sediment samples collected from El-Manzala Lake in Egypt. k0-INAA according to Westcott's formalism has been implemented using the complete irradiation kit of the fast pneumatic rabbit and some selected manually loaded irradiation sites for short and long irradiation at Egypt Second Research Reactor (ETRR-2). Zr-Au and Co sets as neutron flux monitors are used to determine the neutron flux parameters (f and α) in each irradiation sites. Two reference materials IAEA Soil-7 samples have been inserted and implemented for data validation and an internal monostandard multi monitor used (k0 based IM-NAA). It was given a good agreement between the experimental analyzed values and that obtained of the certified values. The major and trace elements in the sediment samples have been evaluated with the use of Co as an internal and Au as an external monostandard comparators. The concentrations of the elements (Cr, Mn and Zn) in the sediment samples of the present work are discussed regarding to those obtained from other sites.

  19. Study on the characterization of the neutron radiography facility in HANARO for two-phase flow research

    Energy Technology Data Exchange (ETDEWEB)

    Lim, I. C.; Seo, C. G.; Jeong, J. H.; Lee, B. H.; Choi, Y. S

    2001-01-01

    For the application of dynamic neutron radiography to the two-phase flow research using HANARO, several experimental items to which the radiography technique is beneficial were identified through the review of the outputs from the related researches and the discussions with experts. Also, the investigation of the equipments including the beam port, camera and converter was made and a hardware and a software for image processing were equipped. It was confirmed that the calibration curve for the attenuation of neutron beam in fluid which is required for the two-phase flow experiment could be obtained by the computer code calculation. Based on the investigation results on the equipment and the results from the measurement of BNCT beam characteristics, a high speed camera and an image intensifier will be purchased. Then, the high speed dynamic neutron radiography facility for two-phase flow experiments will be fully equipped.

  20. Prions: the danger of biochemical weapons

    Directory of Open Access Journals (Sweden)

    Eric Almeida Xavier

    2014-09-01

    Full Text Available The knowledge of biotechnology increases the risk of using biochemical weapons for mass destruction. Prions are unprecedented infectious pathogens that cause a group of fatal neurodegenerative diseases by a novel mechanism. They are transmissible particles that are devoid of nucleic acid. Due to their singular characteristics, Prions emerge as potential danger since they can be used in the development of such weapons. Prions cause fatal infectious diseases, and to date there is no therapeutic or prophylactic approach against these diseases. Furthermore, Prions are resistant to food-preparation treatments such as high heat and can find their way from the digestive system into the nervous system; recombinant Prions are infectious either bound to soil particles or in aerosols. Therefore, lethal Prions can be developed by malicious researchers who could use it to attack political enemies since such weapons cause diseases that could be above suspicion.

  1. 武器装备体系需求变更管理研究%Research on Requirements Change Management of Weapon Equipment System of Systems

    Institute of Scientific and Technical Information of China (English)

    耿青霞; 杨秀月; 杨雷

    2011-01-01

    According to the characteristic of requirements change of weapon equipment system-of-systems, the paper studies the basic conception, analyzes the principle and work flows of requirements change of weapon equipment system-of-systems. Moreover, it brings forward the analysis frame of requirements change supporting theory and methods for the choice and development of the tools of requirements change management of weapon equipment system-of-systems. It is significant to implement the requirements change scientific management and enhance the quality of requirements generation of weapon equipment system-of-systems.%依据武器装备体系需求变更的特点,研究了武器装备体系需求变更管理的基本概念,分析了武器装备体系需求变更管理的原则和流程,构建了武器装备体系需求变更分析框架,为体系需求变更管理工具的选择和开发提供理论和方法支持,对实现武器装备体系需求变更的科学管理,提高需求生成的质量具有重要的理论指导意义。

  2. Numerical research on the anisotropic transport of thermal neutron in heterogeneous porous media with micron X-ray computed tomography

    Science.gov (United States)

    Wang, Yong; Yue, Wenzheng; Zhang, Mo

    2016-06-01

    The anisotropic transport of thermal neutron in heterogeneous porous media is of great research interests in many fields. In this paper, it is the first time that a new model based on micron X-ray computed tomography (CT) has been proposed to simultaneously consider both the separation of matrix and pore and the distribution of mineral components. We apply the Monte Carlo method to simulate thermal neutrons transporting through the model along different directions, and meanwhile detect those unreacted thermal neutrons by an array detector on the other side of the model. Therefore, the anisotropy of pore structure can be imaged by the amount of received thermal neutrons, due to the difference of rock matrix and pore-filling fluids in the macroscopic reaction cross section (MRCS). The new model has been verified by the consistent between the simulated data and the pore distribution from X-ray CT. The results show that the evaluation of porosity can be affected by the anisotropy of media. Based on the research, a new formula is developed to describe the correlation between the resolution of array detectors and the quality of imaging. The formula can be further used to analyze the critical resolution and the suitable number of thermal neutrons emitted in each simulation. Unconventionally, we find that a higher resolution cannot always lead to a better image.

  3. Basics of Fusion-Fissison Research Facility (FFRF) as a Fusion Neutron Source

    Energy Technology Data Exchange (ETDEWEB)

    Leonid E. Zakharov

    2011-06-03

    FFRF, standing for the Fusion-Fission Research Facility represents an option for the next step project of ASIPP (Hefei, China) aiming to a first fusion-fission multifunctional device [1]. FFRF strongly relies on new, Lithium Wall Fusion plasma regimes, the development of which has already started in the US and China. With R/a=4/1m/m, Ipl=5 MA, Btor=4-6 T, PDT=50- 100 MW, Pfission=80-4000MW, 1 m thick blanket, FFRF has a unique fusion mission of a stationary fusion neutron source. Its pioneering mission of merging fusion and fission consists in accumulation of design, experimental, and operational data for future hybrid applications.

  4. 贫信息下空袭兵器威胁能力评估方法%Research on Assessment for Threat Ability of Air Raid Weapon under Lacking Information

    Institute of Scientific and Technical Information of China (English)

    赵喜; 李修和; 沈阳

    2011-01-01

    Nowadays, at aerial defense combat, the air raid weapons become more and more powerful,which bring more menace to our key target. So it is badly needed to evaluate the menace ability of air raid weapons, so as to assign aerial defense power and protect our target. This paper researches the process of assessment for threat ability of aerial raid weapon, provides the arithmetic and math model under the background of modern aerial-defense combat and lacking information. The example given in the end shows the practicability of the model.%现代防空作战中,各种空袭兵器突袭能力不断增强,对我方目标构成了极大威胁.因此,需要对空袭兵器的威胁能力进行评估,合理分配各种防空火力,以达到保护我方目标的目的.研究了现代防空作战背景下,空袭兵器威胁能力评估的全过程,给出了贫信息下,威胁能力评估的算法,建立了数学模型,最后用实例说明了该评估方法的实用性.

  5. Research on Non-lethal Efficiency Evaluation of Electrical Weapon%电击武器非致命效能评估

    Institute of Scientific and Technical Information of China (English)

    郭三学; 黄德勇; 赵晓青

    2014-01-01

    This thesis brings up a method to evaluate the non-lethal efficiency of electrical weapon. First of all,on the basis of analyzing the key influence factors to non-lethal electrical weapon’s effectiveness,a non-lethal effectiveness evaluation index system is built. And then,the combination of quantitative calculation and qualitative analysis are adopted,the fuzzy evaluation method is applied to the non-lethal weapon effectiveness evaluation,the fuzzy evaluation matrix is determined,the fuzzy comprehensive method to build evaluation model is choosen. Finally,through the analysis of examples given non-lethal electrical weapon efficiency score,comparing the three kinds of model types of non-lethal electrical weapon efficiency,it is concluded that the results tally with the actual situation. It provides auxiliary decision-making basis for the development and application of non-lethal electrical weapon.%提出了电击武器非致命效能的评估方法,分析了影响电击武器非致命效能的关键因素,建立了电击武器非致命效能评估指标体系,采用定性分析和定量计算相结合,将模糊评判法应用到电击武器非致命效能评估中,确定了模糊评判矩阵,建立了评估模型。比较了3种不同类型电击武器的非致命效能,得出了符合实际情况的结果,为电击武器的发展应用提供了辅助决策的依据。

  6. Non-lethal weapons and their characteristics

    OpenAIRE

    DAMJANOVIC DRAGAN Z.

    2015-01-01

    Non-lethal weapons, also called less-lethal weapons, less-than lethal weapons, non-deadly weapons, compliance weapons, or pain-inducing weapons are weapons intended to be less likely to kill a living target than conventional weapons. It is often understood that accidental, incidental, and correlative casualties are risked wherever force is applied, but non-lethal weapons try to minimise the risk as much as possible. Non-lethal weapons are used in combat situations to limit the escalation of c...

  7. NON-LETHAL WEAPONS AND THEIR CHARACTERISTICS

    OpenAIRE

    2015-01-01

    Non-lethal weapons, also called less-lethal weapons, less-than lethal weapons, non-deadly weapons, compliance weapons, or pain-inducing weapons are weapons intended to be less likely to kill a living target than conventional weapons. It is often understood that accidental, incidental, and correlative casualties are risked wherever force is applied, but non-lethal weapons try to minimise the risk as much as possible. Non-lethal weapons are used in combat situations to limit the escalation of c...

  8. The Status of Research Regarding Magnetic Mirrors as a Fusion Neutron Source or Power Plant

    Energy Technology Data Exchange (ETDEWEB)

    Simonen, T

    2008-12-23

    Experimental results, theory and innovative ideas now point with increased confidence to the possibility of a Gas Dynamic Trap (GDT) neutron source which would be on the path to an attractively simple Axisymmetric Tandem Mirror (ATM) power plant. Although magnetic mirror research was terminated in the US 20 years ago, experiments continued in Japan (Gamma 10) and Russia (GDT), with a very small US effort. This research has now yielded data, increased understanding, and generated ideas resulting in the new concepts described here. Early mirror research was carried out with circular axisymmetric magnets. These plasmas were MHD unstable due to the unfavorable magnetic curvature near the mid-plane. Then the minimum-B concept emerged in which the field line curvature was everywhere favorable and the plasma was situated in a MHD stable magnetic well (70% average beta in 2XII-B). The Ioffe-bar or baseball-coil became the standard for over 40 years. In the 1980's, driven by success with minimum-B stabilization and the control of ion cyclotron instabilities in PR6 and 2XII-B, mirrors were viewed as a potentially attractive concept with near-term advantages as a lower Q neutron source for applications such as a hybrid fission fuel factory or toxic waste burner. However there are down sides to the minimum-B geometry: coil construction is complex; restraining magnetic forces limit field strength and mirror ratios. Furthermore, the magnetic field lines have geodesic curvature which introduces resonant and neoclassical radial transport as observed in early tandem mirror experiments. So what now leads us to think that simple axisymmetric mirror plasmas can be stable? The Russian GDT experiment achieves on-axis 60% beta by peaking of the kinetic plasma pressure near the mirror throat (where the curvature is favorable) to counter-balance the average unfavorable mid-plane curvature. Then a modest augmentation of plasma pressure in the expander results in stability. The GDT

  9. Advanced Scintillator Detectors for Neutron Imaging in Inertial Confinement Fusion

    Science.gov (United States)

    Geppert-Kleinrath, Verena; Danly, Christopher; Merrill, Frank; Simpson, Raspberry; Volegov, Petr; Wilde, Carl

    2016-10-01

    The neutron imaging team at Los Alamos National Laboratory (LANL) has been providing two-dimensional neutron imaging of the inertial confinement fusion process at the National Ignition Facility (NIF) for over five years. Neutron imaging is a powerful tool in which position-sensitive detectors register neutrons emitted in the fusion reactions, producing a picture of the burning fuel. Recent images have revealed possible multi-dimensional asymmetries, calling for additional views to facilitate three-dimensional imaging. These will be along shorter lines of sight to stay within the existing facility at NIF. In order to field imaging capabilities equivalent to the existing system several technological challenges have to be met: high spatial resolution, high light output, and fast scintillator response to capture lower-energy neutrons, which have scattered from non-burning regions of fuel. Deuterated scintillators are a promising candidate to achieve the timing and resolution required; a systematic study of deuterated and non-deuterated polystyrene and liquid samples is currently ongoing. A test stand has been implemented to measure the response function, and preliminary data on resolution and light output have been obtained at the LANL Weapons Neutrons Research facility.

  10. Measurement of neutron flux and beam divergence at the cold neutron guide system of the new Munich research reactor FRM-II

    Science.gov (United States)

    Zeitelhack, K.; Schanzer, C.; Kastenmüller, A.; Röhrmoser, A.; Daniel, C.; Franke, J.; Gutsmiedl, E.; Kudryashov, V.; Maier, D.; Päthe, D.; Petry, W.; Schöffel, T.; Schreckenbach, K.; Urban, A.; Wildgruber, U.

    2006-05-01

    A sophisticated neutron guide system has been installed at the new Munich neutron source FRM-II to transport neutrons from the D 2 cold neutron source to several instruments, which are situated in a separate neutron guide hall. The guide system takes advantage of supermirror coatings and includes a worldwide unique "twisted" guide for a desired phase space transformation of the neutron beam. During the initial reactor commissioning in summer 2004, the integral and differential neutron flux as well as the distribution of beam divergence at the exit of two representative and the twisted neutron guide were measured using time-of-flight spectroscopy and gold-foil activation. The experimental results can be compared to extensive simulation calculations based on MCNP and McStas. The investigated guides fulfill the expectations of providing high neutron fluxes and reveal good quality with respect to the reflective coatings and the installation precision.

  11. Measurement of neutron flux and beam divergence at the cold neutron guide system of the new Munich research reactor FRM-II

    Energy Technology Data Exchange (ETDEWEB)

    Zeitelhack, K. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany)]. E-mail: karl.zeitelhack@frm2.tum.de; Schanzer, C. [Physik-Department E21, TU Muenchen, D-85747 Garching (Germany); Kastenmueller, A. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Roehrmoser, A. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Daniel, C. [Physik-Department E22, TU Muenchen, D-85747 Garching (Germany); Franke, J. [Max-Planck-Institut fuer Metallforschung, D-70569 Stuttgart (Germany); Gutsmiedl, E. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Kudryashov, V. [GKSS Forschungszentrum GmbH, D-21502 Geesthacht (Germany); Maier, D. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Paethe, D. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Petry, W. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Schoeffel, T. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Schreckenbach, K. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Urban, A. [ZWE FRM-II, TU Muenchen, D-85747 Garching (Germany); Wildgruber, U. [Max-Planck-Institut fuer Metallforschung, D-70569 Stuttgart (Germany)

    2006-05-10

    A sophisticated neutron guide system has been installed at the new Munich neutron source FRM-II to transport neutrons from the D{sub 2} cold neutron source to several instruments, which are situated in a separate neutron guide hall. The guide system takes advantage of supermirror coatings and includes a worldwide unique 'twisted' guide for a desired phase space transformation of the neutron beam. During the initial reactor commissioning in summer 2004, the integral and differential neutron flux as well as the distribution of beam divergence at the exit of two representative and the twisted neutron guide were measured using time-of-flight spectroscopy and gold-foil activation. The experimental results can be compared to extensive simulation calculations based on MCNP and McStas. The investigated guides fulfill the expectations of providing high neutron fluxes and reveal good quality with respect to the reflective coatings and the installation precision.

  12. Nuclear track-etched pore membrane production using neutrons from the Thai research reactor TRR-1/M1

    Directory of Open Access Journals (Sweden)

    Thawat Chittrakarn

    2002-11-01

    Full Text Available This work presents the results of the nuclear pore membrane production using the neutrons from the Thai research reactor TRR-1/M1 for pore piercing process on the polycarbonate thin film. With our experimental design, the fast neutron provides better results in pore piercing comparing with thermal neutron bombardment. This can be explained by most of the latent tracks produced by thermal neutron bombardment not penetrating through the thin film. Chemical etching process using NaOH solution with appropriate time, concentration and temperature is employed to enlarge the latent tracks in the bombarded film. Fast neutron bombardment with 5, 10 and 20 minutes bombarding time successfully produces the nuclear track membrane. Pore size and pore density of the produced membranes examined by SEM are 0.24 – 1.01 μm and 4.7 – 245 × 106 pore/cm2, respectively. Bubble point tests show the maximum pore diameter of the produced membrane ranged between 1.18 – 3.25 μm.

  13. Neutron activation analysis at the Livermore pool-type reactor for the environmental research program. [Identification of trace element contaminants

    Energy Technology Data Exchange (ETDEWEB)

    Ragaini, R.C.; Heft, R.E.; Garvis, D.

    1976-07-02

    Instrumental neutron activation analysis is a technique of trace analysis using measurements of radioactivity induced in the sample by exposure to a source of neutrons. The induced activity is measured by the emitted gamma radiation. Each gamma emitter can then be identified by the energy of the photopeaks produced as the nuclide decays and by the half-life of the neutron-induced activity. A complex computer program GAMANAL has been used to accomplish the major tasks of nuclide identification and quantification. The nuclide data output from GAMANAL is processed by a second computer code NADAC, which develops elemental abundance data from disintegration rates observed. The methods are those employed at the Livermore Pool-Type Reactor in support of the environmental research trace element analysis program. Among the procedures described and discussed are sample preparation, irradiation, analysis, and application of the technique.

  14. Neutronic and thermal-hydraulic analysis of fission molybdenum-99 production at Tehran Research Reactor using LEU plate targets.

    Science.gov (United States)

    Abedi, Ebrahim; Ebrahimkhani, Marzieh; Davari, Amin; Mirvakili, Seyed Mohammad; Tabasi, Mohsen; Maragheh, Mohammad Ghannadi

    2016-12-01

    Efficient and safe production of molybdenum-99 ((99)Mo) radiopharmaceutical at Tehran Research Reactor (TRR) via fission of LEU targets is studied. Neutronic calculations are performed to evaluate produced (99)Mo activity, core neutronic safety parameters and also the power deposition values in target plates during a 7 days irradiation interval. Thermal-hydraulic analysis has been also carried out to obtain thermal behavior of these plates. Using Thermal-hydraulic analysis, it can be concluded that the safety parameters are satisfied in the current study. Consequently, the present neutronic and thermal-hydraulic calculations show efficient (99)Mo production is accessible at significant activity values in TRR current core configuration. Copyright © 2016 Elsevier Ltd. All rights reserved.

  15. Monte Carlo Calculation of Core Reactivity and Fluxes for the Development of the BNCT Neutron Source at the Kyiv Research Reactor

    Science.gov (United States)

    Gritzay, Olena; Kalchenko, Oleksandr; Klimova, Nataliya; Razbudey, Volodymyr; Sanzhur, Andriy; Binney, Stephen

    2005-05-01

    The presented results show our consecutive steps in developing a neutron source with parameters required by Boron Neutron Capture Therapy (BNCT) at the Kyiv Research Reactor (KRR). The main goal of this work was to analyze the influence of installation of different types of uranium converters close to the reactor core on neutron beam characteristics and on level of reactor safety. The general Monte Carlo radiation transport code MCNP, version 4B, has been used for these calculations.

  16. Bioterrorism: pathogens as weapons.

    Science.gov (United States)

    Anderson, Peter D; Bokor, Gyula

    2012-10-01

    Biowarfare has been used for centuries. The use of biological weapons in terrorism remains a threat. Biological weapons include infectious agents (pathogens) and toxins. The most devastating bioterrorism scenario would be the airborne dispersal of pathogens over a concentrated population area. Characteristics that make a specific pathogen a high-risk for bioterrorism include a low infective dose, ability to be aerosolized, high contagiousness, and survival in a variety of environmental conditions. The most dangerous potential bioterrorism agents include the microorganisms that produce anthrax, plague, tularemia, and smallpox. Other diseases of interest to bioterrorism include brucellosis, glanders, melioidosis, Q fever, and viral encephalitis. Food safety and water safety threats are another area of concern.

  17. Progress in alternative neutron detection to address the helium-3 shortage

    Energy Technology Data Exchange (ETDEWEB)

    Kouzes, Richard T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lintereur, Azaree T. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Siciliano, Edward R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-06-01

    One of the main uses for 3He is in gas proportional counters for neutron detection. Such detectors are used at neutron scattering science facilities and in radiation portal monitors deployed for homeland security and non-proliferation applications. Other uses of 3He are for research detectors, commercial instruments, well logging detectors, dilution refrigerators, lung imaging, for targets in nuclear research, and for basic research in condensed matter physics. The supply of 3He comes entirely from the decay of tritium produced for nuclear weapons in the U.S. and Russia. Due to the large increase in use of 3He for science and homeland security (since 2002), the supply has dwindled, and can no longer meet the demand. This has led to the development of a number of alternative neutron detection schemes.

  18. Research with neutron and synchrotron radiation on aerospace and automotive materials and components

    Energy Technology Data Exchange (ETDEWEB)

    Kaysser, Wolfgang; Abetz, Volker; Huber, Norbert; Kainer, Karl Ulrich; Pyczak, Florian; Schreyer, Andreas; Staron, Peter [Helmholtz-Zentrum Geesthacht Zentrum fuer Material und Kuestenforschung, Geesthacht (Germany); Esslinger, Joerg [MTU Aero Engines GmbH, Muenchen (Germany); Klassen, Thomas [Helmholtz-Zentrum Geesthacht Zentrum fuer Material und Kuestenforschung, Geesthacht (Germany); Helmut Schmidt Universitaet, Hamburg (Germany)

    2011-08-15

    Characterization with neutrons and synchrotron radiation has yielded essential contributions to the research and development of automotive and aerospace materials, processing methods, and components. This review mainly emphasises developments related to commercial passenger airplanes and light-duty cars. Improved and partly new materials for the reduction of airframe weight and joining by laser-beam welding and friction stir welding are ongoing areas of assessment. Chemical reactions, microstructure development, and residual stresses are frequently measured. Polymers and polymer matrix composites often require special experimental techniques. The thrust-to-weight ratio of aero-engines is increasing due to the improved design of components and the use of innovative materials. Investigations on superalloys, {gamma}-TiAl, and thermal barrier coatings are described in some detail. A discussion of the use of neutron and synchrotron diffraction in automotive applications covers the analysis of surface effects with respect to lubricants and wear, as well as the investigation of microstructure development, deformation, and fatigue behavior of materials, welds and components. Special steels, Al and Mg alloys are discussed and residual stresses in automotive components such as gears or crankshafts are described. Applications of characterization methods on membranes for polymeric membrane fuel cells and on nanocrystalline metal hydrides for hydrogen storage are shown. The degradation of railway tracks after long-term use is taken as an example for the application of synchrotron methods to transport systems beyond the commercial aircraft and light duty passenger car. (Copyright copyright 2011 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  19. Counterproliferation of Nuclear Weapons

    Science.gov (United States)

    2010-04-01

    an occurrence. In his book, Atomic Tragedy, Sean Malloy writes that Henry Stimson, the United States Secretary of War, warned in April, 1945 that...Ibid., 380. 41 Ibid. 42 Sean L. Malloy , Atomic Tragedy: Henry L. Stimson and the Decision to use the Bomb Against Japan (Ithaca, New York...Weapons of Mass Destruction in the Middle East, 96-97. 45 Robert M. Gates, National Defense Strategy (Washington, DC: US Government Printing Office

  20. Research on Quantization System of Weapon Equipment Combat Capability%武器装备作战能力量化体系

    Institute of Scientific and Technical Information of China (English)

    陈国社; 马亚平

    2011-01-01

    Weapon equipmen combat capability quantity is a primary data engineering in the field of war game.As the basic element of weapon equipmen combat capability , "five kinds capability" is decomposed into some factors reasonably.Through the scientific and reasonable partition of weapon equipmen combat capability quantization level, the framework of weapon equipmen combat capability quantization is set up.Finally, the main works and interrelated methods about index system setting up and model system designing is introduced simply.%武器装备作战能力量化问题是现代作战模拟领域的一项基础数据工程.以"五力"为武器装备作战能力的基本构成要素,对其适度分解,形成了武器装备作战能力内涵较为全面、详细的描述.对武器装备作战能力量化层次进行了科学、合理划分,确定了武器装备作战能力各分量的首要量化层次,形成了武器装备作战能力量化体系结构.介绍了武器装备作战能力量化指标体系建立和量化模型体系构建所涉及的主要工作及相应研究思路.

  1. Design of Stopper of Prompt Gamma Neutron Activation Analysis Facility at China Advanced Research Reactor

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The PGNAA facility consists of the filtered collimated neutron beam, the shielding of the whole facility, the control system, the detecting equipment and the data acquisition and analysis system. The neutron beam is filtered by a mono-crystalline bismuth filter,

  2. On-line beam monitoring for neutron capture therapy at the MIT Research Reactor

    Science.gov (United States)

    Harling, Otto K.; Moulin, Damien J.; Chabeuf, Jean-Michel; Solares, Guido R.

    1995-08-01

    Neutron capture therapy sets new requirements on the measurement and monitoring of the radiation fields used in this new form of therapy. Beams used for neutron capture therapy are comprised of mixed radiation fields which include slow, epithermal, and fast neutrons, as well as gamma rays. A computer-based beam monitoring system for epithermal or thermal neutron capture therapy is described. This system provides accurate, sensitive, and rapid on-line readout and recording of the various beam components. Readout of fluxes, fluences, and corresponding doses in the target are provided in color coded graphic analog as well as numerical form on the computer monitors. Variations in neutron spectrum or spatial distribution of the beam can be rapidly diagnosed with the aid of the monitor readout. Redundancy of fluence measurement is provided by an independent system using scalers and timers and by utilizing reactor power measuring instruments.

  3. 32 CFR 234.10 - Weapons.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 2 2010-07-01 2010-07-01 false Weapons. 234.10 Section 234.10 National Defense... PENTAGON RESERVATION § 234.10 Weapons. (a) Except as otherwise authorized under this section, the following are prohibited: (1) Possessing a weapon. (2) Carrying a weapon. (3) Using a weapon. (b) This section...

  4. Development of Pneumatic Transfer Irradiation Facility (PTS no.1) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-03-15

    A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide and a delayed neutron counting system. The pneumatic transfer system (PTS no.1) involving a manual system and an semiautomatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor in 2006. In this technical report, the conception, design, operation and control of these system (PTS no.1) was described. Also the experimental results and the characteristic parameters measured by a mock-up test, a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  5. Weapon Possession Among College Students: A Study From a Midwestern University.

    Science.gov (United States)

    Jang, Hyunseok; Kang, Ji Hyon; Dierenfeldt, Rick; Lindsteadt, Greg

    2015-10-01

    Weapon possession on college campuses causes great concern, but there remains a lack of research examining the determinants of this phenomenon. Previous studies addressing weapon possession have primarily focused on either K-12 or the general adult population. Unlike previous studies, this study examined the weapon possession among college students using data collected from a mid-sized university in Missouri, and 451 students participated. Weapon possession and other theoretical factors were measured through the self-administered survey. Logistical regression analysis revealed that weapon socialization was the most significant factor in predicting student weapon carrying. Also, gender and age were significant factors in explaining campus-based weapon possession. This research has a limitation with generalizability because the data were collected from only a single university with convenient sampling. Future studies need to cover a wider range of college students from a variety of different universities with random sampling.

  6. Handheld ultrasound concealed weapons detector

    Science.gov (United States)

    Felber, Franklin S.; Wild, Norbert C.; Nunan, Scott C.; Breuner, Dennis; Doft, Frank

    1998-12-01

    A handheld, battery-operated prototype of a remove concealed weapons detector has been built and tested. The concealed weapons detector will enable law enforcement and security officers to detect metallic and nonmetallic weapons concealed beneath clothing remotely from beyond arm's length to about 20 feet. These detectors may be used to: (1) allow hands-off, stand-off frisking of suspects for metallic and nonmetallic weapons; and (2) search for metallic and nonmetallic weapons on cooperative subjects at courthouse entrances and other monitored security portals. We have demonstrated that we image weapons concealed under heavy clothing, not just detect them, at ranges up to 15 feet using the same ultrasound frequency (40 kHz) used by commercial rangefinders. The concealed weapons detector operates much as a rangefinder, but at higher peak fluxes and pulse repetition frequencies. The detector alerts the user to concealed weapons audibly and visibly by detecting ultrasound glints above a body/clothing baseline, and by compensating for changing range and attenuation. The detector locates concealed weapons within a 6-inch illuminated spot at 10 feet. The signal processor eliminates any signal from behind the target.

  7. Thought on Weapons and Equipments Research and Production in Civil-military Integrated Development%武器装备科研生产军民融合式发展思考

    Institute of Scientific and Technical Information of China (English)

    赵洪利; 李睿

    2013-01-01

    Constructing the civil-military integrated weapons and equipments research and production system is the necessary requisition for implementing history mission effectively of the army in new century and wining local war in informational condition.The civil-military integrated development of weapons and equipments research and production is deeply researched,some measures and suggestion are brought forward from four ways such as breaking industry bulwark,unifying military and civil standards,erecting intercommunicative flat and completing run mechanism.%建立军民融合、寓军于民的武器装备科研生产体系,是有效履行新世纪新阶段我军历史使命、打赢信息化条件下局部战争的必然要求.从打破行业壁垒、统一军民标准、搭建互动平台、完善运行机制4个方面对武器装备科研生产军民融合式发展进行了深入探讨,并提出了措施建议.

  8. Development of detector for neutron monitor of wide energy range. Joint research

    CERN Document Server

    Kim, E; Nakamura, T; Rasolonjatovo, D R D; Shiomi, T; Tanaka, S; Yamaguchi, Y; Yoshizawa, M

    2002-01-01

    Radiation monitoring of neutrons in high-power proton accelerator facilities is very important for radiation safety management for workers and members of the public. In the present study, a neutron detector that can evaluate dose of neutrons in the energy range from thermal energy to 100MeV was developed using an organic liquid scintillator, a boron-loaded scintillator and a sup 6 Li glass scintillator. First, a method was developed to evaluate neutron doses above several MeV by a spectrum weight function (G-function) which is applied to the organic liquid scintillator, and the validity of the methods was confirmed by dose evaluation in some neutron fields. Second, the G-function was applied to the boron-loaded scintillator which detects thermal neutrons by sup 1 sup 0 B(n, alpha) sup 7 Li reaction, in order to expand the covering neutron energy range. The response function and the G-function of the scintillator were evaluated by experiment and calculation, and the characteristics of dose measurement were ana...

  9. Boron neutron capture therapy of malignant brain tumors at the Brookhaven Medical Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Joel, D.D.; Coderre, J.A.; Chanana, A.D. [Brookhaven National Lab., Upton, NY (United States). Medical Dept.

    1996-12-31

    Boron neutron capture therapy (BNCT) is a bimodal form of radiation therapy for cancer. The first component of this treatment is the preferential localization of the stable isotope {sup 10}B in tumor cells by targeting with boronated compounds. The tumor and surrounding tissue is then irradiated with a neutron beam resulting in thermal neutron/{sup 10}B reactions ({sup 10}B(n,{alpha}){sup 7}Li) resulting in the production of localized high LET radiation from alpha and {sup 7}Li particles. These products of the neutron capture reaction are very damaging to cells, but of short range so that the majority of the ionizing energy released is microscopically confined to the vicinity of the boron-containing compound. In principal it should be possible with BNCT to selectively destroy small nests or even single cancer cells located within normal tissue. It follows that the major improvements in this form of radiation therapy are going to come largely from the development of boron compounds with greater tumor selectivity, although there will certainly be advances made in neutron beam quality as well as the possible development of alternative sources of neutron beams, particularly accelerator-based epithermal neutron beams.

  10. Boron neutron capture therapy of malignant brain tumors at the Brookhaven Medical Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Joel, D.D.; Coderre, J.A.; Chanana, A.D. [Brookhaven National Lab., Upton, NY (United States). Medical Dept.

    1996-12-31

    Boron neutron capture therapy (BNCT) is a bimodal form of radiation therapy for cancer. The first component of this treatment is the preferential localization of the stable isotope {sup 10}B in tumor cells by targeting with boronated compounds. The tumor and surrounding tissue is then irradiated with a neutron beam resulting in thermal neutron/{sup 10}B reactions ({sup 10}B(n,{alpha}){sup 7}Li) resulting in the production of localized high LET radiation from alpha and {sup 7}Li particles. These products of the neutron capture reaction are very damaging to cells, but of short range so that the majority of the ionizing energy released is microscopically confined to the vicinity of the boron-containing compound. In principal it should be possible with BNCT to selectively destroy small nests or even single cancer cells located within normal tissue. It follows that the major improvements in this form of radiation therapy are going to come largely from the development of boron compounds with greater tumor selectivity, although there will certainly be advances made in neutron beam quality as well as the possible development of alternative sources of neutron beams, particularly accelerator-based epithermal neutron beams.

  11. Role of IUC-DAEF in promoting neutron beam research in India

    Indian Academy of Sciences (India)

    P S Goyal

    2004-07-01

    Inter University Consortium for Department of Atomic Energy Facilities (IUC-DAEF) is an autonomous institute of the University Grants Commission and provides an interface between the university fraternity and the institutions of Department of Atomic Energy. Mumbai Centre of IUC-DAEF promotes and supports the use of neutron facilities at Dhruva reactor by the university scientists. To augment the existing neutron scattering facilities, IUC-DAEF has developed a neutron beam line at Dhruva reactor. The present paper gives a brief survey of the activities and achievements of Mumbai Centre of IUC-DAEF.

  12. Insulin as a weapon.

    Science.gov (United States)

    Robinson, Samuel D; Safavi-Hemami, Helena

    2016-12-01

    The discovery of insulin and its use for the treatment of diabetes is undoubtedly one of the true successes of modern medicine. Injectable insulin would prove the first effective treatment for a previously incurable and usually fatal disease. Soon after however, the powerful effects of insulin overdose would be reported, and subsequently exploited for dubious medical and sometimes nefarious purposes. In this article we describe the discovery that certain venomous marine snails of the genus Conus also exploit the powerful effects of insulin overdose, employing it as a weapon for prey capture. Copyright © 2016 Elsevier Ltd. All rights reserved.

  13. A neutronic feasibility study for LEU conversion of the IR-8 research reactor.

    Energy Technology Data Exchange (ETDEWEB)

    Deen, J. R.

    1998-10-22

    Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), and LEU (19.75%) fuel assembly (FA) designs using three dimensional multi-group diffusion theory models benchmarked to detailed Monte Carlo models of the reactor. Comparisons were made of changes in reactivity, cycle length, average {sup 235}U discharge burnup, thermal neutron flux, and control rod worths for the 90% and 36% enriched IRT-3M fuel assembly and the 19.75% enriched IRT-4M fuel assembly with the same fuel management strategy. The results of these comparisons showed that a uranium density of 3.5 g/cm{sup 3} in the fuel meat would be required in the LEU IRT-4M fuel assembly to match the cycle length of the HEU(90%) IRT-3M FA and an LEU density of 3.7 g/cm{sup 3} is needed to match the cycle length of the HEU(36%) IRT-3M FA.

  14. Research on the Reliability Model of Light Weapons Life%轻武器寿命可靠性模型研究

    Institute of Scientific and Technical Information of China (English)

    白俊敏; 董富强; 曾妍

    2016-01-01

    为轻武器寿命可靠性评定提供理论依据,运用经典的可靠性理论,将轻武器装备寿命试验归结为可修复系统的有替换定时截尾试验,通过分析某型机枪的寿命试验数据,对母体寿命可能的分布类型作出假设,选择字2检验法对假设进行拟合优度检验,利用最小二乘法得出对应分布的线性相关系数,通过比较确定母体分布类型,建立了该型机枪寿命的可靠性数学模型,对同类轻武器装备的可靠性指标评定提供了一定的参考。%To provide a theoretical basis of the reliability evaluation for light weapons life,using the classical eliability theory,put the light weapons life test down to a replacement time censored test of the repairable system,through the analysis on life test data of a certain type of machine gun,make assumptions about the possible type of distribution of maternal life, select Chi-square test method to make the goodness of fit test for the hypotheses,compute the linear correlation coefficient of distribution by the least square method,confirm parent distribution types through the comparison,build reliability mathematics model for this type of machine gun life,to provide a certain reference for the reliability index evaluation of the similar light weapon equipment.

  15. Optimization of Neutron Spectrum in Northwest Beam Tube of Tehran Research Reactor for BNCT, by MCNP Code

    Energy Technology Data Exchange (ETDEWEB)

    Zamani, M. [National Radiation Protection Department - NRPD, Atomic Energy Organization of Iran - AEOI, Tehran (Iran, Islamic Republic of); End of North Kargar st, Atomic Energy Organization of Iran, P.O. Box: 14155-1339, Tehran (Iran, Islamic Republic of); Kasesaz, Y.; Khalafi, H.; Shayesteh, M. [Radiation Application School, Nuclear Science and Technology Research Institute, AEOI, Tehran (Iran, Islamic Republic of)

    2015-07-01

    In order to gain the neutron spectrum with proper components specification for BNCT, it is necessary to design a Beam Shape Assembling (BSA), include of moderator, collimator, reflector, gamma filter and thermal neutrons filter, in front of the initial radiation beam from the source. According to the result of MCNP4C simulation, the Northwest beam tube has the most optimized neuron flux between three north beam tubes of Tehran Research Reactor (TRR). So, it has been chosen for this purpose. Simulation of the BSA has been done in four above mentioned phases. In each stage, ten best configurations of materials with different length and width were selected as the candidates for the next stage. The last BSA configuration includes of: 78 centimeters of air as an empty space, 40 centimeters of Iron plus 52 centimeters of heavy-water as moderator, 30 centimeters of water or 90 centimeters of Aluminum-Oxide as a reflector, 1 millimeters of lithium (Li) as thermal neutrons filter and finally 3 millimeters of Bismuth (Bi) as a filter of gamma radiation. The result of Calculations shows that if we use this BSA configuration for TRR Northwest beam tube, then the best neutron flux and spectrum will be achieved for BNCT. (authors)

  16. Evaluation for status and utilization of neutron activation analysis facility of HANARO research reactor (1996-2003)

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Chung, Young Ju; Kim, Sun Ha; Baek, Sung Ryel; Cho, Hyun Je; Park, Kwang Won; Kang, Sang Hun; Lim, Jong Myoung; Kim, Young Jin

    2004-05-01

    This report is written for the evaluation of the utilization and the status of Neutron Activation Analysis (NAA) facility of HANARO research reactor (1996-2003) which is accomplished by NAA user supporting system ; (i) the results by the number of sample is classified the research and development and analytical service, each item which is divided into the type of supporting (component analysis, nuclide analysis, neutron irradiation) and the field of utilization (environment, human health, industrial materials, standard materials, social and culture and others) are summarized with relevant contents in detail, (ii) The trends of the utilization is evaluated with a technology, a field, an organization of utilization, (iii) the results of training and education for students and users, the survey of user's demand, the investigation of self-satisfaction for NAA user supporting system.

  17. Modern trends in the development of position sensitive neutron detectors for condensed matter research

    Indian Academy of Sciences (India)

    A V Belushkin

    2008-10-01

    Different types of neutron scattering experiment for the study of condensed matter properties pose specific and often contradictory requirements for detector characteristics. There is no single type of detector which satisfies all the criteria. Therefore, compromise is inevitable and some of the characteristics are trade off in favour of others. Present report gives an overview of detector systems presently operating at the leading neutron scattering facilities as well as some development work around the globe.

  18. Naval Weapons Station Earle Reassessment

    Science.gov (United States)

    2013-12-01

    surveys for their Section 110 compliance: Architectural Resources Survey, Naval Weapons Station Earle, Monmouth County, New Jersey (Louis Berger 1999...text within brackets. Berger Report 1999 Architectural Resources Survey, Naval Weapons Station Earle, Monmouth County, New Jersey (Louis Berger... architectural treatment of buildings at NWS Earle: a traditional vernacular theme with minimal decorative detailing. This so-called minimal traditional

  19. Proportionality and Autonomous Weapons Systems

    NARCIS (Netherlands)

    van den Boogaard, J.

    2015-01-01

    Given the swift technologic development, it may be expected that the availability of the first truly autonomous weapons systems is fast approaching. Once they are deployed, these weapons will use artificial intelligence to select and attack targets without further human intervention. Autonomous

  20. Proportionality and Autonomous Weapons Systems

    NARCIS (Netherlands)

    van den Boogaard, J.

    2015-01-01

    Given the swift technologic development, it may be expected that the availability of the first truly autonomous weapons systems is fast approaching. Once they are deployed, these weapons will use artificial intelligence to select and attack targets without further human intervention. Autonomous weap

  1. Development of the JAERI computational dosimetry system (JCDS) for boron neutron capture therapy. Cooperative research

    CERN Document Server

    Kumada, H; Matsumura, A; Nakagawa, Y; Nose, T; Torii, Y; Uchiyama, J; Yamamoto, K; Yamamoto, T

    2003-01-01

    The Neutron Beam Facility at JRR-4 enables us to carry out boron neutron capture therapy with epithermal neutron beam. In order to make treatment plans for performing the epithermal neutron beam BNCT, it is necessary to estimate radiation doses in a patient's head in advance. The JAERI Computational Dosimetry System (JCDS), which can estimate distributions of radiation doses in a patient's head by simulating in order to support the treatment planning for epithermal neutron beam BNCT, was developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images, and that generates a input data file automatically for calculation of neutron flux and gamma-ray dose distributions in the brain with the Monte Carlo code MCNP, and that displays these dose distributions on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By using CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is...

  2. Musculoskeletal colloquialisms based on weapons.

    Science.gov (United States)

    Agrawal, Anuj

    2017-01-01

    Eponyms and colloquialisms are commonly used in orthopaedic literature and convey a great deal of information in a concise fashion. Several orthopaedic conditions have characteristic clinical or radiologic appearances, mimicking the appearance of certain arms or weapons. Most of these are easy to memorise and recognise, provided the orthopaedic surgeon is aware of the colloquialism and familiar with the appearance of the weapon on which it is based. Unfortunately, many such colloquialisms are based on traditional weapons no longer in current use, and their appearances are not familiar to most orthopaedists, creating confusion and difficulty in understanding them. In this paper, we have reviewed the musculoskeletal colloquialisms based on weapons, including a brief description of the weapon with illustrations, highlighting the importance of the colloquialism in diagnosis or treatment of musculoskeletal conditions.

  3. Nuclear weapon reliability evaluation methodology

    Energy Technology Data Exchange (ETDEWEB)

    Wright, D.L. [Sandia National Labs., Albuquerque, NM (United States)

    1993-06-01

    This document provides an overview of those activities that are normally performed by Sandia National Laboratories to provide nuclear weapon reliability evaluations for the Department of Energy. These reliability evaluations are first provided as a prediction of the attainable stockpile reliability of a proposed weapon design. Stockpile reliability assessments are provided for each weapon type as the weapon is fielded and are continuously updated throughout the weapon stockpile life. The reliability predictions and assessments depend heavily on data from both laboratory simulation and actual flight tests. An important part of the methodology are the opportunities for review that occur throughout the entire process that assure a consistent approach and appropriate use of the data for reliability evaluation purposes.

  4. Assessment of the implementation of a neutron measurement system during the commissioning of the Jordan Research and Training Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Bae, Sang Hoon; Suh, Sang Mun [Division of Research Reactor System Design, Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Cha, Han Ju [Dept. of Electrical Engineering, Intelligent Power Conversion Laboratory, Chungnam National University, Daejeon (Korea, Republic of)

    2017-04-15

    The Jordan Research and Training Reactor (JRTR) is the first research reactor in Jordan, the commissioning of which is ongoing. The reactor is a 5-MWth, open-pool type, light-water-moderated, and cooled reactor with a heavy water reflector system. The neutron measurement system (NMS) applied to the JRTR employs a wide-range fission chamber that can cover from source range to power range. A high-sensitivity boron trifluoride counter was added to obtain more accurate measurements of the neutron signals and to calibrate the log power signals; the NMS has a major role in the entire commissioning stage. However, few case studies exist concerning the application of the NMS to a research reactor. This study introduces the features of the NMS and the boron trifluoride counter in the JRTR and shares valuable experiences from lessons learned from the system installation to its early commissioning. In particular, the background noise relative to the signal-to-noise ratio and the NMS signal interlock are elaborated. The results of the count rates with the neutron source and the effects of the discriminator threshold are summarized.

  5. 面向典型武器系统的作战能力评估研究%Research on the Combat Capability Evaluation for Typical Weapon

    Institute of Scientific and Technical Information of China (English)

    王巧珍; 杨凡德

    2011-01-01

    On the basis of the characteristics of a typical laser weapons overseas, the paper establishes a corresponding evaluation index system. For the limitation of the analytic network process (ANP), the optimal transfer matrix is intruded to improve it and then the improved ANP is applied to the combat capability evaluation for the laser weapons, which proves validity of the method and rationality of the index system.%在分析国外某典型激光武器系统特性的基础上,建立了其作战能力评估指标体系.利用最优传递矩阵对网络层次分析法(analytic network process,ANP)存在的缺陷进行了改进,将该方法应用到该武器系统作战能力评估过程中,验证了该方法的有效性和指标体系的合理性.

  6. 坦克分队动态火力优化配置建模%Research on the Model of Dynamic Weapon Target Assignment for Tank Unit

    Institute of Scientific and Technical Information of China (English)

    徐克虎; 黄大山; 王天召

    2013-01-01

      充分考虑信息化战场上坦克分队战斗中我方作战单元、目标及战场环境等因素的影响,依据火力单元的战场感知能力、射击命中概率与目标的防护能力、战场价值确定射击价值,依据火力单元的战场机动时间和射击预留时间确定射击时机,建立动态火力优化配置模型。%The weapon and environment features in informationization battlefield have been considered sufficiently to analyse shooting value and shooting time. The shooting value was determined by the battlefield awareness ability and hit probability of fire unit and the protection ability and battlefield value of target. The shooting time was determined by the appointed-motion time and scheduled time of fire unit. The model of dynamic weapon target assignment has been established based on the two above-mentioned elements.

  7. Pakistan’s Nuclear Weapons: Proliferation and Security Issues

    Science.gov (United States)

    2010-10-07

    on Fissile Materials http://www.fissilematerials.org/ipfm/ site_down/gfmr07.pdf; SIPRI Yearbook 2007. The International Panel on Fissile Materials...State for Foreign and Commonwealth Affairs David Miliband told the Charlie Rose Show December 15, 2008, that Islamabad’s nuclear weapons “are under...Weapons in Pakistan,” Pakistan Security Research Unit Brief Number 22, University of Bradford, November 18, 2007. Available at http://spaces.brad.ac.uk

  8. Adversarial Use of Weapons of Mass Destruction

    Science.gov (United States)

    2000-01-01

    had weaponized 10,000 liters of concentrated botu- linum toxin, 6,500 liters of concentrated anthrax, and 1,580 liters of concentrated aflatoxin .2 The...might cost only $30–50 million, according to the Research Institute for the Study of Conflict and Terrorism. That could be cut in half if safety ...10 Most nations pursuing NBC capabilities today are also consider- ing long-range delivery means. On the strategic level adversaries are likely to use

  9. Research on Test Method of Ship-Borne Torpedo Defence Weapon System Intercepting Torpedo in Sea Trial%舰载鱼雷防御武器系统拦截实航鱼雷试验方法

    Institute of Scientific and Technical Information of China (English)

    侯宝娥; 陈高杰

    2014-01-01

    Based on the test destination of ship-borne torpedo defence weapon system intercepting torpedo in sea trial,this paper first introduces the system constitution and working principle briefly. And then,the feasible test sea -lanes are researched and designed. Lastly,the concrete test implementary scheme,data-processing and result assessment are proposed. The method can guide the torpedo defense fighting and the operating of torpedo defense weapon system.%针对舰载鱼雷防御武器系统拦截实航鱼雷试验目的,在简单介绍系统组成及工作原理的基础上,研究设计了可行的试验航路,并提出具体的试验实施方案、试验数据处理及结果评定方法。对水面舰的鱼雷防御作战、鱼雷防御武器系统的使用有一定的指导意义。

  10. Feasibility Study on the Use of Small-Angle Neutron Scattering for Microstructural Determinations of Technological Alloys, Carried out at Atomic Weapons Research Establishment (AWRE), Aldermaston, England.

    Science.gov (United States)

    1978-01-01

    currently being) studied : 1. Titanium Alloy from Disc Section-Fatigue (Ti-6-.4). 2. HY-130; Hydrogen Embrittlement of Notched Specimen. 3. Stainless...Isostatic Pressed Superalloy 4 A. UDIMET 700 B. Dr. V. Wilms , MTU, Mun ich C. Heat treated and agei ng of HIPPID UDIMET 700 0. SANS shows excellent...Miscellaneous Superalloys Inco loy , Has tel loy, HI PPED al loys , Incone l (cree p failure specimen) are currently under study at AWRE. Some preliminary

  11. Development of Pneumatic Transfer Irradiation Facility (PTS no.3) for Neutron Activation Analysis at HANARO Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Y. S.; Moon, J. H.; Kim, S. H.; Sun, G. M.; Baek, S. Y.; Kim, H. R.; Kim, Y. J

    2008-04-15

    A pneumatic transfer system (PTS) is one of the most important facilities used during neutron irradiation of a target material for instrumental neutron activation analysis (INAA) in a research reactor. In particular, a fast pneumatic transfer system is essential for the measurement of a short half-life nuclide. The pneumatic transfer irradiation system (PTS no.3) involving a manual system and an semi-automatic system were reconstructed with new designs of a functional improvement at the HANARO research reactor and NAA laboratory of RI building in 2006. In this technical report, the design, operation and control of these system (PTS no.3) was described. Also the experimental results and the characteristic parameters measured from a functional operation test and an irradiation test of these systems, such as the transfer time of irradiation capsule, the different neutron flux, the temperature of the irradiation position with an irradiation time, the radiation dose rate when the rabbit is returned, etc. are reported to provide a user information as well as a reactor's management and safety.

  12. Development of a cryogenic load frame for the neutron diffractometer at Takumi in Japan Proton Accelerator Research Complex

    Energy Technology Data Exchange (ETDEWEB)

    Jin, Xinzhe; Nakamoto, Tatsushi; Ogitsu, Toru; Yamamoto, Akira; Sugano, Michinaka [High Energy Accelerator Research Organization (KEK), Tsukuba, Ibaraki 305-0801 (Japan); Harjo, Stefanus; Aizawa, Kazuya; Abe, Jun; Gong, Wu; Iwahashi, Takaaki [Japan Atomic Energy Agency, Tokai-mura, Naka-gun, Ibaraki 319-1195 (Japan); Hemmi, Tsutomu [Japan Atomic Energy Agency, Naka-shi, Ibaraki 311-0193 (Japan); Umeno, Takahiro [Taiyo Nippon Sanso Corporation, Tsukuba, Ibaraki 306-2611 (Japan)

    2013-06-15

    To prepare for projects such as the Large Hadron Collider upgrade, International Thermonuclear Experimental Reactor and Demonstration reactor, it is important to form a clear understanding of stress-strain properties of the materials that make up superconducting magnets. Thus, we have been studying the mechanical properties of superconducting wires using neutron diffraction measurements. To simulate operational conditions such as temperature, stress, and strain, we developed a cryogenic load frame for stress-strain measurements of materials using a neutron diffractometer at Japan Proton Accelerator Research Complex (J-PARC) Takumi beam line. The maximum load that can be applied to a sample using an external driving machine is 50 kN. Using a Gifford-MacMahon cryocooler, samples can be measured down to temperatures below 10 K when loaded. In the present paper, we describe the details of the cryogenic load frame with its test results by using type-304 stainless steel wire.

  13. Research and development of a compact discharge-driven D-D fusion neutron source for explosive detection

    Energy Technology Data Exchange (ETDEWEB)

    Yoshikawa, Kiyoshi [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan)]. E-mail: kiyoshi@iae.kyoto-u.ac.jp; Masuda, Kai [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan); Takamatsu, Teruhisa [Institute of Advanced Energy, Kyoto University, Uji, Kyoto (Japan); Shiroya, Seiji [Research Reactor Institute, Kyoto University, Kumatori, Osaka (Japan); Misawa, Tsuyoshi [Research Reactor Institute, Kyoto University, Kumatori, Osaka (Japan); Hotta, Eiki [Department of Energy Sciences, Tokyo Institute of Technology, Yokohama (Japan); Ohnishi, Masami [Department of Electrical Engineering and Computer Science, Kansai University, Suita, Osaka (Japan); Yamauchi, Kunihito [Department of Energy Sciences, Tokyo Institute of Technology, Yokohama (Japan); Osawa, Hodaka [Department of Electrical Engineering and Computer Science, Kansai University, Suita, Osaka (Japan); Takahashi, Yoshiyuki [Research Reactor Institute, Kyoto University, Kumatori, Osaka (Japan)

    2007-08-15

    Current results are described on the research and development of the advanced humanitarian landmine detection system by using a compact discharge-type fusion neutron source called IECF (Inertial-Electrostatic Confinement fusion) devices. With a 50 mm-thick water-jacketed IEC device (IEC20C) of a 200 mm inner diameter, it can produce 10{sup 7} neutrons/s stably in CW mode for 80 kV and 80 mA. Ample 10.8 MeV {gamma}-rays produced through (n, {gamma}) reaction with nitrogen atoms in the melamine (C{sub 3}H{sub 6}N{sub 6}) powder (explosive simulant) are clearly measured by a BGO-NaI-combined scintillation sensor with distinct difference in cases with and without melamine. This proves feasibility of the identification of the buried landmines.

  14. Development of a cryogenic load frame for the neutron diffractometer at Takumi in Japan Proton Accelerator Research Complex.

    Science.gov (United States)

    Jin, Xinzhe; Nakamoto, Tatsushi; Harjo, Stefanus; Hemmi, Tsutomu; Umeno, Takahiro; Ogitsu, Toru; Yamamoto, Akira; Sugano, Michinaka; Aizawa, Kazuya; Abe, Jun; Gong, Wu; Iwahashi, Takaaki

    2013-06-01

    To prepare for projects such as the Large Hadron Collider upgrade, International Thermonuclear Experimental Reactor and Demonstration reactor, it is important to form a clear understanding of stress-strain properties of the materials that make up superconducting magnets. Thus, we have been studying the mechanical properties of superconducting wires using neutron diffraction measurements. To simulate operational conditions such as temperature, stress, and strain, we developed a cryogenic load frame for stress-strain measurements of materials using a neutron diffractometer at Japan Proton Accelerator Research Complex (J-PARC) Takumi beam line. The maximum load that can be applied to a sample using an external driving machine is 50 kN. Using a Gifford-MacMahon cryocooler, samples can be measured down to temperatures below 10 K when loaded. In the present paper, we describe the details of the cryogenic load frame with its test results by using type-304 stainless steel wire.

  15. In vitro biological effectiveness of JRR-4 epithermal neutron beam. Experiment under free air beam and in water phantom. Cooperative research

    CERN Document Server

    Yamamoto, T; Horiguchi, Y; Kishi, T; Kumada, H; Matsumura, A; Nose, T; Torii, Y; Yamamoto, K

    2002-01-01

    The surviving curve and the biological effectiveness factor of dose components generated in boron neutron capture therapy (BNCT) were separately determined in neutron beams at Japan Research Reactor No.4. Surviving fraction of V79 Chinese hamster cell with or without sup 1 sup 0 B was obtained using an epithermal neutron beam (ENB), a mixed thermal-epithermal neutron beam (TNB-1), and a thermal neutron beam (TNB-2), which were used or planned to use for BNCT clinical trial. The cell killing effect of these neutron beams with or without the presence of sup 1 sup 0 B depended highly on the neutron beam used, according to the epithermal and fast neutron content in the beam. The biological effectiveness factor values of the boron capture reaction for ENB, TNB-1 and TNB-2 were 3.99+-0.24, 3.04+-0.19 and 1.43+-0.08, respectively. The biological effectiveness factor values of the high-LET dose components based on the hydrogen recoils and the nitrogen capture reaction were 2.50+-0.32, 2.34+-0.30 and 2.17+-0.28 for EN...

  16. Computational analysis of neutronic parameters for TRIGA Mark-II research reactor using evaluated nuclear data libraries

    Energy Technology Data Exchange (ETDEWEB)

    Uddin, M.N. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh); Sarker, M.M., E-mail: sarker_md@yahoo.co [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Khan, M.J.H. [Reactor Physics and Engineering Division, Institute of Nuclear Science and Technology, Atomic Energy Research Establishment, Ganakbari, Savar, GPO Box 3787, Dhaka-1000 (Bangladesh); Islam, S.M.A. [Department of Physics, Jahangirnagar University, Dhaka (Bangladesh)

    2010-03-15

    The aim of this study is to analyze the neutronic parameters of TRIGA Mark-II research reactor using the chain of NJOY-WIMS-CITATION computer codes based on evaluated nuclear data libraries CENDL-2.2 and JEFF-3.1.1. The nuclear data processing code NJOY99.0 has been employed to generate the 69 group WIMS library for the isotopes of TRIGA core. The cell code WIMSD-5B was used to generate the cross sections in CITATION format and then 3-dimensional diffusion code CITTATION was used to calculate the neutronic parameters of the TRIGA Mark-II research reactor. All the analyses were performed using the 7-group macroscopic cross section library. The CITATION test-runs using different cross section sets based on different models applied in WIMS calculations have shown a strong influence of those models on the final integral parameters. Some of the cells were specially treated with PRIZE options available in WIMSD-5B to take into account the fine structure of the flux gradient in the fuel-reflector interface region. It was observed that two basic parameters, the effective multiplication factor, k{sub eff} and the thermal neutron flux, were in good agreement among the calculated results with each other as well as the measured values. The maximum power densities at the hot spot were 1.0446E02 W/cc and 1.0426E02 W/cc for the libraries CENDL-2.2 and JEFF-3.1.1 respectively. The calculated total peaking factors 5.793 and 5.745 were compared to the original SAR value of 5.6325 as well as MCNP result. Consequently, this analysis will be helpful to enhance the neutronic calculations and also be used for the further thermal-hydraulics study of the TRIGA core.

  17. Neutronic and thermal-hydraulic analysis of new irradiation channels inside the Moroccan TRIGA Mark II research reactor core.

    Science.gov (United States)

    Chham, E; El Bardouni, T; Benaalilou, K; Boukhal, H; El Bakkari, B; Boulaich, Y; El Younoussi, C; Nacir, B

    2016-10-01

    This study was conducted to improve the capacity of radioisotope production in the Moroccan TRIGA Mark II research reactor, which is considered as one of the most important applications of research reactors. The aim of this study is to enhance the utilization of TRIGA core in the field of neutron activation and ensure an economic use of the fuel. The main idea was to create an additional irradiation channel (IC) inside the core. For this purpose, three new core configurations are proposed, which differ according to the IC position in the core. Thermal neutron flux distribution and other neutronic safety parameters such as power peaking factors, excess reactivity, and control rods worth reactivity were calculated using the Monte Carlo N-Particle Transport (MCNP) code and neutron cross-section library based on ENDF/B-VII evaluation. The calculated thermal flux in the central thimble (CT) and in the added IC for the reconfigured core is compared with the thermal flux in the CT of the existing core, which is taken as a reference. The results show that all the obtained fluxes in CTs are very close to the reference value, while a remarkable difference is observed between the fluxes in the new ICs and reference. This difference depends on the position of IC in the reactor core. To demonstrate that the Moroccan TRIGA reactor could safely operate at 2MW, with new configurations based on new ICs, different safety-related thermal-hydraulic parameters were investigated. The PARET model was used in this study to verify whether the safety margins are met despite the new modifications of the core. The results show that it is possible to introduce new ICs safely in the reactor core, because the obtained values of the parameters are largely far from compromising the safety of the reactor.

  18. Development of a polarized neutron beam line at Algerian research reactors using McStas software

    Science.gov (United States)

    Makhloufi, M.; Salah, H.

    2017-02-01

    Unpolarized instrumentation has long been studied and designed using McStas simulation tool. But, only recently new models were developed for McStas to simulate polarized neutron scattering instruments. In the present contribution, we used McStas software to design a polarized neutron beam line, taking advantage of the available spectrometers reflectometer and diffractometer in Algeria. Both thermal and cold neutron was considered. The polarization was made by two types of supermirrors polarizers FeSi and CoCu provided by the HZB institute. For sake of performance and comparison, the polarizers were characterized and their characteristics reproduced. The simulated instruments are reported. Flipper and electromagnets for guide field are developed. Further developments including analyzers and upgrading of the existing spectrometers are underway.

  19. Upgrade of the IGN-14 neutron generator for research on detection of fusion-plasma products

    Energy Technology Data Exchange (ETDEWEB)

    Igielski, Andrzej; Kurowski, Arkadiusz; Janik, Władysław; Gabańska, Barbara; Woźnicka, Urszula, E-mail: Urszula.Woznicka@ifj.edu.pl

    2015-10-11

    The fast neutron generator (IGN-14) at the Institute of Nuclear Physics of the Polish Academy of Sciences (IFJ PAN) in Kraków (Poland) is a laboratory multi-purpose experimental device. Neutrons are produced in a beam-target D–D or D–T reactions. A new vacuum chamber installed directly to the end of the ion guide of IGN-14 makes it possible to measure not only neutrons but also alpha particles in the presence of a mixed radiation field of other accompanying reaction products. The new experimental setup allows test detectors dedicated to spectrometric measurements of thermonuclear fusion reaction products. - Highlights: • Nuclear reactions at the target correspond to the fusion reaction in hot plasma. • Measuring vacuum chamber has been built and installed. • Spatial distribution of the particle mixed fields in chamber was calculated. • New experimental setup for tests of detectors dedicated to measure of fusion reaction products.

  20. Development of the JAERI computational dosimetry system (JCDS) for boron neutron capture therapy. Cooperative research

    Energy Technology Data Exchange (ETDEWEB)

    Kumada, Hiroaki; Yamamoto, Kazuyoshi; Torii, Yoshiya; Uchiyama, Junzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Matsumura, Akira; Yamamoto, Tetsuya; Nose, Tadao [Tsukuba Univ., Tsukuba, Ibaraki (Japan); Nakagawa, Yoshinobu [National Sanatorium Kagawa-Children' s Hospital, Kagawa (Japan); Kageji, Teruyoshi [Tokushima Univ., Tokushima (Japan)

    2003-03-01

    The Neutron Beam Facility at JRR-4 enables us to carry out boron neutron capture therapy with epithermal neutron beam. In order to make treatment plans for performing the epithermal neutron beam BNCT, it is necessary to estimate radiation doses in a patient's head in advance. The JAERI Computational Dosimetry System (JCDS), which can estimate distributions of radiation doses in a patient's head by simulating in order to support the treatment planning for epithermal neutron beam BNCT, was developed. JCDS is a software that creates a 3-dimentional head model of a patient by using CT and MRI images, and that generates a input data file automatically for calculation of neutron flux and gamma-ray dose distributions in the brain with the Monte Carlo code MCNP, and that displays these dose distributions on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By using CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal in the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System which can support to set the patient to an actual irradiation position swiftly and accurately. This report describes basic design of JCDS and functions in several processing, calculation methods, characteristics and performance of JCDS. (author)

  1. Fundamental neutron physics at LANSCE

    Energy Technology Data Exchange (ETDEWEB)

    Greene, G.

    1995-10-01

    Modern neutron sources and science share a common origin in mid-20th-century scientific investigations concerned with the study of the fundamental interactions between elementary particles. Since the time of that common origin, neutron science and the study of elementary particles have evolved into quite disparate disciplines. The neutron became recognized as a powerful tool for studying condensed matter with modern neutron sources being primarily used (and justified) as tools for neutron scattering and materials science research. The study of elementary particles has, of course, led to the development of rather different tools and is now dominated by activities performed at extremely high energies. Notwithstanding this trend, the study of fundamental interactions using neutrons has continued and remains a vigorous activity at many contemporary neutron sources. This research, like neutron scattering research, has benefited enormously by the development of modern high-flux neutron facilities. Future sources, particularly high-power spallation sources, offer exciting possibilities for continuing this research.

  2. Making Weapons for the Terracotta Army

    Directory of Open Access Journals (Sweden)

    Marcos Martinón-Torres

    2011-10-01

    Full Text Available The Terracotta Army of the First Emperor of China is one of the most emblematic archaeological sites in the world. Many questions remain about the logistics of technology, standardisation and labour organisation behind the creation of such a colossal construction in just a few decades over 2,000 years ago. An ongoing research project co-ordinated between the UCL Institute of Archaeology and the Emperor Qin Shihang's Terracotta Army Museum is beginning to address some of these questions. This paper outlines some results of the typological, metric, microscopic, chemical and spatial analyses of the 40,000 bronze weapons recovered with the Terracotta Warriors. Thanks to a holistic approach developed specifically for this project, it is possible to reveal remarkable aspects of the organisation of the Qin workforce in production cells, of the standardisation, efficiency and quality-control procedures employed, and of the sophisticated technical knowledge of the weapon-makers.

  3. Youths Carrying a Weapon or Using a Weapon in a Fight: What Makes the Difference?

    Science.gov (United States)

    Thurnherr, Judit; Michaud, Pierre-Andre; Berchtold, Andre; Akre, Christina; Suris, Joan-Carles

    2009-01-01

    The objective of this study was to characterize weapon-carrying adolescents and to assess whether weapon carriers differ from weapon users. Data were drawn from a cross-sectional school-based survey of 7548 adolescents aged 16-20 years in Switzerland. Youths carrying a weapon were compared with those who do not. Subsequently, weapon carriers were…

  4. Intense fusion neutron sources

    Science.gov (United States)

    Kuteev, B. V.; Goncharov, P. R.; Sergeev, V. Yu.; Khripunov, V. I.

    2010-04-01

    The review describes physical principles underlying efficient production of free neutrons, up-to-date possibilities and prospects of creating fission and fusion neutron sources with intensities of 1015-1021 neutrons/s, and schemes of production and application of neutrons in fusion-fission hybrid systems. The physical processes and parameters of high-temperature plasmas are considered at which optimal conditions for producing the largest number of fusion neutrons in systems with magnetic and inertial plasma confinement are achieved. The proposed plasma methods for neutron production are compared with other methods based on fusion reactions in nonplasma media, fission reactions, spallation, and muon catalysis. At present, intense neutron fluxes are mainly used in nanotechnology, biotechnology, material science, and military and fundamental research. In the near future (10-20 years), it will be possible to apply high-power neutron sources in fusion-fission hybrid systems for producing hydrogen, electric power, and technological heat, as well as for manufacturing synthetic nuclear fuel and closing the nuclear fuel cycle. Neutron sources with intensities approaching 1020 neutrons/s may radically change the structure of power industry and considerably influence the fundamental and applied science and innovation technologies. Along with utilizing the energy produced in fusion reactions, the achievement of such high neutron intensities may stimulate wide application of subcritical fast nuclear reactors controlled by neutron sources. Superpower neutron sources will allow one to solve many problems of neutron diagnostics, monitor nano-and biological objects, and carry out radiation testing and modification of volumetric properties of materials at the industrial level. Such sources will considerably (up to 100 times) improve the accuracy of neutron physics experiments and will provide a better understanding of the structure of matter, including that of the neutron itself.

  5. Development of computer software for neutron energy spectrum adjustment in research reactors

    Directory of Open Access Journals (Sweden)

    Iqbal Masood

    2009-01-01

    Full Text Available A computer program has been developed for neutron energy spectrum adjustment using the deconvolution method. The BUNKI-based algorithm has been implemented to converge quickly yielding calculated neutron energy spectrum which is in good agreement with theoretical predictions. The foil activation data have been used as an input for each unfolding technique and various activation foils including Au-197, Al-27, Ni-58, Co-59, and Mg-24 covering thermal to fast energy range have been utilized. The group cross-section values were derived from the data given in the pre-processed cross-section libraries in ENDF-6 format of IRDF-90/NMF-G. Firstly, virtual approach was used for neutron energy spectrum adjustment. In this case, the activity of foils before and after the adjustment was almost the same but the flux had the maximum error of 14%. Secondly, the experimental measured activity of the threshold foils was then used for a real system. The activity of the threshold foils before and after the neutron energy adjustment had the maximum error of 33%.

  6. Research on pinches driven by Speed-2 generator: Hard X-ray and neutron emission in plasma focus configuration

    Energy Technology Data Exchange (ETDEWEB)

    Soto, L.; Moreno, J.; Silva, P.; Sylvester, G.; Zambra, M.; Pavez, C. [Comision Chilena de Energia Nuclear, Santiago (Chile); Pavez, C. [Universidad de Concepcion (Chile); Raspa, V. [Buenos Aires Univ., PLADEMA, CONICET and INFIP (Argentina); Castillo, F. [Insitituto de Ciencias Nucleares, UNAM (Mexico); Kies, W. [Heinrich-Heine-Univ., Dusseldorf (Germany)

    2004-07-01

    Speed-2 is a generator based on Marx technology and was designed in the University of Dusseldorf. Speed-2 consists on 40 +/- Marx modules connected in parallel (4.1 {mu}F equivalent Marx generator capacity, 300 kV, 4 MA in short circuit, 187 kJ, 400 ns rise time, dI/dt {approx} 10{sup 13} A/s). Currently Speed-2 is operating at CCHEN (Chilean nuclear energy commission), being the most powerful and energetic device for dense transient plasma in the Southern Hemisphere. Most of the previous works developed in Speed-2 at Dusseldorf were done in a plasma focus configuration for soft X-ray emission and the neutron emission from Speed-2 was not completely studied. The research program at CCHEN considers experiments in different pinch configurations (plasma focus, gas puffed plasma focus, gas embedded Z-pinch, wire arrays) at current of hundred of kilo- to mega-amperes, using the Speed-2 generator. The Chilean operation has begun implementing and developing diagnostics in a conventional plasma focus configuration operating in deuterium in order to characterize the neutron emission and the hard X-ray production. Silver activation counters, plastics CR39 and scintillator-photomultiplier detectors are used to characterize the neutron emission. Images of metallic plates with different thickness are obtained on commercial radiographic film, Agfa Curix ST-G2, in order to characterize an effective energy of the hard X-ray outside of the discharge. (authors)

  7. Risk in the Weapons Stockpile

    Energy Technology Data Exchange (ETDEWEB)

    Noone, Bailey C [Los Alamos National Laboratory

    2012-08-14

    When it comes to the nuclear weapons stockpile, risk must be as low as possible. Design and care to keep the stockpile healthy involves all aspects of risk management. Design diversity is a method that helps to mitigate risk.

  8. Research Progress in Silicon Carbide Neutron Detector%SiC中子探测器的研究进展

    Institute of Scientific and Technical Information of China (English)

    胡青青; 杨俊; 刘国福; 罗晓亮

    2012-01-01

    相比于气体、闪烁体及常规半导体中子探测器,基于第三代半导体材料SiC的中子探测器具有体积小、响应快、位置分辨率好、抗高温和耐辐照等众多优点.其中抗高温和耐辐照是应用于核反应堆堆芯、高能物理试验和太空等高温高压以及强辐射环境下的中子探测器需要突破的瓶颈.论文总结和分析了SiC的材料特性,SiC中子探测器的结构、工作原理、国内外发展现状以及存在的问题,并对我国中子探测器的发展趋势进行了探讨.%The detectors which are based on the third era semiconductor material SiC offer several important advantages over gas, scintillator and conventional semiconductor neutron detectors, such as compact size, faster charge - collection times, better location and spatial resolution, temperature and radiation hardness et al. A detector capable of operating at elevated temperatures and in high radiation fields including nuclear reactors, high - energy physical experiment and outer space, is the chokepoint that neutron detector need to break through. This article introduces the properties of the epitaxial silicon carbide material, SiC neutron detector configuration , work principle, also summarizes and analyses recent researches and problems need to solve of SiC neutron detector at home and abroad. At last,discusses the developing direction of radiation detectors in the interior.

  9. A high performance neutron powder diffractometer at 3 MW Triga Mark-II research reactor in Bangladesh

    Science.gov (United States)

    Kamal, I.; Yunus, S. M.; Datta, T. K.; Zakaria, A. K. M.; Das, A. K.; Aktar, S.; Hossain, S.; Berliner, R.; Yelon, W. B.

    2016-07-01

    A high performance neutron diffractometer called Savar Neutron Diffractometer (SAND) was built and installed at radial beam port-2 of TRIGA Mark II research reactor at AERE, Savar, Dhaka, Bangladesh. Structural studies of materials are being done by this technique to characterize materials crystallograpohically and magnetically. The micro-structural information obtainable by neutron scattering method is very essential for determining its technological applications. This technique is unique for understanding the magnetic behavior in magnetic materials. Ceramic, steel, electronic and electric industries can be benefited from this facility for improving their products and fabrication process. This instrument consists of a Popovicimonochromator with a large linear position sensitive detector array. The monochromator consists of nine blades of perfect single crystal of silicon with 6mm thickness each. The monochromator design was optimized to provide maximum flux on 3mm diameter cylindrical sample with a relatively flat angular dependence of resolution. Five different wave lengths can be selected by orienting the crystal at various angles. A sapphire filter was used before the primary collimator to minimize the first neutron. The detector assembly is composed of 15 linear position sensitive proportional counters placed at either 1.1 m or 1.6 m from the sample position and enclosed in a air pad supported high density polythene shield. Position sensing is obtained by charge division using 1-wide NIM position encoding modules (PEM). The PEMs communicate with the host computer via USB. The detector when placed at 1.1 m, subtends 30˚ (2θ) at each step and covers 120˚ in 4 steps. When the detector is placed at 1.6 m it subtends 20˚ at each step and covers 120˚ in 6 steps. The instrument supports both low and high temperature sample environment. The instrument supports both low and high temperature sample environment. The diffractometer is a state-of-the art technology

  10. The Weaponization of Social Media

    Science.gov (United States)

    2016-06-10

    media efforts will be compared to similar Western business and civic social media centric marketing efforts from both a technical and theoretical...THE WEAPONIZATION OF SOCIAL MEDIA A thesis presented to the Faculty of the U.S. Army Command and General Staff College in...The Weaponization of Social Media 5a. CONTRACT NUMBER 5b. GRANT NUMBER 5c. PROGRAM ELEMENT NUMBER 6. AUTHOR(S) Jack B. Irby III, MAJ 5d

  11. Training courses on neutron detection systems on the ISIS research reactor: on-site and through internet training

    Energy Technology Data Exchange (ETDEWEB)

    Lescop, B.; Badeau, G.; Ivanovic, S.; Foulon, F. [National Institute for Nuclear science and Technology French Atomic Energy and Alternative Energies Commission (CEA), Saclay Research Center, 91191 Gif-sur-Yvette (France)

    2015-07-01

    Today, ISIS research reactor is an essential tool for Education and Training programs organized by the National Institute for Nuclear Science and Technology (INSTN) from CEA. In the field of nuclear instrumentation, the INSTN offers both, theoretical courses and training courses on the use of neutron detection systems taking advantage of the ISIS research reactor for the supply of a wide range of neutron fluxes. This paper describes the content of the training carried out on the use of neutron detectors and detection systems, on-site or remote. The ISIS reactor is a 700 kW open core pool type reactor. The facility is very flexible since neutron detectors can be inserted into the core or its vicinity, and be used at different levels of power according to the needs of the course. Neutron fluxes, typically ranging from 1 to 10{sup 12} n/cm{sup 2}.s, can be obtained for the characterisation of the neutron detectors and detection systems. For the monitoring of the neutron density at low level of power, the Instrumentation and Control (I and C) system of the reactor is equipped with two detection systems, named BN1 and BN2. Each way contains a fission chamber, type CFUL01, connected to an electronic system type SIREX.The system works in pulse mode and exhibits two outputs: the counting rate and the doubling time. For the high level of power, the I and C is equipped with two detection systems HN1 and HN2.Each way contain a boron ionization chamber (type CC52) connected to an electronics system type SIREX. The system works in current mode and has two outputs: the current and the doubling time. For each mode, the trainees can observe and measure the signal at the different stages of the electronic system, with an oscilloscope. They can understand the role of each component of the detection system: detector, cable and each electronic block. The limitation of the detection modes and their operating range can be established from the measured signal. The trainees can also

  12. Weapon use increases the severity of domestic violence but neither weapon use nor firearm access increases the risk or severity of recidivism.

    Science.gov (United States)

    Folkes, Stephanie E F; Hilton, N Zoe; Harris, Grant T

    2013-04-01

    Use of weapons is a risk factor for domestic violence severity, especially lethality. It is not clear, however, whether access to firearms itself increases assault severity, or whether it is characteristic of a subgroup of offenders who are more likely to commit severe and repeated domestic assault. This reanalysis of 1,421 police reports of domestic violence by men found that 6% used a weapon during the assault and 8% had access to firearms. We expected that firearm use would be rare compared to other weapons and that actual weapon use rather than firearm access would increase the severity of domestic assaults. Firearm access was associated with assault severity, but this was mostly attributable to use of nonfirearm weapons. Weapon use was associated with older age, lower education, and relationship history as well as to assault severity. Victims were most concerned about future assaults following threats and actual injuries. Although firearm access and weapon use were related to actuarial risk of domestic violence recidivism, neither predicted the occurrence or severity of recidivism. We conclude that, consistent with previous research in the United States and Canada, firearm use in domestic violence is uncommon even among offenders with known firearm access. Weapon use is characteristic of a subgroup of offenders who commit more severe domestic violence, and seizure of weapons may be an effective intervention.

  13. Neutron sources and applications

    Energy Technology Data Exchange (ETDEWEB)

    Price, D.L. [ed.] [Argonne National Lab., IL (United States); Rush, J.J. [ed.] [National Inst. of Standards and Technology, Gaithersburg, MD (United States)

    1994-01-01

    Review of Neutron Sources and Applications was held at Oak Brook, Illinois, during September 8--10, 1992. This review involved some 70 national and international experts in different areas of neutron research, sources, and applications. Separate working groups were asked to (1) review the current status of advanced research reactors and spallation sources; and (2) provide an update on scientific, technological, and medical applications, including neutron scattering research in a number of disciplines, isotope production, materials irradiation, and other important uses of neutron sources such as materials analysis and fundamental neutron physics. This report summarizes the findings and conclusions of the different working groups involved in the review, and contains some of the best current expertise on neutron sources and applications.

  14. Application & Research of Hypothesis Test Method in Weapon Test%假设检验方法在兵器试验中的应用研究

    Institute of Scientific and Technical Information of China (English)

    尹江丽; 郭效芝

    2013-01-01

    Based on the problems which needing the hypothesis test in weapon test, this paper proposes processing data by use of a hypothesis test. By establishing the null hypothesis and alternative hypothesis to select the appropriate statistics, the sample is measured according to the data to judge the reasonableness of the hypothesis on the basis of the test of the hypothesis. If the hypothesis is proved reasonable, it can be used as the basis for data analysis and data application to establish a corresponding hypothesis test model and apply the hypothesis test to weapon test. The application example shows that this method is reasonable and effective. It applies to standard deviation and rate, as well as quality inspection, and is an effective way to test the indexes of military products.%  针对兵器试验中需要进行假设检验的问题,提出一种利用假设检验进行数据处理的方法。通过建立原假设与备选假设,选取适当的统计量,再根据资料实测样本,对所做的假设进行检验,从而判断此假设是否合理,若假设通过检验,则可以作为数据分析和应用的依据,并建立相应的假设检验模型,将假设检验方法运用到兵器试验中。实例应用结果表明:该方法合理有效,不仅适用于质量的检验,对标准差、比率等指标均可进行检验,是兵工产品指标测定的一种有效方法。

  15. OIL AS POLITICAL WEAPON

    Directory of Open Access Journals (Sweden)

    Mariana, BUICAN

    2013-12-01

    Full Text Available Oil (called by some black gold has not always been as coveted and used, but only in the last hundred years has established itself as a highly sought after as an indispensable proper functioning of modern economic activity that an important factor in international politics. International oil regime has changed in the last decades. In 1960, oil regime was a private oligopol which had links with governments main consuming countries. By then the price of a barrel of oil was two U.S. dollars and seven major transnational oil companies decided the amount of oil that will be produced. Meanwhile the world region with the largest oil exports were more strongly expressed nationalism and decolonization. Result, it was so in the late 60s in the region occur independent states. They have created an organization aim of this resource to their advantage - OPEC (Organization of Petroleum Exporting Countries. Thus since 1973 there have been changes in the international regime governing oil field, namely producing countries were fixed production rate and price. After this time the oil weapon has become increasingly important in the management of international relations. Oil influenced the great powers to Middle East conflicts that occurred in the last century, but their attitude about the emergence of new sources of oil outside OPEC. In the late 90's, Russia has become a major supplier of oil to the West.

  16. Applied research and development of neutron activation analysis - The study on human health and environment by neutron activation analysis of biological samples

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Seung Yeon; Yoo, Jong Ik; Lee, Jae Kwang; Lee, Sung Jun; Lee, Sang Sun; Jeon, Ki Hong; Na, Kyung Won; Kang, Sang Hun [Yonsei University, Seoul (Korea)

    2000-04-01

    With the development of the precise quantitative analytical method for the analysis of trace elements in the various biological samples such as hair and food, evaluation in view of health and environment to the trace elements in various sources which can be introduced inside human body was done. The trace elemental distribution in Korean total diet and representative food stuff was identified first. With the project the elemental distributions in supplemental healthy food and Korean and Chinese origin oriental medicine were identified. The amount of trace elements ingested with the hair analysis of oriental medicine takers were also estimated. The amounts of trace elements inhaled with the analysis of foundry air, blood and hair of foundry workers were also estimated. The basic estimation method in view of health and environment with the neutron activation analysis of biological samples such as foods and hair was established with the result. Nationwide usage system of the NAA facility in Hanaro in many different and important areas of biological area can be initiated with the results. The output of the project can support public heath, environment, and medical research area. The results can be applied for the process of micronutrients enhanced health food production and for the health safety and health status enhancement with the additional necessary data expansion and the development of various evaluation technique. 19 refs., 7 figs., 23 tabs. (Author)

  17. Design of epithermal neutron beam for clinical BNCT treatment at Slovenian TRIGA research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Maucec, Marko [Jozef Stefan Institute, Reactor Physics Division, Lubljana (Slovenia). E-mail: marko.mauce@ijs.si

    1999-07-01

    The Monte Carlo feasibility study of development of epithermal neutron beam for BNCT clinical trials on Jozef Stefan Institute (JSI) TRIGA reactor is presented. The investigation of the possible use of fission converter for the purpose of enhancement of neutron beam, as well as the set-up of TRIGA reactor core is performed. The optimization of the irradiation facility components is carried out and the configuration with the most favorable cost/performance ratio is proposed. The simulation results prove that a BNCT irradiation facility with performances, comparable to existing beams throughout the world, could be installed in the thermalizing column of the TRIGA reactor, quite suitable for the clinical treatments of human patients. (author)

  18. Study of cold neutron sources: Implementation and validation of a complete computation scheme for research reactor using Monte Carlo codes TRIPOLI-4.4 and McStas

    Energy Technology Data Exchange (ETDEWEB)

    Campioni, Guillaume; Mounier, Claude [Commissariat a l' Energie Atomique, CEA, 31-33, rue de la Federation, 75752 Paris cedex (France)

    2006-07-01

    The main goal of the thesis about studies of cold neutrons sources (CNS) in research reactors was to create a complete set of tools to design efficiently CNS. The work raises the problem to run accurate simulations of experimental devices inside reactor reflector valid for parametric studies. On one hand, deterministic codes have reasonable computation times but introduce problems for geometrical description. On the other hand, Monte Carlo codes give the possibility to compute on precise geometry, but need computation times so important that parametric studies are impossible. To decrease this computation time, several developments were made in the Monte Carlo code TRIPOLI-4.4. An uncoupling technique is used to isolate a study zone in the complete reactor geometry. By recording boundary conditions (incoming flux), further simulations can be launched for parametric studies with a computation time reduced by a factor 60 (case of the cold neutron source of the Orphee reactor). The short response time allows to lead parametric studies using Monte Carlo code. Moreover, using biasing methods, the flux can be recorded on the surface of neutrons guides entries (low solid angle) with a further gain of running time. Finally, the implementation of a coupling module between TRIPOLI- 4.4 and the Monte Carlo code McStas for research in condensed matter field gives the possibility to obtain fluxes after transmission through neutrons guides, thus to have the neutron flux received by samples studied by scientists of condensed matter. This set of developments, involving TRIPOLI-4.4 and McStas, represent a complete computation scheme for research reactors: from nuclear core, where neutrons are created, to the exit of neutrons guides, on samples of matter. This complete calculation scheme is tested against ILL4 measurements of flux in cold neutron guides. (authors)

  19. Re-research on the size of proto-neutron star in core-collapse supernova

    Institute of Scientific and Technical Information of China (English)

    Luo Zhi-Quan; Liu Men-Quan

    2008-01-01

    The electron capture timeseale may be shorter than hydrodynamic timescale in inner iron core of core-collapse supernova according to a recent new idea. Based on the new idea, this paper carries out a numerical simulation on supernova explosion for the progenitor model Wsl5M⊙. The numerical result shows that the size of proto-neutron star has a significant change (decrease about 20%), which may affects the propagation of the shock wave and the final explosion energy.

  20. Neutron activation analysis in archaeological and solar energy research; Neutronenaktivierungsanalyse in Archaeometrie und Solarenergieforschung

    Energy Technology Data Exchange (ETDEWEB)

    Stieghorst, Christian

    2016-06-23

    For 80 years now, neutron activation analysis (NAA) has been providing reliable data of the elemental composition for different materials in various scientific fields. Today, there are still many applications for NAA, and new methods based on neutron activation were developed during the last couple of years. In this work the focus was on the precise elemental analysis of different materials. For the provenance studies of ancient Roman limestone objects the elemental composition of samples and quarries were compared by using geochemical indicators and multivariate statistics of the elemental composition dataset, which was previously produced by using instrumental neutron activation analysis (INAA). The samples of this work originated from different archeological sites and quarries in the French region of Lorraine as well as samples from excavations in the Belgian city of Tongeren. Various objects could successfully assign to one of the Lorraine quarries via principle component analysis (PCA) and support vector machines (SVM).The aim of the co-operation between the Fraunhofer Institute for Solar Energy Systems ISE in Freiburg, Germany, and the Institute of Nuclear Chemistry in Mainz, Germany, was to reduce the energy and cost consumption during the production process of multicrystalline solar cells at a constant efficiency level. The test ingots were produced at the ISE and measured with NAA. The colleagues' work on this topic was focused on INAA measurements of the 3d transition metals and a new developed method for phosphorus detection. In this work prompt-gamma neutron activation analysis (PGAA) was used to measure the dopand boron as well as hydrogen. The PGAA facility of the FRM II reactor close to the city of Munich was used for this purposes. For the measurement of boron amounts below the PGAA detection limit in the medium ppb{sub w}-range a new method developed at the FRM II by Lichtinger was tested. A qualitative boron detection was successful.

  1. Recent developments in neutron imaging with applications for porous media research

    Science.gov (United States)

    Kaestner, Anders P.; Trtik, Pavel; Zarebanadkouki, Mohsen; Kazantsev, Daniil; Snehota, Michal; Dobson, Katherine J.; Lehmann, Eberhard H.

    2016-09-01

    Computed tomography has become a routine method for probing processes in porous media, and the use of neutron imaging is especially suited to the study of the dynamics of hydrogenous fluids, and of fluids in a high-density matrix. In this paper we give an overview of recent developments in both instrumentation and methodology at the neutron imaging facilities NEUTRA and ICON at the Paul Scherrer Institut. Increased acquisition rates coupled to new reconstruction techniques improve the information output for fewer projection data, which leads to higher volume acquisition rates. Together, these developments yield significantly higher spatial and temporal resolutions, making it possible to capture finer details in the spatial distribution of the fluid, and to increase the acquisition rate of 3-D CT volumes. The ability to add a second imaging modality, e.g., X-ray tomography, further enhances the feature and process information that can be collected, and these features are ideal for dynamic experiments of fluid distribution in porous media. We demonstrate the performance for a selection of experiments carried out at our neutron imaging instruments.

  2. Neutron tomography

    Science.gov (United States)

    Crump, James C., III; Richards, Wade J.; Shields, Kevin C.

    1995-07-01

    The McClellan Nuclear Radiation Center's (MNRC) staff in conjunction with a Cooperative Research and Development Agreement (CRDA) with the U.C. Santa Barbara facility has developed a system that can be used for aircraft inspection of jet engine blades. The problem was to develop an inspection system that can detect very low concentrations of hydrogen (i.e., greater than 100 ppm) in metal matricies. Specifically in Titanium alloy jet engine blades. Entrapment and precipitation of hydrogen in metals is an undesirable phenomenon which occurs in many alloys of steel and titanium. In general, metals suffer a loss of mechanical properties after long exposures to hydrogen, especially at high temperatures and pressures, thereby becoming embrittled. Neutron radiography has been used as a nondestructive testing technique for many years. Neutrons, because of their unique interactions with materials, are especially useful in the detection of hydrogen. They have an extremely high interaction cross section for low atomic number nuclei (i.e., hydrogen). Thus hydrogen in a metal matrix can be visualized using neutrons. Traditional radiography is sensitive to the total attenuation integrated over the path of radiation through the material. Increased sensitivity and quantitative cross section resolution can be obtained using three-dimensional volumetric imaging techniques such as tomography. The solution used to solve the problem was to develop a neutron tomography system. The neutron source is the McClellan Nuclear Radiation Center's 1 MW TRIGA reactor. This paper describes the hardware used in the system as well as some of the preliminary results.

  3. Neutron Sources for Standard-Based Testing

    Energy Technology Data Exchange (ETDEWEB)

    Radev, Radoslav [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); McLean, Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2014-11-10

    The DHS TC Standards and the consensus ANSI Standards use 252Cf as the neutron source for performance testing because its energy spectrum is similar to the 235U and 239Pu fission sources used in nuclear weapons. An emission rate of 20,000 ± 20% neutrons per second is used for testing of the radiological requirements both in the ANSI standards and the TCS. Determination of the accurate neutron emission rate of the test source is important for maintaining consistency and agreement between testing results obtained at different testing facilities. Several characteristics in the manufacture and the decay of the source need to be understood and accounted for in order to make an accurate measurement of the performance of the neutron detection instrument. Additionally, neutron response characteristics of the particular instrument need to be known and taken into account as well as neutron scattering in the testing environment.

  4. Solid polystyrene and deuterated polystyrene light output response to fast neutrons

    Science.gov (United States)

    Simpson, R.; Danly, C.; Glebov, V. Yu.; Hurlbut, C.; Merrill, F. E.; Volegov, P. L.; Wilde, C.

    2016-04-01

    The Neutron Imaging System has proven to be an important diagnostic in studying DT implosion characteristics at the National Ignition Facility. The current system depends on a polystyrene scintillating fiber array, which detects fusion neutrons born in the DT hotspot as well as neutrons that have scattered to lower energies in the surrounding cold fuel. Increasing neutron yields at NIF, as well as a desire to resolve three-dimensional information about the fuel assembly, have provided the impetus to build and install two additional next-generation neutron imaging systems. We are currently investigating a novel neutron imaging system that will utilize a deuterated polystyrene (CD) fiber array instead of standard hydrogen-based polystyrene (CH). Studies of deuterated xylene or deuterated benzene liquid scintillator show an improvement in imaging resolution by a factor of two [L. Disdier et al., Rev. Sci. Instrum. 75, 2134 (2004)], but also a reduction in light output [V. Bildstein et al., Nucl. Instrum. Methods Phys. Res., Sect. A 729, 188 (2013); M. I. Ojaruega, Ph.D. thesis, University of Michigan, 2009; M. T. Febbraro, Ph.D. thesis, University of Michigan, 2014] as compared to standard plastic. Tests of the relative light output of deuterated polystyrene and standard polystyrene were completed using 14 MeV fusion neutrons generated through implosions of deuterium-tritium filled capsules at the OMEGA laser facility. In addition, we collected data of the relative response of these two scintillators to a wide energy range of neutrons (1-800 MeV) at the Weapons Neutrons Research Facility. Results of these measurements are presented.

  5. Research of simulation shooting trainer for a certain remote control weapon station%某遥控武器站模拟射击训练器研究

    Institute of Scientific and Technical Information of China (English)

    杨硕; 田兴科; 崔晓颖

    2014-01-01

    火控系统模拟训练器是为适应现代化信息战争而诞生的一种新型训练设备。针对某型遥控武器站火控系统提出一种模拟射击训练器的设计方案,从硬件和软件两个角度详细介绍各模块的实现方法。设计信号调理盒实现各模块间不同信号类型间的相互通讯,采用3DSMAX/Virtools实现三维虚拟战场环境和目标的制作与驱动,基于Qt设计了与实装一致的显控界面。仿真结果表明所设计的模拟射击训练器可以满足模拟训练的需求。%The simulation trainer of fire control system is a new training equipment adapted to modern information warfare. A design scheme of shooting trainer is proposed for the fire control system of a certain remote control weapon station. Proceeding from hardware and software,the implementation method of each module is introduced in detail. The signal conditioning box was designed to achieve communication among different signals from the modules. 3DSMAX and Virtools are used to realize and drive three-dimensional virtual battlefield environment and the target. The display and control interface consistent with the real equipment was designed by means of Qt. The simulation results show that the design of shooting trainer can meet the training needs.

  6. Mitigation and propagation of sound generated by heavy weapons

    NARCIS (Netherlands)

    Berg, F. van den; Eerden, F.J.M. van der

    2011-01-01

    Much environmental research is performed on predicting the noise impact of heavy weapons or explosives, as the shock waves can propagate over large distances. In the densely populated area of the Netherlands this is of particular interest for the Ministry of Defense. In one research program the miti

  7. Neutron activation analysis and Mossbauer spectroscopy research on coloring mechanism of Chinese Ru porcelain

    Institute of Scientific and Technical Information of China (English)

    2002-01-01

    The characteristic spectrum and its main wavelength of Ru porcelain glaze are measured by color difference instrument to determine the relations between glaze color and its main wavelength. The content of the 30 coloring elements in Ru porcelain is determined by neutron activation analysis (NAA), which showed that iron is the major coloring element. M?ssbauer spectroscopy analysis shows that the iron element in the glaze exists in the form of structural iron (Fe2+, Fe3+). The quantitative relationship between the main wavelength of glaze in various colors and the relative content of structural iron (Fe2+/Fe3+) is determined. Thus the coloring mechanism of Ru porcelain is investigated entirely.

  8. The Effects of Nuclear Weapons

    Energy Technology Data Exchange (ETDEWEB)

    Glasstone, Samuel

    1964-02-01

    This book is a revision of "The Effects of Nuclear Weapons" which was issued in 1957. It was prepared by the Defense Atomic Support Agency of the Department of Defense in coordination with other cognizant governmental agencies and was published by the U.S. Atomc Energy Commission. Although the complex nature of nuclear weapons effects does not always allow exact evaluation, the conclusions reached herein represent the combined judgment of a number of the most competent scientists working the problem. There is a need for widespread public understanding of the best information available on the effects of nuclear weapons. The purpose of this book is to present as accurately as possible, within the limits of national security, a comprehensive summary of this information.

  9. Environmental Detection of Clandestine Nuclear Weapon Programs

    Science.gov (United States)

    Kemp, R. Scott

    2016-06-01

    Environmental sensing of nuclear activities has the potential to detect nuclear weapon programs at early stages, deter nuclear proliferation, and help verify nuclear accords. However, no robust system of detection has been deployed to date. This can be variously attributed to high costs, technical limitations in detector technology, simple countermeasures, and uncertainty about the magnitude or behavior of potential signals. In this article, current capabilities and promising opportunities are reviewed. Systematic research in a variety of areas could improve prospects for detecting covert nuclear programs, although the potential for countermeasures suggests long-term verification of nuclear agreements will need to rely on methods other than environmental sensing.

  10. DOE battery program for weapon applications

    Science.gov (United States)

    Clark, R. P.; Baldwin, A. R.

    This report discusses the Department of Energy (DOE) Weapons Battery program which originates from Sandia National Laboratories (SNL) and involves activities ranging from research, design and development to testing, consulting, and production support. The primary customer is the DOE/Office of Defense Programs, although work is also done for various Department of Defense agencies and their contractors. The majority of the SNL activities involve thermal battery (TB) and lithium ambient temperature battery (LAMB)technologies. Smaller efforts are underway in the areas of silver oxide/zinc and nickel oxide/cadmium batteries as well as double layer capacitors.

  11. The development and application of k -standardization method of neutron activation analysis at Es-Salam research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Alghem, L. [Departement d' Analyse par Activation Neutronique, CRNB, BP 180, Ain Oussera 17200, W Djelfa (Algeria)]. E-mail: lylia_25@hotmail.com; Ramdhane, M. [Departement de physique, Universite Mentouri de Constantine (Algeria); Khaled, S. [Departement d' Analyse par Activation Neutronique, CRNB, BP 180, Ain Oussera 17200, W Djelfa (Algeria); Akhal, T. [Departement d' Analyse par Activation Neutronique, CRNB, BP 180, Ain Oussera 17200, W Djelfa (Algeria)

    2006-01-01

    In recent years the k -NAA method has been applied and developed at the 15 MW Es-Salam research reactor, which includes: (1) the detection efficiency calibration of {gamma}-spectrometer used in k -NAA (2) the determination of reactor neutron spectrum parameters such as {alpha} and f factors in the irradiation channel, and (3) the validation of the developed k -NAA procedure by analysing SRM, namely AIEA-Soil7 and CRM, namely IGGE-GSV4. The analysis results obtained by k -NAA with 27 elements of Soil-7 standard and 14 elements of GSV-4 standard were compared with certified values. The analysis results showed that the deviations between experimental and certified values were mostly less than 10%. The k -NAA procedure established at Es-Salam research reactor has been regarded as a reliable standardization method of NAA and as available for practical applications.

  12. Neutron-Induced Fission Cross Section Measurements for Full Suite of Uranium Isotopes

    Science.gov (United States)

    Laptev, Alexander; Tovesson, Fredrik; Hill, Tony

    2010-11-01

    A well established program of neutron-induced fission cross section measurement at Los Alamos Neutron Science Center (LANSCE) is supporting the Fuel Cycle Research program (FC R&D). The incident neutron energy range spans energies from sub-thermal energies up to 200 MeV by measuring both the Lujan Center and the Weapons Neutron Research center (WNR). Conventional parallel-plate fission ionization chambers with actinide deposited foils are used as a fission detector. The time-of-flight method is implemented to measure neutron energy. Counting rate ratio from investigated and standard U-235 foils is translated into fission cross section ratio. Different methods of normalization for measured ratio are employed, namely, using of actinide deposit thicknesses, normalization to evaluated data, etc. Finally, ratios are converted to cross sections based on the standard U-235 fission cross section data file. Preliminary data for newly investigated isotopes U-236 and U-234 will be reported. Those new data complete a full suite of Uranium isotopes, which were investigated with presented experimental approach. When analysis of the new measured data will is completed, data will be delivered to evaluators. Having data for full set of Uranium isotopes will increase theoretical modeling capabilities and make new data evaluations much more reliable.

  13. Design of the Next Generation Target at the Lujan Neutron Scattering Center, LANSCE

    Energy Technology Data Exchange (ETDEWEB)

    Ferres, Laurent [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); National Graduate School of Engineering and Research Center (ENSICAEN), Caen (France)

    2016-08-03

    Los Alamos National Laboratory (LANL) supports scientific research in many diverse fields such as biology, chemistry, and nuclear science. The Laboratory was established in 1943 during the Second World War to develop nuclear weapons. Today, LANL is one of the largest laboratories dedicated to nuclear defense and operates an 800 MeV proton linear accelerator for basic and applied research including: production of high- and low-energy neutrons beams, isotope production for medical applications and proton radiography. This accelerator is located at the Los Alamos Neutron Science Center (LANSCE). The work performed involved the redesign of the target for the low-energy neutron source at the Lujan Neutron Scattering Center, which is one of the facilities built around the accelerator. The redesign of the target involves modeling various arrangements of the moderator-reflector-shield for the next generation neutron production target. This is done using Monte Carlo N-Particle eXtended (MCNPX), and ROOT analysis framework, a C++ based-software, to analyze the results.

  14. Detecting buried metallic weapons in a controlled setting using a conductivity meter.

    Science.gov (United States)

    Dionne, Charles A; Schultz, John J; Murdock, Ronald A; Smith, Stephen A

    2011-05-20

    Forensic personnel may face a daunting task when searching for buried weapons at crime scenes or potential disposal sites. In particular, it is common to search for a small firearm that was discarded or buried by a perpetrator. When performing forensic searches, it is recommended to first use non-invasive methods such as geophysical instruments to minimize damage to evidence and to the crime scene. Geophysical tools are used to pinpoint small areas of interest across a scene for invasive testing, rather than digging large areas throughout the site. Prior to this project, there was no published research that tested the utility of the conductivity meter to search for metallic weapons such as firearms and blunt and sharp edged weapons. A sample comprised of 32 metallic weapons including firearms, blunt and sharp edged weapons, and scrap metals was buried in a controlled setting to test the applicability of a conductivity meter for forensic searches. Weapons were tested at multiple depths and after data collection was performed for one depth, the weapons were reburied 5 cm deeper until they were no longer detected. Variables such as weapon size, burial depth, transect interval spacing (25 and 50 cm), and metallic composition were tested. All of the controlled variables influenced maximum depth of detection. For example, size was a factor as larger weapons were detected at deeper depths compared to smaller weapons. Metal composition affected maximum depth of detection as the conductivity meter detected items comprised of ferrous metals at deeper depths than non-ferrous metals. Searches for large buried items may incorporate a transect interval spacing of 50 cm but small weapons may be undetected between transects and therefore a transect interval spacing of 25 cm is recommended. Overall, the conductivity meter is a geophysical tool to consider when searching for larger-sized metallic weapons or to use in conjunction with an all-metal detector, particularly when

  15. The Effects of Nuclear Weapons

    Energy Technology Data Exchange (ETDEWEB)

    Glasstone, Samuel

    1957-06-01

    This handbook prepared by the Armed Forces Special Weapons Project of the Department of Defense in coordination with other cognizant government agencies and published by the United States Atomic Energy Commission, is a comprehensive summary of current knowledge on the effects of nuclear weapons. The effects information contained herein is calculated for yields up to 20 megatons and the scaling laws for hypothetically extending the calculations beyond this limit are given. The figure of 20 megatons however is not be taken as an indication of capabilities or developments.

  16. Computation of Weapons Systems Effectiveness

    Science.gov (United States)

    2013-09-01

    Aircraft Dive Angle : Initial Weapon Release Velocity at x-axis VOx VOz x: x-axis z: z-axis : Initial Weapon Release Velocity at z...altitude Impact Velocity (x− axis), Vix = VOx (3.4) Impact Velocity (z− axis), Viz = VOz + (g ∗ TOF) (3.5) Impact Velocity, Vi = �Vix2 + Viz2 (3.6...compute the ballistic partials to examine the effects that varying h, VOx and VOz have on RB using the following equations: ∂RB ∂h = New RB−Old RB

  17. A new irradiation method with a neutron filter for silicon neutron transmutation doping at the Japan research reactor no. 3 (JRR-3).

    Science.gov (United States)

    Komeda, Masao; Kawasaki, Kozo; Obara, Toru

    2013-04-01

    We studied a new silicon irradiation holder with a neutron filter designed to make the vertical neutron flux profile uniform. Since an irradiation holder has to be made of a low activation material, we applied aluminum blended with B4C as the holder material. Irradiation methods to achieve uniform flux with a filter are discussed using Monte-Carlo calculation code MVP. Validation of the use of the MVP code for the holder's analyses is also discussed via characteristic experiments. Copyright © 2013 Elsevier Ltd. All rights reserved.

  18. Application of high-frame-rate neutron radiography to steam explosion research

    Science.gov (United States)

    Saito, Y.; Mishima, K.; Hibiki, T.; Yamamoto, A.; Sugimoto, J.; Moriyama, K.

    1999-11-01

    To understand the behavior of dispersed molten metal particles dropped into water during the premixing process of steam explosion, experiments were performed by using heated stainless-steel particles simulating dispersed molten metal particles. High-frame-rate neutron radiography was successfully employed for visualization and void fraction measurement. Visualization was conducted by dropping heated stainless-steel particle into heavy water filled in a rectangular tank with the particle diameter (6, 9, and 12 mm) and temperature (600°C, 700°C, 800°C, and 1000°C) as parameters. Steam generation due to direct contact of heated particle and heavy water was successfully visualized by the high-frame-rate neutron radiography at the recording speed of 500 frames/s. From void fraction measurement it was revealed that the amount of generated steam was in proportion to the particle size and temperature. It is suggested that the ambient liquid might be superheated by the particle-liquid contact.

  19. Neutrons and photons in materials research for thin film solar cells

    Energy Technology Data Exchange (ETDEWEB)

    Schorr, Susan [Institute of Geological Sciences, Freie Universitaet Berlin (Germany); Stephan, Christiane; Mainz, Roland; Rodriguez-Alvarez, Humberto; Tovar, Michael [Helmholtz-Zentrum Berlin fuer Materialien und Energie (Germany)

    2011-08-15

    The understanding of the interplay between structural and electronic properties of photovoltaic materials as well as a deeper insight into growth pathways and phase formation kinetics of the absorber layer in a thin film solar cell give a crucial contribution to the continuous improvement of the solar cell efficiency. Among the various experimental methods used for the investigation of the structure and microstructure of photovoltaic materials, neutron, and X-ray (photon) scattering are key techniques of choice. Both techniques are complementary, which is demonstrated in the present paper. Neutron powder diffraction is used to detect different kinds of intrinsic point defects in chalcopyrite type and kesterite type semiconductors. The calculated defect concentrations may lead to the expectation of a clustering of anti-site defects and vacancy to the electrical inactive defect pairs (2V{sub Cu}+In{sub Cu}) and (In{sub Cu}+Cu{sub In}). By the means of energy dispersive X-ray diffraction (EDXRD) phase formations and grain growth in thin films are studied in real time. The potential of EDXRD for in situ studies of reactions during the formation of chalcopyrite thin films is demonstrated. (Copyright copyright 2011 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

  20. Fundamental interactions involving neutrons and neutrinos: reactor-based studies led by Petersburg Nuclear Physics Institute (National Research Centre 'Kurchatov Institute') [PNPI (NRC KI)

    Science.gov (United States)

    Serebrov, A. P.

    2015-11-01

    Neutrons of very low energy ( ˜ 10-7 eV), commonly known as ultracold, are unique in that they can be stored in material and magnetic traps, thus enhancing methodical opportunities to conduct precision experiments and to probe the fundamentals of physics. One of the central problems of physics, of direct relevance to the formation of the Universe, is the violation of time invariance. Experiments searching for the nonzero neutron electric dipole moment serve as a time invariance test, and the use of ultracold neutrons provides very high measurement precision. Precision neutron lifetime measurements using ultracold neutrons are extremely important for checking ideas on the early formation of the Universe. This paper discusses problems that arise in studies using ultracold neutrons. Also discussed are the currently highly topical problem of sterile neutrinos and the search for reactor antineutrino oscillations at distances of 6-12 meters from the reactor core. The field reviewed is being investigated at multiple facilities globally. The present paper mainly concentrates on the results of PNPI-led studies at WWR-M PNPI (Gatchina), ILL (Grenoble), and SM-3 (Dimitrovgrad) reactors, and also covers the results obtained during preparation for research at the PIK reactor which is under construction.

  1. Verification and Validation of Neutronic/Thermalhydraulic 3D-Time Dependent Model for Treatment of Super-critical States of Light water Research Reactors Accidents

    Energy Technology Data Exchange (ETDEWEB)

    Khaled, S.M. [Department of Basic Studies and Sciences, Community College, University of Tabuk, Tabuk (Saudi Arabia); Department of Mathematics, Faculty of Sciences, Helwan University, Cairo (Egypt)

    2015-07-01

    This work presents the Verification and testing both the neutronic and thermal-hydraulics response of the positive reactivity-initiated power excursion accidents in small light water research reactors. Some research reactors have to build its own severe accidents code system. In this sense, a 3D space-time-dependent neutron diffusion models with thermal hydraulic feedback have been introduced, compared and tested both experimentally at criticality 14-cent and theoretically up to 1.5 $ with a number of similar codes. The results shows that no expected core failure or moderator boiling. (author)

  2. Reactor in search for money. Cooled neutrons for unique research; Reactor zoekt geld. Gekoelde neutronen maken onderzoek mogelijk

    Energy Technology Data Exchange (ETDEWEB)

    Verdult, E.

    2010-12-17

    The modernization of radiation research at the Delft University of Technology depends on subsidies for new instruments. OYSTER (Optimised Yield for Science, Technology and Education of Radiation) is the plan of the Reactor Institute Delft (RID) to realize such a modernization. The article comprises detailed drawings of the inside of the reactor and illustrates the CNIF (Cold Neutron Irradiation Facility) to fight cancer and POSH-PALS (Positron Annihilation Lifetime Spectrometry) to visualize the atomic structure of materials. [Dutch] De modernisering van het stralingsonderzoek aan de Technische Universiteit Delft staat of valt met subsidie voor een nieuwe opzet van het instrumentarium. OYSTER (Optimised Yield for Science, Technology and Education of Radiation) is het plan van het Reactor Instituut Delft (RID) om de installatie te moderniseren. Het artikel bevat gedetailleerde tekeningen van de binnenkant van de reactor en illustreert de CNIF (Cold Neutron Irradiation Facility) voor de bestrijding van kanker en POSH-PALS (Positron Annihilation Lifetime Spectrometry) waarmee de structuur van materialen op atoomniveau inzichtelijk kan worden gemaakt.

  3. Preliminary study of degradation from neutron effects of core-structural materials of Thai Research Reactor TRR-1/M1

    Science.gov (United States)

    Ampornrat, P.; Boonsuwan, P.; Sangkaew, S.; Angwongtrakool, T.

    2017-06-01

    Thai research reactor went first critical in 1962. The reactor was converted in 1977 from an MTR-type with high-enriched uranium fuel to a TRIGA-MARK III type using low-enriched uranium fuel, called TRR-1/M1. Since the TRR-1/M1 has been operated for almost 40 years, degradation of reactor structural materials is expected. In this preliminary study, the potential degradation from neutron effects of core-structural materials, e.g., fuel clad (SS304) and core components (Al6061) were studied. Assessment included calculation of neutron energy, flux and fluence in the reactor core to evaluate displacement rate (dpa) and irradiation effects on the material properties. Results showed maximum displacement rates on SS304 was 5.24×10-8 per cm3·sec and on Al6061 was 1.14×10-8 per cm3·sec. The corresponding maximum displacement levels were ∼17 dpa for SS304, and ∼4 dpa for Al6061. At these levels of displacement, it is possible for the materials to result in tensile strength increasing and ductility reduction. Further inspection on the core-structural materials needs to be conducted to validate the assessment results from this study.

  4. PROFESSOR ZDZISŁAW ŻYGULSKI JR.: AN OUTSTANDING PERSON, A GREAT PERSONALITY, A MUSEUM PROFESSIONAL, A RESEARCHER ON ANTIQUE WEAPONS, ORIENTAL ART AND EUROPEAN PAINTING (1921–2015

    Directory of Open Access Journals (Sweden)

    Teresa Grzybkowska

    2017-02-01

    Full Text Available Professor Zdzisław Żygulski Jr. (1921–2015 was one of the most prominent Polish art historians of the second half of the 20th century. He treated the history of art as a broadly understood science of mankind and his artistic achievements. His name was recognised in global research on antique weapons, and among experts on Rembrandt and Leonardo da Vinci. He studied museums and Oriental art. He wrote 35 books, about 200 articles, and numerous essays on art; he wrote for the daily press about his artistic journeys through Europe, Japan and the United States. He illustrated his publications with his own photographs, and had a large set of slides. Żygulski created many exhibitions both at home and abroad presenting Polish art in which armour and oriental elements played an important role. He spent his youth in Lvov, and was expatriated to Cracow in 1945 together with his wife, the pottery artist and painter Eva Voelpel. He studied English philology and history of art at the Jagiellonian University (UJ, and was a student under Adam Bochnak and Vojeslav Molè. He was linked to the Czartoryski Museum in Cracow for his whole life; he worked there from 1949 until 2010, for the great majority of time as curator of the Arms and Armour Section. He devoted his whole life to the world of this museum, and wrote about its history and collections. Together with Prof. Zbigniew Bocheński, he set up the Association of Lovers of Old Armour and Flags, over which he presided from 1972 to 1998. He set up the Polish school of the study of militaria. He was a renowned and charismatic member of the circle of international researchers and lovers of militaria. He wrote the key texts in this field: Broń w dawnej Polsce na tle uzbrojenia Europy i Bliskiego Wschodu [Weapons in old Poland compared to armaments in Europe and the Near East], Stara broń w polskich zbiorach [Old weapons in Polish armouries], Polski mundur wojskowy [Polish military uniforms] (together with H

  5. 32 CFR 1903.10 - Weapons.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 6 2010-07-01 2010-07-01 false Weapons. 1903.10 Section 1903.10 National... INSTALLATIONS § 1903.10 Weapons. (a) Except as provided in paragraph (c) of this section, knowingly possessing or causing to be present a weapon on an Agency installation, or attempting to do so is prohibited. (b...

  6. 48 CFR 25.301-3 - Weapons.

    Science.gov (United States)

    2010-10-01

    ... 48 Federal Acquisition Regulations System 1 2010-10-01 2010-10-01 false Weapons. 25.301-3 Section... FOREIGN ACQUISITION Contracts Performed Outside the United States 25.301-3 Weapons. The contracting officer shall follow agency procedures and the weapons policy established by the combatant commander or...

  7. Basic research of boron neutron-capture therapy for treatment of pancreatic cancer. Application of neutron radiography for visualization of boron compound on BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Yanagie, Hironobu [Tokyo Univ. (Japan). Inst. of Medical Science

    1997-02-01

    The cytotoxic effects of locally injected {sup 10}B-immunoliposomes (anti-CEA) on human pancreatic carcinoma xenografts in nude mice were evaluated with thermal neutron irradiation. After thermal neutron irradiation of mice injected with {sup 10}B-immunoliposomes, AsPC-1 tumour growth was suppressed relative to controls. Histopathologically, hyalinization and necrosis were found in {sup 10}B-treated tumours, while tumour tissue injected with saline or saline-containing immunoliposomes showed neither destruction nor necrosis. These results suggest that intratumoral injection of boronated immunoliposomes can increase the retention of {sup 10}B atoms by tumour cells, causing tumour growth suppression in vivo upon thermal neutron irradiation. We prepared boronated PEG-binding bovine serum albumin ({sup 10}B-PEG-BSA). {sup 10}B concentrations in AsPC-1, human pancreatic cancer cells (2 x 10{sup 5} /well) obtained 24 hrs after incubation with {sup 10}B-PEG-BSA was 13.01 {+-} 1.74 ppm. The number of {sup 10}B atoms delivered to the tumor cells was calculated to be 7.83 x 10{sup 11} at 24 hrs after incubation with {sup 10}B-PEG-BSA. These data indicated that the {sup 10}B-PEG-BSA could deliver a sufficient amount of {sup 10}B atoms (more than 10{sup 9} atoms/cell) to the tumor cells to induce cytotoxic effects after incubation upon thermal neutron irradiation. Neutron capture autoradiography by using an Imaging Plate (IP-NCR) was performed on AsPC-1 tumor-bearing mouse that had been given an intratumoral injection of {sup 10}B-PEG BSA or {sup 10}B-cationic liposome. We had demonstrated the {sup 10}B-PEG BSA or {sup 10}B-cationic liposome is taken up by AsPC-1 tumor tissue to a much greater extent than by normal tissues. (J.P.N.)

  8. Basic research of boron neutron-capture therapy for treatment of pancreatic cancer. Application of neutron radiography for visualization of boron compound on BNCT

    Energy Technology Data Exchange (ETDEWEB)

    Yanagie, Hironobu [Tokyo Univ. (Japan). Inst. of Medical Science

    1997-02-01

    The cytotoxic effects of locally injected {sup 10}B-immunoliposomes (anti-CEA) on human pancreatic carcinoma xenografts in nude mice were evaluated with thermal neutron irradiation. After thermal neutron irradiation of mice injected with {sup 10}B-immunoliposomes, AsPC-1 tumour growth was suppressed relative to controls. Histopathologically, hyalinization and necrosis were found in {sup 10}B-treated tumours, while tumour tissue injected with saline or saline-containing immunoliposomes showed neither destruction nor necrosis. These results suggest that intratumoral injection of boronated immunoliposomes can increase the retention of {sup 10}B atoms by tumour cells, causing tumour growth suppression in vivo upon thermal neutron irradiation. We prepared boronated PEG-binding bovine serum albumin ({sup 10}B-PEG-BSA). {sup 10}B concentrations in AsPC-1, human pancreatic cancer cells (2 x 10{sup 5} /well) obtained 24 hrs after incubation with {sup 10}B-PEG-BSA was 13.01 {+-} 1.74 ppm. The number of {sup 10}B atoms delivered to the tumor cells was calculated to be 7.83 x 10{sup 11} at 24 hrs after incubation with {sup 10}B-PEG-BSA. These data indicated that the {sup 10}B-PEG-BSA could deliver a sufficient amount of {sup 10}B atoms (more than 10{sup 9} atoms/cell) to the tumor cells to induce cytotoxic effects after incubation upon thermal neutron irradiation. Neutron capture autoradiography by using an Imaging Plate (IP-NCR) was performed on AsPC-1 tumor-bearing mouse that had been given an intratumoral injection of {sup 10}B-PEG BSA or {sup 10}B-cationic liposome. We had demonstrated the {sup 10}B-PEG BSA or {sup 10}B-cationic liposome is taken up by AsPC-1 tumor tissue to a much greater extent than by normal tissues. (J.P.N.)

  9. Handheld Concealed Weapons Detector Development

    Science.gov (United States)

    2003-03-01

    Enforcement, Edward M. Carapezza, Donald Spector, Eds., Proc. SPIE 2938, 110 - 119 (1997). 3. Franklin Felber, Norbert Wild, Scott Nunan , Dennis Breuner... Nunan , D. Breuner, and F. Doft, "Handheld Ultrasound Concealed-Weapons Detector," in Enforcement and Security Technologies, A. Trent DePersia, J. J

  10. Neutron transport-burnup code MCORGS and its application in fusion fission hybrid blanket conceptual research

    Science.gov (United States)

    Shi, Xue-Ming; Peng, Xian-Jue

    2016-09-01

    Fusion science and technology has made progress in the last decades. However, commercialization of fusion reactors still faces challenges relating to higher fusion energy gain, irradiation-resistant material, and tritium self-sufficiency. Fusion Fission Hybrid Reactors (FFHR) can be introduced to accelerate the early application of fusion energy. Traditionally, FFHRs have been classified as either breeders or transmuters. Both need partition of plutonium from spent fuel, which will pose nuclear proliferation risks. A conceptual design of a Fusion Fission Hybrid Reactor for Energy (FFHR-E), which can make full use of natural uranium with lower nuclear proliferation risk, is presented. The fusion core parameters are similar to those of the International Thermonuclear Experimental Reactor. An alloy of natural uranium and zirconium is adopted in the fission blanket, which is cooled by light water. In order to model blanket burnup problems, a linkage code MCORGS, which couples MCNP4B and ORIGEN-S, is developed and validated through several typical benchmarks. The average blanket energy Multiplication and Tritium Breeding Ratio can be maintained at 10 and 1.15 respectively over tens of years of continuous irradiation. If simple reprocessing without separation of plutonium from uranium is adopted every few years, FFHR-E can achieve better neutronic performance. MCORGS has also been used to analyze the ultra-deep burnup model of Laser Inertial Confinement Fusion Fission Energy (LIFE) from LLNL, and a new blanket design that uses Pb instead of Be as the neutron multiplier is proposed. In addition, MCORGS has been used to simulate the fluid transmuter model of the In-Zinerater from Sandia. A brief comparison of LIFE, In-Zinerater, and FFHR-E will be given.

  11. Neutron-gamma discrimination in elpasolite scintillator detector

    Science.gov (United States)

    Morgan, Brittany

    Existing nuclear stockpiles and weapons-making capabilities imperil the global community. Current nonproliferation efforts involve the research and development of newer, more efficient detection systems that can be deployed for the interdiction and monitoring of special nuclear materials (SNM). Spontaneous and induced fission events in SNM produce neutrons and gamma rays, which can be detected and analyzed, in particular, using scintillator detectors. Various electronic data acquisition systems and data analysis methods have been employed to record and characterize neutron and photon signatures. The goal of this thesis is to develop a new method of discrimination between neutrons and photons in the CLYC elpasolite scintillator detector. Because neutrons and photons interact uniquely with scintillator materials, they generate scintillation light decay signals of different time profiles. Several conventional and digital pulse shape discrimination (PSD) methods exist to exploit the different features of detector signal waveforms caused by the different time profiles of the scintillation decay. They can be categorized on the basis of their implementation: time domain only or time and frequency domain. In this study, wavelet analysis is implemented in the time domain. When the discrete wavelet transform is applied to each pulse, the Haar wavelet is sampled over the signal to generate a set of coefficients, which are then further analyzed using numerical integration. The wavelet-based signal analysis code was written in Matlab. The code processes a single detector waveform at a time. It first applies the discrete wavelet transform to smooth the waveform, and then calculates the power of this signal. After performing partial integrations on different parts of the coefficients' curve, it calculates the radiation identification (RID) value that serves as a threshold for neutron-gamma discrimination. Beyond the identifying threshold, the signal is categorized as a neutron

  12. [Modern pneumatic weapons and injuries they cause].

    Science.gov (United States)

    Kozachenko, I N

    2013-01-01

    The data on the history of development and further improvement of pneumatic weapons are presented with special reference to specific features of different types and varieties of these weapons, cartridges for them, and the sphere of their application. Investigations into peculiarities of damages caused by high-capacity pneumatic weapons to the objects of forensic medical expertise affected from different distances are reviewed. Results of forensic medical expertise and clinical studies on the structure of body injuries inflicted by gunshots from pneumatic weapons to the human body are discussed. The author emphasizes the necessity of developing up-to-date terminology and classification of gunshot injuries caused by shooting from pneumatic weapons.

  13. A review on neutron reflectometry

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Jeong Soo; Lee, Chang Hee; Shim, Hae Seop; Seong, Baek Seok

    1999-03-01

    This report contains principle and characteristic of neutron reflectometry. Therefore, in case of operating neutron reflectometer at HANARO in future, it will be a reference to the user who wishes to use the instrument effectively. Also, the current situation of neutron reflectometer operating in the world was examined. The detail of neutron reflectometer such as GANS(MURR), ADAM(ILL), POSY II(ANL), ROG(IRI) was described. The recent research situation on neutron reflectometry was also examined and it helps us to determine research field. (author)

  14. Counter Weapon Control

    Science.gov (United States)

    2015-03-26

    further research efforts into solving optimal control problems with differential game theory. I wish to thank Capt. Carr for his efforts and time in...maximization problem for the I-T distance, and gives validity to differential game theory as a tool that can solve one sided optimal control problems . The result...and minimization-maximization problems . 86 Future Research. Differential Game Theory can be employed to solve a diverse array of problems . The

  15. Dose-response relationship of dicentric chromosomes in human lymphocytes obtained for the fission neutron therapy facility MEDAPP at the research reactor FRM II.

    Science.gov (United States)

    Schmid, E; Wagner, F M; Romm, H; Walsh, L; Roos, H

    2009-02-01

    The biological effectiveness of neutrons from the neutron therapy facility MEDAPP (mean neutron energy 1.9 MeV) at the new research reactor FRM II at Garching, Germany, has been analyzed, at different depths in a polyethylene phantom. Whole blood samples were exposed to the MEDAPP beam in special irradiation chambers to total doses of 0.14-3.52 Gy at 2-cm depth, and 0.18-3.04 Gy at 6-cm depth of the phantom. The neutron and gamma-ray absorbed dose rates were measured to be 0.55 Gy min(-1) and 0.27 Gy min(-1) at 2-cm depth, while they were 0.28 and 0.25 Gy min(-1) at 6-cm depth. Although the irradiation conditions at the MEDAPP beam and the RENT beam of the former FRM I research reactor were not identical, neutrons from both facilities gave a similar linear-quadratic dose-response relationship for dicentric chromosomes at a depth of 2 cm. Different dose-response curves for dicentrics were obtained for the MEDAPP beam at 2 and 6 cm depth, suggesting a significantly lower biological effectiveness of the radiation with increasing depth. No obvious differences in the dose-response curves for dicentric chromosomes estimated under interactive or additive prediction between neutrons or gamma-rays and the experimentally obtained dose-response curves could be determined. Relative to (60)Co gamma-rays, the values for the relative biological effectiveness at the MEDAPP beam decrease from 5.9 at 0.14 Gy to 1.6 at 3.52 Gy at 2-cm depth, and from 4.1 at 0.18 Gy to 1.5 at 3.04 Gy at 6-cm depth. Using the best possible conditions of consistency, i.e., using blood samples from the same donor and the same measurement techniques for about two decades, avoiding the inter-individual variations in sensitivity or the differences in methodology usually associated with inter-laboratory comparisons, a linear-quadratic dose-response relationship for the mixed neutron and gamma-ray MEDAPP field as well as for its fission neutron part was obtained. Therefore, the debate on whether the fission-neutron

  16. Neutrons in soft matter

    CERN Document Server

    Imae, Toyoko; Furusaka, Michihiro; Torikai, Naoya

    2011-01-01

    Neutron and synchrotron facilities, which are beyond the scale of the laboratory, and supported on a national level in countries throughout the world.  These tools for probing micro- and nano-structure research and on fast dynamics research of atomic location in materials have been key in the development of new polymer-based materials. Different from several existing professional books on neutron science, this book focuses on theory, instrumentation, an applications. The book is divided into five parts: Part 1 describes the underlying theory of neutron scattering. Part 2 desc

  17. Aggression and attitudes to time and risk in weapon-using violent offenders.

    Science.gov (United States)

    Brennan, Iain R; Moore, Simon C; Shepherd, Jonathan P

    2010-08-15

    The use of weapons in violence increases both the severity of harm to victims and the severity of legal consequences for offenders, but little is known of the characteristics of violent offenders who choose to use weapons. Levels of anger, attitude to risk, time discounting, and antisocial history among a sample of weapon-using violent offenders (n=15) were compared to violent offenders who had not used a weapon (n=10) and nonviolent offenders (n=15). Results showed that weapon-using violent offenders displayed greater trait aggression and were more risk seeking than other offender types. In addition, weapon-using violent offenders were first convicted at an earlier age and truanted from school more frequently compared to other offender types. The results indicate that weapon users are more aggressive and more risk taking, but no more present focused than other violent and nonviolent offenders. Further research into the cognitive and social factors that influence weapon use is required if this dangerous behavior is to be reduced. Copyright (c) 2009 Elsevier Ireland Ltd. All rights reserved.

  18. Biomechanical and performance implications of weapon design: comparison of bullpup and conventional configurations.

    Science.gov (United States)

    Stone, Richard T; Moeller, Brandon F; Mayer, Robert R; Rosenquist, Bryce; Van Ryswyk, Darin; Eichorn, Drew

    2014-06-01

    Shooter accuracy and stability were monitored while firing two bullpup and two conventional configuration rifles of the same caliber in order to determine if one style of weapon results in superior performance. Considerable debate exists among police and military professionals regarding the differences between conventional configuration weapons, where the magazine and action are located ahead of the trigger, and bullpup configuration, where they are located behind the trigger (closer to the user). To date, no published research has attempted to evaluate this question from a physical ergonomics standpoint, and the knowledge that one style might improve stability or result in superior performance is of interest to countless military, law enforcement, and industry experts. A live-fire evaluation of both weapon styles was performed using a total of 48 participants. Shooting accuracy and fluctuations in biomechanical stability (center of pressure) were monitored while subjects used the weapons to perform standard drills. The bullpup weapon designs were found to provide a significant advantage in accuracy and shooter stability, while subjects showed considerable preference toward the conventional weapons. Although many mechanical and maintenance issues must be considered before committing to a bullpup or conventional weapon system, it is clear in terms of basic human stability that the bullpup is the more advantageous configuration. Results can be used by competitive shooter, military, law enforcement, and industry experts while outfitting personnel with a weapon system that leads to superior performance.

  19. Ultra-Cold Neutrons (UCN)

    Data.gov (United States)

    Federal Laboratory Consortium — Researchers working at the Los Alamos Neutron Science Center and eight other member institutions of an international collaboration are constructing the most intense...

  20. Deterrence and Cyber-Weapons

    Science.gov (United States)

    2013-03-01

    67, no. 4 (2012): 41. 4 Scott Shackelford , “Estonia Three Years Later,” Journal of Internet Law 8, no. 13 (2010): 25. 3 weapons were employed...effects of 134 Scott Shackelford , “From Nuclear War to Net War: Analogizing Cyber-Attacks in...International Law,” (unpublished paper, Stanford University), 5-6. 135 Shackelford , unpublished paper, 76. 136 Ibid., 73. 137 Mary Ellen O’Connell, “Cyber

  1. Neutron Stars and Pulsars

    CERN Document Server

    Becker, Werner

    2009-01-01

    Neutron stars are the most compact astronomical objects in the universe which are accessible by direct observation. Studying neutron stars means studying physics in regimes unattainable in any terrestrial laboratory. Understanding their observed complex phenomena requires a wide range of scientific disciplines, including the nuclear and condensed matter physics of very dense matter in neutron star interiors, plasma physics and quantum electrodynamics of magnetospheres, and the relativistic magneto-hydrodynamics of electron-positron pulsar winds interacting with some ambient medium. Not to mention the test bed neutron stars provide for general relativity theories, and their importance as potential sources of gravitational waves. It is this variety of disciplines which, among others, makes neutron star research so fascinating, not only for those who have been working in the field for many years but also for students and young scientists. The aim of this book is to serve as a reference work which not only review...

  2. Notes on the Lumped Backward Master Equation for the Neutron Extinction/Survival Probability

    Energy Technology Data Exchange (ETDEWEB)

    Prinja, Anil K [Los Alamos National Laboratory

    2012-07-02

    The expected or mean neutron number (or density) provides an adequate characterization of the neutron population and its dynamical excursions in most neutronic applications, in particular power reactors. Fluctuations in the neutron number, originating from the inherent randomness of neutron interactions and fission neutron multiplicities, are relatively small and ignorable for operational purposes, although measurements of the variance and time correlations provide valuable diagnostic information on fundamental reactor physics parameters. However, it is well known that there exist situations of great interest and importance in which a strictly deterministic description, or even one supplemented with a knowledge of low order statistical averages (variance, correlation), provides an incomplete and very unsatisfactory description of the state of the neutron population. These situations are marked by persistent large fluctuations in the neutron number where the emergence of a deterministic phase is suppressed. Such situations are strongly stochastic and therefore unpredictable (i.e., the mean is not representative of the actual population), and can arise either by design or by accident. Examples where the stochastic behavior of neutron populations must be taken into account include: nuclear weapon single-point safety assessment; criticality excursions in spent fuel storage and in the handling of fissile solutions in fuel fabrication and reprocessing; approach to critical under suboptimal reactor start-up conditions; preinitiation in fast burst research reactors; and weak nuclear signatures in the passive detection of nuclear materials. What distinguishes strongly stochastic neutronic systems from strongly deterministic systems is that, in the former, neutron multiplication occurs in the presence of weak neutron sources, such as spontaneous fission and background (cosmic) radiation. Weak sources (in a sense that can be made quite precise) lead to well separated fission

  3. Research and development program in reactor diagnostics and monitoring with neutron noise methods. Stage 7. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Pazsit, I.; Demaziere, C.; Arzhanov, V. [Chalmers Univ. of Technology, Goeteborg (Sweden). Department of Reactor Physics; Garis, N.S. [Swedish Nuclear Power Inspectorate, Stockholm (Sweden)

    2001-08-01

    This report constitutes stage 7 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. A proposal for the continuation of this program in stage 8 is also given at the end of the report. In stage 6, the basic principles of a 3-D fully coupled neutronic/thermal-hydraulic simulator in the frequency domain were presented. The neutronic model relied on the two-group diffusion approximation, whereas the thermal-hydraulic algorithms relied on the so called 'lumped' model. The key element of this simulator was that only the static data were required which could be obtained from the Studsvik Scandpower CASMO-4/TABLES-3/ SIMULATE-3 code package. The simulator was developed with this underlying idea, which means that the calculation of the static fluxes and the eigenvalue were avoided. Depending on what kind of spatial discretization scheme which is used in the noise simulator to calculate the 'leakage' noise, it is not granted that the system remains critical by using the group constants supplied by SIMULATE. Nevertheless, when the system is critical, the balance equations should be fulfilled in all nodes with respect to the discretization scheme used. In concrete terms, the calculation of the static fluxes and eigenvalue can be avoided if the system is brought back to criticality by modifying the cross-sections so that the balance equations are always fulfilled with the chosen spatial discretization scheme. This approach was used in this study with the finite difference scheme. As pointed out in stage 6, the finite difference scheme is relatively inefficient compared to finite elements or nodal methods, but on the other hand it is rather easy to implement. These two more sophisticated schemes are planned to be investigated at a later stage, but for the time being the simulator relying on the finite difference scheme was improved as much as possible so that a 2-D entirely

  4. Influence of the neutron transport tube on neutron resonance densitometry

    Directory of Open Access Journals (Sweden)

    Kitatani Fumito

    2017-01-01

    Full Text Available Neutron Resonance Densitometry (NRD is a non-destructive assay technique of nuclear materials in particle-like debris that contains various materials. An aim of NRD is to quantify nuclear materials in a melting fuel of Fukusima Daiichi plant, spent nuclear fuel and annihilation disposal fuel etc. NRD consists of two techniques of Neutron Resonance Transmission Analysis (NRTA and Neutron Resonance Capture Analysis (NRCA or Prompt Gamma-ray Analysis (PGA. A density of nuclear material isotopes is decided with NRTA. The materials absorbing a neutron in a wide energy range such as boron in a sample are identified by NRCA/PGA. The information of NRCA/PGA is used in NRTA analysis to quantify nuclear material isotopes. A neutron time of flight (TOF method is used in NRD measurements. A facility, consisting of a neutron source, a neutron flight path, and a detector is required. A short flight path and a strong neutron source are needed to downsize such a facility and put NRD into practical use. A neutron transport tube covers a flight path to prevent noises. In order to investigate the effect of neutron transport tube and pulse width of a neutron source, we carried out NRTA experiments with a 2-m short neutron transport tube constructed at Kyoto University Research Reactor Institute - Linear Accelerator (KURRI-LINAC, and impacts of shield of neutron transport tube and influence of pulse width of a neutron source were examined. A shield of the neutron transport tube reduced a background and had a good influence on the measurement. The resonance dips of 183W at 27 eV was successfully observed with a pulse width of a neutron source less than 2 μs.

  5. Development of Neutron Spectrometer

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Chang Hee; Lee, J. S.; Seong, B. S. (and others)

    2007-06-15

    Neutron spectrometers which are used in the basic researches such as physics, chemistry and materials science and applied in the industry were developed at the horizontal beam port of HANARO reactor. In addition, the development of core components for neutron scattering and the upgrade of existing facilities are also performed. The vertical neutron reflectometer was fabricated and installed at ST3 beam port. The performance test of the reflectometer was completed and the reflectometer was opened to users. The several core parts and options were added in the polarized neutron spectrometer. The horizontal neutron reflectometer from Brookhaven National Laboratory was moved to HANARO and installed, and the performance of the reflectometer was examined. The HIPD was developed and the performance test was completed. The base shielding for TAS was fabricated. The soller collimator, Cu mosaic monochromator, Si BPC monochromator and position sensitive detector were developed and applied in the neutron spectrometer as part of core component development activities. In addition, the sputtering machine for mirror device are fabricated and the neutron mirror is made using the sputtering machine. The FCD was upgraded and the performance of the FCD are improved over the factor of 10. The integration and upgrade of the neutron detection system were also performed.

  6. The intense neutron generator

    Energy Technology Data Exchange (ETDEWEB)

    Lewis, W.B

    1966-07-01

    The presentation discusses both the economic and research contexts that would be served by producing neutrons in gram quantities at high intensities by electrical means without uranium-235. The revenue from producing radioisotopes is attractive. The array of techniques introduced by the multipurpose 65 megawatt Intense Neutron Generator project includes liquid metal cooling, superconducting magnets for beam bending and focussing, super-conductors for low-loss high-power radiofrequency systems, efficient devices for producing radiofrequency power, plasma physics developments for producing and accelerating hydrogen, ions at high intensity that are still far out from established practice, a multimegawatt high voltage D.C. generating machine that could have several applications. The research fields served relate principally to materials science through neutron-phonon and other quantum interactions as well as through neutron diffraction. Nuclear physics is served through {mu}-, {pi}- and K-meson production. Isotope production enters many fields of applied research. (author)

  7. Neutronic simulation calculations to assess the proliferation resistance of nuclear technologies; Neutronenphysikalische Simulationsrechnungen zur Proliferationsresistenz nuklearer Technologien

    Energy Technology Data Exchange (ETDEWEB)

    Englert, Matthias

    2009-07-13

    This thesis investigates the proliferation resistance of nuclear technologies on the basis of three case studies. After a brief description of the concept of proliferation resistance the utilized computer codes and methods are presented. The first case study investigates the potential of monolithic fuel for the conversion of one-fuel-element high-flux research reactors from highly enriched to low enriched uranium using the example of the german research reactor FRM-II. The second case study assesses the proliferation potential of future tokamak based fusion reactors by using neutronic simulations of a possible plutonium production. The third example investigates the proliferation potential of spallation neutron sources to produce nuclear weapon relevant material and the proliferation resistance of such facilities. (orig.)

  8. Neutron Repulsion

    OpenAIRE

    Manuel, Oliver K.

    2011-01-01

    Earth is connected gravitationally, magnetically and electrically to its heat source - a neutron star that is obscured from view by waste products in the photosphere. Neutron repulsion is like the hot filament in an incandescent light bulb. Excited neutrons are emitted from the solar core and decay into hydrogen that glows in the photosphere like a frosted light bulb. Neutron repulsion was recognized in nuclear rest mass data in 2000 as the overlooked source of energy, the keystone of an arch...

  9. Combined application of imaging techniques for the characterization and authentication of ancient weapons

    Science.gov (United States)

    Salvemini, Filomena; Grazzi, Francesco; Kardjilov, Nikolay; Wieder, Frank; Manke, Ingo; Edge, David; Williams, Alan; Zoppi, Marco

    2017-05-01

    Non-invasive experimental methods play an important role in the field of cultural heritage. Benefiting from the technical progress in recent years, neutron imaging has been demonstrated to complement effectively studies based on surface analysis, allowing for a non-invasive characterization of the whole three-dimensional volume. This study focuses on a kris and a kanjar, two weapons from ancient Asia, to show the potential of the combined use of X-ray and neutron imaging techniques for the characterisation of the manufacturing methods and the authentication of objects of cultural and historical interest.

  10. Outline of spallation neutron source engineering

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Noboru [Center for Neutron Science, Tokai Research Establishment, Japan Atomic Energy Research Institute, Tokai, Ibaraki (Japan)

    2001-01-01

    Slow neutrons such as cold and thermal neutrons are unique probes which can determine structures and dynamics of condensed matter in atomic scale. The neutron scattering technique is indispensable not only for basic sciences such as condensed matter research and life science, but also for basic industrial technology in 21 century. It is believed that to survive in the science-technology competition in 21 century would be almost impossible without neutron scattering. However, the intensity of neutrons presently available is much lower than synchrotron radiation sources, etc. Thus, R and D of intense neutron sources become most important. The High-Intensity Proton Accelerator Project is now being promoted jointly by Japan Atomic Energy Research Institute and High Energy Accelerator Research Organization, but there has so far been no good text which covers all the aspects of pulsed spallation neutron sources. The present review was prepare aiming at giving a better understanding on pulsed spallation neutron sources not only to neutron source researchers but also more widely to neutron scattering researchers and accelerator scientists in this field. The contents involve, starting from what is neutron scattering and what neutrons are necessary for neutron scattering, what is the spallation reaction, how to produce neutrons required for neutron scattering more efficiently, target-moderator-reflector neutronics and its engineering, shielding, target station, material issues, etc. The author have engaged in R and D of pulsed apallation neutron sources and neutron scattering research using them over 30 years. The present review is prepared based on the author's experiences with useful information obtained through ICANS collaboration and recent data from the JSNS (Japanese Spallation Neutron Source) design team. (author)

  11. Effectiveness Testing and Evaluation of Non-Lethal Weapons for Crowd Management

    Science.gov (United States)

    2014-06-01

    Weapons”) • Participants were recruited from the general population to participate in an investigation on “ Crowd Movement ” • Fifty-two healthy men...U.S. Army Armament Research, Development, and Engineering Center EFFECTIVENESS TESTING AND EVALUATION OF NON-LETHAL WEAPONS FOR CROWD MANAGEMENT...SUBTITLE EFFECTIVENESS TESTING AND EVALUATION OF NON-LETHAL WEAPONS FOR CROWD MANAGEMENT Presented at the Virtual 82nd Military Operations Research

  12. 36 CFR 2.4 - Weapons, traps and nets.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 1 2010-07-01 2010-07-01 false Weapons, traps and nets. 2.4... PROTECTION, PUBLIC USE AND RECREATION § 2.4 Weapons, traps and nets. (a)(1) Except as otherwise provided in... prohibited: (i) Possessing a weapon, trap or net (ii) Carrying a weapon, trap or net (iii) Using a weapon...

  13. 基于直觉模糊的强声非致命武器作战效能评估研究%Research on Effectiveness Evaluation of Loud Sonic Non-Lethal Weapons

    Institute of Scientific and Technical Information of China (English)

    蒋贤沛; 郭三学; 刘小华; 朱挺

    2016-01-01

    针对强声非致命武器使用过程中非致命性不确定的问题,介绍了强声非致命武器的作用机理,分析影响强声非致命武器作战效能的关键因素,建立以非致命性为核心的效能评估指标体系,通过直觉模糊综合评判改进传统模糊评判,对强声非致命武器进行作战效能评估.评价理论对非致命武器效能的评估具有可行性,可为其他非致命武器效能评估提供借鉴.%Concerning the uncertainty of non-lethal efficiency in using loud sonic non-lethal weapons,this paper introduces the working mechanisms of loud sonic non-lethal weapons.The key factors influencing comprehensive performance of loud sonic non-lethal weapons are analyzed. The non-lethal effectiveness evaluation is established as the core of the index system.The intuitionistic fuzzy comprehensive evaluation is used to improve traditional fuzzy comprehensive evaluation and is used for the comprehensive effectiveness evaluation of loud sonic non-lethal weapons.The evaluation theory on non-lethal weapons is feasible and the evaluation of the other non-lethal weapons can use it for reference.

  14. Basic Research on Remote Sensing of Fissile Materials utilizing Gamma rays and Neutrons

    Science.gov (United States)

    2017-02-01

    6201 Fort Belvoir, VA 22060-6201 T E C H N IC A L R E P O R T DTRA-TR-15-56 Basic Research on Remote Sensing of Fissile Materials...2017 HDTRA1-09-1-0059 David C. Ingram Prepared by: Ohio University 105 Research and Technology Center Athens, OH...AVAILABILITY STATEMENT 13. SUPPLEMENTARY NOTES 14. ABSTRACT 15. SUBJECT TERMS 16. SECURITY CLASSIFICATION OF: 17. LIMITATION

  15. Optimization of the Army’s Fast Neutron Moderator for Radiography

    Science.gov (United States)

    2013-02-26

    TECHNOLOGY DEVELOPMENTS 13 PNL Generator / Moderator Design 13 CONCLUSIONS 15 REFERENCES 16 LIST OF SYMBOLS, ABBREVIATIONS...and x-ray image 12 Figure 6: Second half comparison of neutron, processed, and x-ray image 13 Figure 7: The initial setup of the PNL neutron...reactor facility; for example, muntions and weapon systems that contain energetic materials. TECHNOLOGY DEVELOPMENTS: PNL Generator / Moderator

  16. Optimization of Aimpoints for Coordinate Seeking Weapons

    Science.gov (United States)

    2015-09-01

    process. The program works by first taking in the number of weapons used and arranging them in a fixed uniform spacing on a circle centered on the...MATLAB program is used as the coding tool for the development of this algorithm and the optimization process. The program works by first taking in the...number of weapons used and arranging them in a fixed uniform spacing on a circle centered on the assumed target location. Then, the weapon

  17. New weapons and the arms race

    Energy Technology Data Exchange (ETDEWEB)

    Tsipis, K.

    1983-01-01

    In speaking about technologies that could further animate the weapons competition between the US and the USSR, it is useful to distinguish between technologies that have already been incorporated into specific weapons systems, and new technologies that are of a generic nature, can be used in a variety of applications, and can best be described by the tasks that they can perform rather than any specific weapons' application. The author discusses these in reverse order.

  18. INFLUENCE OF SCATTERED NEUTRON RADIATION ON METROLOGICAL CHARACTERISTICS OF АТ140 NEUTRON CALIBRATION FACILITY

    Directory of Open Access Journals (Sweden)

    D. I. Komar

    2017-01-01

    Full Text Available Today facilities with collimated radiation field are widely used as reference in metrological support of devices for neutron radiation measurement. Neutron fields formed by radionuclide neutron sources. The aim of this research was to study characteristics of experimentally realized neutron fields geometries on АТ140 Neutron Calibration Facility using Monte Carlo method.For calibration, we put a device into neutron field with known flux density or ambient equivalent dose rate. We can form neutron beam from radionuclide fast-neutron source in different geometries. In containercollimator of АТ140 Neutron Calibration Facility we can install special inserts to gather fast-neutron geometry or thermal-neutron geometry. We need to consider neutron scattering from air and room’s walls. We can conduct measurements of neutron field characteristics in several points and get the other using Monte Carlo method.Thermal neutron collimator forms a beam from radionuclide source with a significant amount of neutrons with thermal energies. From found relationship between full neutron flux and distance to neutron source we see that inverse square law is violated. Scattered radiation contribution into total flux increases when we are moving away from neutron source and significantly influences neutron fields characteristics. While source is exposed in shadow-cone geometry neutron specter has pronounced thermal component from wall scattering.In this work, we examined main geometry types used to acquire reference neutron radiation using radionuclide sources. We developed Monte Carlo model for 238Pu-Be neutron source and АТ140 Neutron Calibration Facility’s container-collimator. We have shown the most significant neutron energy distribution factor to be scattered radiation from room’s walls. It leads to significant changes of neutron radiation specter at a distance from the source. When planning location, and installing the facility we should consider

  19. A different kind of weapon focus: simulated training with ballistic weapons reduces change blindness

    OpenAIRE

    Taylor, J. Eric T.; Witt, Jessica K.; Pratt, Jay

    2017-01-01

    Attentional allocation is flexibly altered by action-related priorities. Given that tools – and specifically weapons – can affect attentional allocation, we asked whether training with a weapon or holding a weapon during search would affect change detection. In three experiments, participants searched for changes to agents, shootable objects, or environments in the popular flicker paradigm. Participants trained with a simulated weapon or watched a video from the same training perspective and ...

  20. 5单元中子散射相机仿真研究%Simulation research of neutron scatter camera with five units

    Institute of Scientific and Technical Information of China (English)

    张显鹏; 张美; 盛亮; 欧阳晓平

    2012-01-01

    采用粒子输运程序MCNP与FORTRAN,MATLAB程序相结合,对一种5单元结构的中子散射相机原型进行了蒙特卡罗模拟,对252Cf裂变中子源进行了图像、能量的重建.结果表明:该相机的能量分辨力为9%左右,角分辨与闪烁体的体积有关;中子能量为2 MeV左右时,散射相机的探测效率达到最大值;源的距离、闪烁体尺寸、前后面板距离、事件数等对重建图像的分辨力都有不同程度的影响;散射相机可以获得裂变中子源的能谱形状,但系统的结构、探测阈值等会使能谱测量造成一定的偏差.该理论工作的结论可推广到由更多单元组成的散射相机中使用.%As a neutron detecting and imaging device used for detection of special nuclear material (SNM) , the newly reported neutron scatter camera can acquire the neutron position and energy information simultaneously. Zn this paper, the particle transport code MCNP was used together with the program MATLAB and Fortran to simulate a five-units prototype of a neutron scatter camera, and to reconstruct the image and energy of a 252Cf neutron source. The calculation results show that the camera' s energy resolution is about 9% sad its angular resolution is related to the si2e of the scintiHators; when the neutron energy equals 2 MeV, the detection efficiency reaches a maximum; the distance of the source, the size of the scintiHators, the distance between the front and rear surfaces of the detectors, and the number of the events have influence on the resolution of the image to a certain extent; the scatter camera can measure the fission neutron energy spectrum, but the factors such as the camera's structure and detection threshold could result in some inaccuracy of the measurement. This simulation work lays a foundation for further experimental research, and its conclusion can be generalized to the neutron scatter camera with much units.

  1. 论民企参军的认识定位%Discussion on Participation of Private Enterprises in Scientific Research and Production of Weapons and Equipments

    Institute of Scientific and Technical Information of China (English)

    舒本耀; 吕继超; 吴亚菲

    2015-01-01

    针对新形势下民企参军理论认识比较混乱的问题,界定了民企参军的科学内涵,分析了优势民企应具备的技术优势、规模优势和比较优势等,阐述了优势民企作为技术创新重要引擎、军品市场平等主体、装备采购合作伙伴的新认识。%Aiming at the confusion on the participation of private enterprise in scientific research and production of w eapons and equipments ,the paper defines the scientific meaning of the participa‐tion ,analyzes the characteristics like technical advantage ,scale advantage and comparative advantage , then the paper illustrates the new understanding that private enterprises with advantages may be the important engines of technical innovation ,the equal subjects of military product market and partner of equipment procurement .

  2. Neutron Time of Flight Spectrometer for Velocity Selector Calibration

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Small angle neutron spectrometer on China Advanced Research Reactor (CARR) is located at neutron guide hall and is installed on the end of cold neutron guide. Velocity selector which can purify white light neutron beam into monochromatic neutron beam with wavelength

  3. 76 FR 6087 - Draft Weapons Safety Assessment on the Use of Enhanced Weapons; Notice of Availability and...

    Science.gov (United States)

    2011-02-03

    ... Draft Weapons Safety Assessment on the Use of Enhanced Weapons; Notice of Availability and Request for... ``Weapons Safety Assessment'' (WSA). This guidance would be used by licensees and certificate holders applying to the NRC to obtain enhanced weapons under the NRC's proposed rule titled ``Enhanced Weapons...

  4. Proceedings of the Tungsten Workshop for Hard Target Weapons Program

    Energy Technology Data Exchange (ETDEWEB)

    Mackiewicz-Ludtka, G.; Hayden, H.W.; Davis, R.M.

    1995-06-01

    The purpose of this meeting was to review and exchange information and provide technical input for improving technologies relevant to the Hard Target Weapons Program. This workshop was attended by representatives from 17 organizations, including 4 Department of Defense (DoD) agencies, 8 industrial companies, and 5 laboratories within DOE. Hard targets are defined as reinforced underground structures that house enemy forces, weapon systems, and support equipment. DOE-ORO and Martin Marietta Energy Systems, Inc. (Energy Systems) have been involved in advanced materials research and development (R&D) for several DOE and DoD programs. These programs are conducted in close collaboration with Eglin AFB, Department of the Army`s Picatinny Arsenal, and other DoD agencies. As part of this ongoing collaboration, Eglin AFB and Oak Ridge National Laboratory planned and conducted this workshop to support the Hard Target Weapons Program. The objectives of this workshop were to (1) review and identify the technology base that exists (primarily due to anti-armor applications) and assess the applicability of this technology to the Hard Target Weapons Program requirements; (2) determine future directions to establish the W materials, processing, and manufacturing technologies suitable for use in fixed, hard target penetrators; and (3) identify and prioritize the potential areas for technical collaboration among the participants.

  5. Study on void fraction distribution in the moderator cell of Cold Neutron Source systems in China Advanced Research Reactor

    Science.gov (United States)

    Li, Liangxing; Li, Huixiong; Hu, Jinfeng; Bi, Qincheng; Chen, Tingkuan

    2007-04-01

    A physical model is developed for analyzing and evaluating the void fraction profiles in the moderator cell of the Cold Neutron Source (CNS) of the China Advanced Research Reactor (CARR), which is now constructing in the China Institute of Atomic Energy (CIAE). The results derived from the model are compared with the related experimental data and its propriety is verified. The model is then used to explore the influence of various factors, including the diameter of boiling vapor bubbles, liquid density, liquid viscosity and the total heating power acted on the moderator cell, on the void fraction profiles in the cell. The results calculated with the present model indicate that the void fraction in the moderator cell increases linearly with heating power, and increases with the liquid viscosity, but decreases as the size of bubbles increases, and increases linearly with heating power. For the case where hydrogen is being used as a moderator, calculation results show that the void fraction in the moderator cell may be less than 30%, which is the maximum void fraction permitted from the nuclear physics point of view. The model and the calculation results will help to obtain insight of the mechanism that controls the void fraction distribution in the moderator cell, and provide theoretical supports for the moderator cell design.

  6. Research on pinches driven by SPPED 2 generator hard X-ray and neutron emission in plasma focus configuration

    CERN Document Server

    Sánchez-Soto, L L; Silva, P; Sylvester, G S; Zambra, M; Pavez, C; Raspa, V; Castillo, F; Kies, W; Soto, Leopoldo; Moreno, Jose; Silva, Patricio; Sylvester, Gustavo; Zambra, Marcelo; Pavez, Cristian; Raspa, Veronica; Castillo, Fermin; Kies, Walter

    2004-01-01

    SPEED2 is a generator based on Marx technology and was designed in the University of Dusseldorf. SPEED2 consists on 40 +/- Marx modules connected in parallel (4.1 mF equivalent Marx generator capacity, 300 kV, 4 MA in short circuit, 187 kJ, 400 ns rise time, dI/dt~1013 A/s). Currently the SPEED2 is operating at the Comision Chilena de Energia Nuclear, CCHEN, Chile, being the most powerful and energetic device for dense transient plasma in the Southern Hemisphere. Most of the previous works developed in SPEED2 at Dusseldorf were done in a plasma focus configuration for soft X-ray emission and the neutron emission from SPEED2 was not completely studied. The research program at CCHEN considers experiments in different pinch configurations (plasma focus, gas puffed plasma focus, gas embedded Z-pinch, wire arrays) at current of hundred of kiloamperes to mega-amperes, using the SPEED2 generator. The Chilean operation has begun implementing and developing diagnostics in a conventional plasma focus configuration oper...

  7. Effect of the New WIMSD Libraries on the Neutronic Parameters of the First and Equilibrium Cores of the Indonesian Multipurpose Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Sembiring, T.M.; Suparlina, L. [Center for Reactor Technology and Nuclear Safety, National Nuclear Energy Agency (BATAN), Kawasan PUSPIPTEK Gd. No. 80, Serpong, Tangerang Selatan 15310 (Indonesia); Hong, Liem Peng [Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology O-okayama, Meguro, Tokyo 152-8550 (Japan)

    2011-07-01

    Accurate neutronic parameters are very important in the design and safety analysis of a research reactor. The calculation method and neutron cross-section data play an important role to obtain those neutronic parameters. In this work, we reported our new results on the effects of the recent neutron cross-section data of the WIMSD libraries, JEFF-3.1 and ENDF/B-VII.0, on the criticality parameters of the first and equilibrium cores of the Indonesian multipurpose reactor, RSG-GAS reactor. WIMSD lattice code together with WIMSD libraries, coupled with the in- core fuel management code BATAN-FUEL, has been used routinely in the in-core management analysis since 1996. The objective of this work is to assess the accuracy of the recent WIMSD libraries before being adopted for routine in-core fuel management. As the first step, a series of core calculations were carried out for determining the effective multiplication factor, burn-up swing reactivity and Xenon equilibrium reactivity for the first and equilibrium cores. The results show that WIMSD library based on the evaluated nuclear data ENDF/B-VII.0 gives better agreement with the experimental results for criticality evaluation (underestimation of less than 0.4%). For burn-up swing evaluation, we found relatively large differences among the libraries (max. 5%). However, there is no significant difference among three WIMSD libraries in determining the Xenon equilibrium reactivity. (author)

  8. 虚拟现实技术在武器对抗仿真中的应用研究%The Research of Virtual Reality's Application on the Simulation of Weapon Systems' Antagonism

    Institute of Scientific and Technical Information of China (English)

    詹荣开; 王宏伟; 贺汉根

    2001-01-01

    Traditional military drill or weapon system's performance evaluation is often accomplished by a sham battle with true weapon systems.With the fast development of virtual reality,virtual sham battle,which integrates virtual reality and weapon systems' simulation,has become possible.Based on the summarization to virtual reality,this paper emphatically discusses virtual reality's application on the simulation of weapon systems'antagonism and a few typical problems in it.At last,a few future development directions are listed.%传统的军事训练或武器系统性能评估通常都采用有真实武器系统的训练或军事演习来进行。随着虚拟现实技术的迅速发展,将它与系统仿真相结合来进行虚拟对抗演练已经成为可能。文中在概述虚拟现实技术的基础上,着重探讨了虚拟现实技术在武器对抗仿真中的应用及其中几个较为典型的问题,并提出了今后的发展方向。

  9. 基于ADC方法的复杂武器系统效能评估方法%Research on Effect Valuation to the Complicated Weapon System Based on ADC

    Institute of Scientific and Technical Information of China (English)

    王晅; 陶禹; 樊丹瑛

    2016-01-01

    ADC method is one of the important methods to assess the effectiveness of weapon equipment. Traditional ADC methods also simplify individual subsystems of weapon system to the series system. In this paper,the ADC methods is optimizes aimed at the various subsystems composed of numerous,complex series-parallel relationship,varying degree of impact on the operational of complex weapon systems. On this method,ADC approach allows a more objective assessment of multiple parallel systems. The actual verification by a certain type of weaponry ADC improved method reasonably practicable,can have a more objective and comprehensive evaluation of complex weapons systems,can be used as reference to other complex weapon system effectiveness assessment methods.%ADC方法是武器装备效能评估的重要方法之一。传统ADC方法一般将武器系统各个分系统简化为串联系统计算。针对复杂武器系统中各个分系统组成繁多、串并联关系复杂、对作战影响程度不一等特点,对ADC方法进行了优化,使得ADC方法可以针对多并联系统更客观地评估。通过某型武器装备的实际验证,改进后的ADC方法合理可行,可以对复杂武器系统拥有更客观和更全面地评价,可作为其他复杂武器系统效能评估方法的参考。

  10. 武器装备全面质量管理目标分析方法研究%Research on Analysis Approach of Weapon Equipment Total Quality Management Goal

    Institute of Scientific and Technical Information of China (English)

    孟冲; 宋华文

    2012-01-01

    为深入实践全面质量管理思想,切实推进武器装备质量管理科学化、精益化发展,提出了一种精益的武器装备全面质量管理目标分析方法.首先,阐释了武器装备全面质量管理目标分析方法的基本内涵及其优越性.其次,提出了该种分析方法的基本实施步骤,一是基于QFD方法构建武器装备设计、研制、生产、试验、维修全过程质量管理目标链;二是基于ANP-ZOGP方法逐步确定阶段武器装备质量管理目标.最后,以某飞行器测发系统设计质量管理目标分析为例,验证了该分析方法的有效性.%In order to carry out total quality management idea, advance weapon equipment quality management scientific and lean development effectively, a lean analysis approach of weapon equipment total quality management goal was put forward. Firstly,the basic meanings and superiorities of analysis approach of weapon equipment total quality management goal were explained. Secondly,the implement steps of this analysis approach were put forward. In this first step, the quality management goal link of weapon equipment design, develop, manufacture, trial and service was established based on QFD. In this second step, weapon equipment quality management goals were ascertained in every phase step by step. Lastly, taking aircraft test and control system design quality management goal as an example, the validity of this analysis approach was validated.

  11. Development of neutron radiography facility for boiling two-phase flow experiment in Kyoto University Research Reactor

    Science.gov (United States)

    Saito, Y.; Sekimoto, S.; Hino, M.; Kawabata, Y.

    2011-09-01

    To visualize boiling two-phase flow at high heat flux by using neutron radiography, a new neutron radiography facility was developed in the B-4 beam hole of KUR. The B-4 beam hole is equipped with a supermirror neutron guide tube with a characteristic wavelength of 1.2 Å, whose geometrical parameters of the guide tube are: 11.7 m total length and 10 mm wide ×74 mm high beam cross-section. The total neutron flux obtained from the KUR supermirror guide tube is about 5×10 7 n/cm 2 s with a nominal thermal output of 5 MW of KUR, which is about 100 times what is obtainable with the conventional KUR neutron radiography facility (E-2 beam hole). In this study a new imaging device, an electric power supply (1200 A, 20 V), and a thermal hydraulic loop were installed. The neutron source, the beam tube, and the radiography rooms are described in detail and the preliminary images obtained at the developed facility are shown.

  12. Neutron Radiography

    Science.gov (United States)

    Heller, A. K.; Brenizer, J. S.

    Neutron radiography and its related two-dimensional (2D) neutron imaging techniques have been established as invaluable nondestructive inspection methods and quantitative measurement tools. They have been used in a wide variety of applications ranging from inspection of aircraft engine turbine blades to study of two-phase fluid flow in operating proton exchange membrane fuel cells. Neutron radiography is similar to X-ray radiography in that the method produces a 2D attenuation map of neutron radiation that has penetrated the object being examined. However, the images produced differ and are often complementary due to the differences between X-ray and neutron interaction mechanisms. The uses and types of 2D neutron imaging have expanded over the past 15 years as a result of advances in imaging technology and improvements in neutron generators/sources and computers. Still, high-intensity sources such as those from reactors and spallation neutron sources, together with conventional film radiography, remain the mainstay of high-resolution, large field-of-view neutron imaging. This chapter presents a summary of the history, methods, and related variations of neutron radiography techniques.

  13. Plans for future neutron facilities within the DOE Office of Energy Research

    Energy Technology Data Exchange (ETDEWEB)

    Thomas, I.

    1995-10-01

    M.R.C. Greenwood brought out some things about the importance of making sure that the public, who funds our work, knows that there is value to it. Currently, the Basic Energy Sciences (BES) advisory committee has a panel that is doing just that for BES research. I insisted that this panel not be the same folks. It is chaired by an economist and it has several nontechnical members on it. I wanted them to have some, you might say, people off the street on it. I have some confidence that often when you bring things to the people, you get good decisions.

  14. Neutron research and facility development at the Oak Ridge Electron Linear Accelerator 1970 to 1995

    Energy Technology Data Exchange (ETDEWEB)

    Peelle, R.W.; Harvey, J.A.; Maienschein, F.C.; Weston, L.W.; Olsen, D.K.; Larson, D.C.; Macklin, R.L.

    1982-07-01

    This report reviews the accomplishments of the first decade of operation of the Oak Ridge Electron Linear Accelerator (ORELA) and discusses the plans for the facility in the coming decade. Motivations for scientific and applied research during the next decade are included. In addition, ORELA is compared with competing facilities, and prospects for ORELA's improvement and even replacement are reported. Development efforts for the next few years are outlined that are consistent with the anticipated research goals. Recommendations for hardware development include improving the electron injection system to give much larger short-pulse currents on a reliable basis, constructing an Electron Beam Injector Laboratory to help make this improvement possible, continuing a study of possibly replacing the electron accelerator with a proton machine, and replacing or upgrading the facility's data-acquistion and immediate-analysis computer systems. Increased operating time and more involvement of nuclear theorists are recommended, and an effective staff size for optimum use of this unique facility is discussed. A bibliography of all ORELA-related publications is included.

  15. [Myocardial infarction after conduction electrical weapon shock].

    Science.gov (United States)

    Ben Ahmed, H; Bouzouita, K; Selmi, K; Chelli, M; Mokaddem, A; Ben Ameur, Y; Boujnah, M R

    2013-04-01

    Controversy persists over the safety of conducted electrical weapons, which are increasingly used by law enforcement agencies around the world. We report a case of 33-year-old man who had an acute inferior myocardial infarction after he was shot in the chest with an electrical weapon. Copyright © 2012 Elsevier Masson SAS. All rights reserved.

  16. Radioactive Fallout From Nuclear Weapons Testing ...

    Science.gov (United States)

    2017-08-07

    Detonating nuclear weapons above ground sends radioactive materials into the atmosphere from the ground level up to very high elevations. Overtime, these materials settle out of the atmosphere and fall to the ground. Fallout typically contains hundreds of different radionuclides. Since the end of aboveground nuclear weapons testing, radionuclides have largely decayed away.

  17. Color image fusion for concealed weapon detection

    NARCIS (Netherlands)

    Toet, A.

    2003-01-01

    Recent advances in passive and active imaging sensor technology offer the potential to detect weapons that are concealed underneath a person's clothing or carried along in bags. Although the concealed weapons can sometimes easily be detected, it can be difficult to perceive their context, due to the

  18. Weapons Acquisition. Processes of Selected Foreign Government.

    Science.gov (United States)

    1986-02-01

    period from 1977 to 1985: (1) 5.56mm calibre assault rifle. (2) Milan and Hot antitank weapon systems. (3) Roland ground-to-air weapon system. (4) AMX 30...and standardization edicts . Awards and penalties are laid on accordingly. (7/17, 13/20) The ministries stand apart from one another in the same way

  19. Nuclear weapons, nuclear effects, nuclear war

    Energy Technology Data Exchange (ETDEWEB)

    Bing, G.F.

    1991-08-20

    This paper provides a brief and mostly non-technical description of the militarily important features of nuclear weapons, of the physical phenomena associated with individual explosions, and of the expected or possible results of the use of many weapons in a nuclear war. Most emphasis is on the effects of so-called ``strategic exchanges.``

  20. Color image fusion for concealed weapon detection

    NARCIS (Netherlands)

    Toet, A.

    2003-01-01

    Recent advances in passive and active imaging sensor technology offer the potential to detect weapons that are concealed underneath a person's clothing or carried along in bags. Although the concealed weapons can sometimes easily be detected, it can be difficult to perceive their context, due to the

  1. Overview of surplus weapons plutonium disposition

    Energy Technology Data Exchange (ETDEWEB)

    Rudy, G.

    1996-05-01

    The safe disposition of surplus weapons useable plutonium is a very important and urgent task. While the functions of long term storage and disposition directly relate to the Department`s weapons program and the environmental management program, the focus of this effort is particularly national security and nonproliferation.

  2. US develops neutron to sniff out nuclear material

    CERN Multimedia

    2002-01-01

    The USA has developed a tiny portable neutron device that can detect hidden nuclear materials. The device is undergoing trials in the Argonne National Laboratory to see if it could be used to stop smuggling and unauthorised use of nuclear weapons and materials (1/2 page).

  3. DeveIopment and Current Researches of Weapon Equipment OperationaI Test%武器装备作战试验发展与研究现状分析

    Institute of Scientific and Technical Information of China (English)

    赵继广; 柯宏发; 康丽华; 黄彦昌

    2015-01-01

    Meeting the realistic combat requirement is the basic requirement of weapon equipment construction.Further perfection and specification of equipment operational test have become one of the prominent problems.Firstly,current operational tests of main military powers in the world such as US,Britain,France and Russia,especially the development course,management systems,new test mode and test talents education of US are analyzed in this paper.Secondly,current equipment operational tests domestically are also discussed.From perspectives such as test objective,test envi-ronment,test direction and test mode,the paper defines the operational test;and then points out weak links in current operational test,like relatively backward demand research,superficial research on test management theory and test technology and insufficient test environment.Finally,the paper brings suggestions on the equipment operational tests from five respects such as demand of operational test,theory and method of innovating operational test,construction of test environment and training of test operators.%武器装备建设的基本要求是满足实战需要,进一步完善、规范装备作战试验成为其中最突出的问题。分析了美、英、法、俄等世界主要军事大国的作战试验发展现状,研究了美军作战试验的发展历程、管理体制、新试验模式、人才培养等方面的特点;分析了国内装备作战试验研究现状,基于试验目的、试验环境、试验主体、试验模式等角度给出了作战试验的定义;指出了目前作战试验存在需求研究相对滞后,试验管理理论和试验技术研究不深入,条件建设不充分等薄弱环节;最后从作战试验需求、作战试验管理理论、作战试验理论方法、试验条件建设及试验人才培养5个方面,对开展装备作战试验研究提出了建议。

  4. Childhood maltreatment and threats with weapons.

    Science.gov (United States)

    Casiano, Hygiea; Mota, Natalie; Afifi, Tracie O; Enns, Murray W; Sareen, Jitender

    2009-11-01

    The relationship between childhood maltreatment and future threats with weapons is unknown. We examined data from the nationally representative National Comorbidity Survey Replication (n = 5692) and conducted multiple logistic regression analyses to determine the association between childhood maltreatment and lifetime behavior of threatening others with a gun or other weapon. After adjusting for sociodemographic variables, physical abuse, sexual abuse, and witnessing domestic violence were significantly associated with threats made with a gun (adjusted odds ratios [AOR] ranging between 3.38 and 4.07) and other weapons (AOR ranging between 2.16 and 2.83). The greater the number of types of maltreatment experienced, the stronger the association with lifetime threats made to others with guns and any weapons. Over 94% of respondents who experienced maltreatment and made threats reported that the maltreatment occurred prior to threatening others with weapons. Prevention efforts that reduce exposure to maltreatment may reduce violent behavior in later life.

  5. Weapon Control System for Airborne Application.

    Directory of Open Access Journals (Sweden)

    M. Sankar Kishore

    2000-07-01

    Full Text Available The integrated fire' control system (IFCS plays an important role in the present-day fighter aircraft and helicopters. Wecapons, such as missiles (active/passive, rockets and guns may be present on thelfighter aircraft or helicopter .IFCS monitors the status of the weapons present on the vehicle and passes the information to pilot/co-pilot. Depending upon the health/availability of the weapons, IFCS selects/fires the weapons. An attempt has been made to bring out the details of one such IFCS. As a I stepping stone, smaller version is developed and same philosophy can be used for integrating ftlore and I more weapons. Here, emphasis has been made on design and development of weapon control unit which is the heart f IFCS, both in hardware and software. The system has been developed using a 486 DX2 processor, and an elaborate software has been developed in PL/M.

  6. Weapon Involvement in the Victimization of Children.

    Science.gov (United States)

    Mitchell, Kimberly J; Hamby, Sherry L; Turner, Heather A; Shattuck, Anne; Jones, Lisa M

    2015-07-01

    To report the prevalence of weapons involved in the victimization of youth with particular emphasis on weapons with a "high lethality risk" and how such exposure fits into the broader victimization and life experiences of children and adolescents. Data were collected as part of the Second National Survey of Children's Exposure to Violence, a nationally representative telephone survey of youth ages 2 to 17 years and caregivers (N = 4114) conducted in 2011. Estimates from the Second National Survey of Children's Exposure to Violence indicate that almost 14 million youth, ages 2–17, in the United States have been exposed to violence involving a weapon in their lifetimes as witnesses or victims,or .1 in 5 children in this age group [corrected]. More than 2 million youth in the United States (1 in 33) have been directly assaulted in incidents where the high lethality risk weapons of guns and knives were used. Differences were noted between victimizations involving higher and lower lethality risk weapons as well as between any weapon involvement versus none. Poly-victims, youth with 7 or more victimization types, were particularly likely to experience victimization with any weapon, as well as victimization with a highly lethal weapon compared with nonpoly-victims. Findings add to the field's broadening conceptualization of youth victimization highlighting the potentially highly consequential risk factor of weapon exposure as a component of victimization experiences on the mental health of youth. Further work on improving gun safety practices and taking steps to reduce children's exposure to weapon-involved violence is warranted to reduce this problem. Copyright © 2015 by the American Academy of Pediatrics.

  7. Concealed weapons detection using electromagnetic resonances

    Science.gov (United States)

    Hunt, Allen R.; Hogg, R. Douglas; Foreman, William

    1998-12-01

    Concealed weapons pose a significant threat to both law enforcement and security agency personnel. The uncontrolled environments associated with peacekeeping and the move toward relaxation of concealed weapons laws here in the U.S. provide a strong motivation for developing weapons detection technologies which are noninvasive and can function noncooperatively. Existing weapons detection systems are primarily oriented to detecting metal and require the cooperation of the person being searched. The new generation of detectors under development that focuses primarily on imaging methods, faces problems associated with privacy issues. There remains a need for a weapons detector which is portable, detects weapons remotely, avoids the issues associated with privacy rights, can tell the difference between car keys and a knife, and is affordable enough that one can be issued to every peacekeeper and law enforcement officer. AKELA is developing a concealed weapons detector that uses wideband radar techniques to excite natural electromagnetic resonances that characterize the size, shape, and material composition of an object. Neural network processing is used to classify the difference between weapons and nuisance objects. We have constructed both time and frequency domain test systems and used them to gather experimental data on a variety of armed and unarmed individuals. These experiments have been performed in an environment similar to the operational environment. Preliminary results from these experiments show that it is possible to detect a weapon being carried by an individual from a distance of 10 to 15 feet, and to detect a weapon being concealed behind the back. The power required is about 100 milliwatts. A breadboard system is being fabricated and will be used by AKELA and our law enforcement partner to gather data in operationally realistic situations. While a laptop computer will control the breadboard system, the wideband radar electronics will fit in a box the

  8. A neutronic feasibility study for LEU conversion of the WWR-SM research reactor in Uzbekistan.

    Energy Technology Data Exchange (ETDEWEB)

    Rakhmanov, A.

    1998-10-19

    The WWR-SM research reactor in Uzbekistan has operated at 10 MW since 1979, using Russian-supplied IRT-3M fuel assemblies containing 90% enriched uranium. Burnup tests of three full-sized IRT-3M FA with 36% enrichment were successfully completed to a burn up of about {approximately}50% in 1987-1989. In August 1998, four IRT-3M FA with 36% enriched uranium were loaded into the core to initiate conversion of the entire core to 36% enriched fuel. This paper presents the results of equilibrium fuel cycle comparisons of the reactor using HEU (90%) and HEU (36%) IRT-3M fuel and compares results with the performance of IRT-4M FA containing LEU (19.75%). The results show that an LEU (19.75%) density of 3.8 g/cm{sup 3} is required to match the cycle length of the HEU (90%) core and an LEU density 3.9 g/cm{sup 3} is needed to match the cycle length of the HEU (36%) core.

  9. Weapons barrel life cycle determination

    Directory of Open Access Journals (Sweden)

    Nebojša Pene Hristov

    2013-10-01

    Full Text Available This article describes the dynamic processes within the gun barrel during the firing process in exploitation. It generally defines the basic principles of constructing tube elements, and shows the distortion of the basic geometry of the tube interior due to wear as well as the impact it causes during exploitation. The article also defines basic empirical models as well as a model based on fracture mechanics for the calculation of a use-life of the barrel, and other elements essential for the safe use of the barrel as the basic weapon element. Erosion causes are analysed in order to control and reduce wear and prolong the lifetime of the gun barrel. It gives directions for the reparation of barrels with wasted resources. In conclusion, the most influential elements of tube wear are given as well as possible modifications of existing systems, primarily propellant charges, with a purpose of prolonging lifetime of gun barrels. The guidelines for a proper determination of the lifetime based on the barrel condition assessment are given as well. INTRODUCTION The barrel as the basic element of each weapon is described as well as the processes occurring during the firing that have impulsive character and are accompanied by large amounts of energy. The basic elements of barrel and itheir constructive characteristics are descibed. The relation between Internal ballistics, ie calculation of the propellant gas pressure in the firing process, and structural elements defined by the barrel material resistance is shown. In general, this part of the study explains the methodology of the gun barrel structural elements calculation, ie. barrel geometry, taking into account the degrees of safety in accordance with Military Standards.   TUBE WEAR AND DEFORMATIONS The weapon barrel gradually wears out during exploitation due to which it no longer satisfies the set requirements. It is considered that the barrel has experienced a lifetime when it fails to fulfill the

  10. Neutron Albedo

    CERN Document Server

    Ignatovich, V K

    2005-01-01

    A new, algebraic, method is applied to calculation of neutron albedo from substance to check the claim that use of ultradispersive fuel and moderator of an active core can help to gain in size and mass of the reactor. In a model of isotropic distribution of incident and reflected neutrons it is shown that coherent scattering on separate grains in the case of thermal neutrons increases transport cross section negligibly, however it decreases albedo from a wall of finite thickness because of decrease of substance density. A visible increase of albedo takes place only for neutrons with wave length of the order of the size of a single grain.

  11. Neutron scattering in Australia

    Energy Technology Data Exchange (ETDEWEB)

    Knott, R.B. [Australian Nuclear Science and Technology Organisation, Menai (Australia)

    1994-12-31

    Neutron scattering techniques have been part of the Australian scientific research community for the past three decades. The High Flux Australian Reactor (HIFAR) is a multi-use facility of modest performance that provides the only neutron source in the country suitable for neutron scattering. The limitations of HIFAR have been recognized and recently a Government initiated inquiry sought to evaluate the future needs of a neutron source. In essence, the inquiry suggested that a delay of several years would enable a number of key issues to be resolved, and therefore a more appropriate decision made. In the meantime, use of the present source is being optimized, and where necessary research is being undertaken at major overseas neutron facilities either on a formal or informal basis. Australia has, at present, a formal agreement with the Rutherford Appleton Laboratory (UK) for access to the spallation source ISIS. Various aspects of neutron scattering have been implemented on HIFAR, including investigations of the structure of biological relevant molecules. One aspect of these investigations will be presented. Preliminary results from a study of the interaction of the immunosuppressant drug, cyclosporin-A, with reconstituted membranes suggest that the hydrophobic drug interdigitated with lipid chains.

  12. Neutron multiplication error in TRU waste measurements

    Energy Technology Data Exchange (ETDEWEB)

    Veilleux, John [Los Alamos National Laboratory; Stanfield, Sean B [CCP; Wachter, Joe [CCP; Ceo, Bob [CCP

    2009-01-01

    Total Measurement Uncertainty (TMU) in neutron assays of transuranic waste (TRU) are comprised of several components including counting statistics, matrix and source distribution, calibration inaccuracy, background effects, and neutron multiplication error. While a minor component for low plutonium masses, neutron multiplication error is often the major contributor to the TMU for items containing more than 140 g of weapons grade plutonium. Neutron multiplication arises when neutrons from spontaneous fission and other nuclear events induce fissions in other fissile isotopes in the waste, thereby multiplying the overall coincidence neutron response in passive neutron measurements. Since passive neutron counters cannot differentiate between spontaneous and induced fission neutrons, multiplication can lead to positive bias in the measurements. Although neutron multiplication can only result in a positive bias, it has, for the purpose of mathematical simplicity, generally been treated as an error that can lead to either a positive or negative result in the TMU. While the factors that contribute to neutron multiplication include the total mass of fissile nuclides, the presence of moderating material in the matrix, the concentration and geometry of the fissile sources, and other factors; measurement uncertainty is generally determined as a function of the fissile mass in most TMU software calculations because this is the only quantity determined by the passive neutron measurement. Neutron multiplication error has a particularly pernicious consequence for TRU waste analysis because the measured Fissile Gram Equivalent (FGE) plus twice the TMU error must be less than 200 for TRU waste packaged in 55-gal drums and less than 325 for boxed waste. For this reason, large errors due to neutron multiplication can lead to increased rejections of TRU waste containers. This report will attempt to better define the error term due to neutron multiplication and arrive at values that are

  13. Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods. Stage 11 and 12. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Sunde, C.; Pazsit, I.; Demaziere, C.; Dahl, O.; Mileshina, L. [Chalmers Univ. of Technology, Goeteborg (Sweden). Dept. of Nuclear Engineering

    2006-06-15

    This report describes the results obtained during Stage 11 and 12 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. The long-term goals are elaborated in more detail in e.g. the Final Reports of stage 1 and 2 (SKI Report 95:14 and 96:50). Higher order eigenfunctions and eigenvalues of the diffusion equation, describing a static core, have lost their significance when doing calculations in realistic systems, since there are usually made by nodal methods or other direct numerical techniques. However, there are situations when knowledge of the higher order modes is still useful. Such case is the separation of the global and regional flux oscillations in the case of BWR instability. Another case is the investigation of the stability properties of large inhomogeneous cores, which is usually quantified with the so-called eigenvalue separation, ES=1/k{sub 1} - 1/k{sub 0} where k{sub 0} and k{sub 1}, are the fundamental and first higher order eigenvalues, respectively. Numerical codes used for ICMF calculations usually do not have the option of calculating the higher order eigenvalues and eigenfunctions. In idealised systems, these can be calculated with semi-analytical methods. In order to get insight into the characteristics of the higher order eigenmodes of the neutron flux and the adjoint, these were calculated in a reflected homogeneous system with two-group theory. The adjoint eigenmodes are necessary if an orthogonality property needs to be used, such as the separation of the modes from a flux shape which is a sum of several eigenmodes. At the same time, the so-called numerical noise simulator, developed at the Dept., was extended such that it became suitable for the calculation of the higher order eigenmodes, both direct and adjoint ones. This simulator can treat real inhomogeneous cores, with an input deck compatible with that of SIMULATE. The simulator was used to calculate the

  14. Quality control and performance evaluation of k{sub 0}-based neutron activation analysis at the Portuguese research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Dung, H.M., E-mail: m.hodzung@itn.p [Instituto Technologico e Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Freitas, M.C. [Instituto Technologico e Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal); Blaauw, M. [Reactor Institute Delft, Delft University of Technology, Mekelweg 15, 2629 JB Delft (Netherlands); Almeida, S.M.; Dionisio, I.; Canha, N.H. [Instituto Technologico e Nuclear, Estrada Nacional 10, 2686-953 Sacavem (Portugal)

    2010-10-11

    The quality control (QC) and performance evaluation for the k{sub 0}-based neutron activation analysis (k{sub 0}-NAA) at the Portuguese research reactor (RPI) has been developed with the intention of using the method to meet the demands of trace element analysis for the applications in environmental, epidemiological and nutritional studies amongst others. The QC and performance evaluation include the following aspects: (1) estimation of the overall/combined standard uncertainty from the primary uncertainty sources; (2) validation of the method using a synthetic multi-element standard (SMELS); and (3) analysis of the certified reference materials from the National Institute of Standards and Technology (USA): NIST-SRM-1633a and NIST-SRM-1648 and the reference material from the International Atomic Energy Agency: IAEA-RM-336, for the purpose of controlling the overall accuracy and precision of the analytical results. The obtained results revealed that the k{sub 0}-NAA method established at the RPI was fit for the purpose. The overall/combined standard uncertainty was estimated for elements of interest in the intended applications. The laboratory's analytical results as compared to the assigned values with the bias were less than 12% for most elements, except for a few elements which biased within 13-18%. The u-score values for most elements were less than |1.64|, except for Co, La and Ti within |1.64|-|1.96| and Sc, Cr, K and Sb within |1.96|-|2.58|. The NIST-1633a was also analyzed over 14 months for the purpose of evaluating the reproducibility of the method. The quality factors of k{sub 0}-NAA established at RPI were evaluated, proving that the method meets the requirements of trace element analysis, which is also considering the method's performance for which the k{sub 0}-NAA affords a specific, rapid and convenient capability for the intended applications.

  15. Measurement and analysis of neutron flux distribution of STACY heterogeneous core by position sensitive proportional counter. Contract research

    CERN Document Server

    Murazaki, M; Uno, Y

    2003-01-01

    We have measured neutron flux distribution around the core tank of STACY heterogeneous core by position sensitive proportional counter (PSPC) to develop the method to measure reactivity for subcritical systems. The neutron flux distribution data in the position accuracy of +-13 mm have been obtained in the range of uranium concentration of 50g/L to 210g/L both in critical and in subcritical state. The prompt neutron decay constant, alpha, was evaluated from the measurement data of pulsed neutron source experiments. We also calculated distribution of neutron flux and sup 3 He reaction rates at the location of PSPC by using continuous energy Monte Carlo code MCNP. The measurement data was compared with the calculation results. As results of comparison, calculated values agreed generally with measurement data of PSPC with Cd cover in the region above half of solution height, but the difference between calculated value and measurement data was large in the region below half of solution height. On the other hand, ...

  16. Neutronic analysis for core conversion (HEU–LEU of the low power research reactor using the MCNP4C code

    Directory of Open Access Journals (Sweden)

    Aldawahra Saadou

    2015-06-01

    Full Text Available Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad cores have been analyzed in this study. The existing HEU core of MNSR was analyzed to validate the neutronic model of reactor, while the LEU core was studied to prove the possibility of fuel conversion of the existing HEU core. The proposed LEU core contained the same number of fuel pins as the HEU core. All other structure materials and dimensions of HEU and LEU cores were the same except the increase in the radius of control rod material from 0.195 to 0.205 cm and keeping the outer diameter of the control rod unchanged in the LEU core. The effective multiplication factor (keff, excess reactivity (ρex, control rod worth (CRW, shutdown margin (SDM, safety reactivity factor (SRF, delayed neutron fraction (βeff and the neutron fluxes in the irradiation tubes for the existing and the potential LEU fuel were investigated. The results showed that the safety parameters and the neutron fluxes in the irradiation tubes of the LEU fuels were in good agreements with the HEU results. Therefore, the LEU fuel was validated to be a suitable choice for fuel conversion of the MNSR in the future.

  17. Measurement and analysis of neutron flux distribution of STACY heterogeneous core by position sensitive proportional counter. Contract research

    Energy Technology Data Exchange (ETDEWEB)

    Murazaki, Minoru; Uno, Yuichi; Miyoshi, Yoshinori [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    2003-03-01

    We have measured neutron flux distribution around the core tank of STACY heterogeneous core by position sensitive proportional counter (PSPC) to develop the method to measure reactivity for subcritical systems. The neutron flux distribution data in the position accuracy of {+-}13 mm have been obtained in the range of uranium concentration of 50g/L to 210g/L both in critical and in subcritical state. The prompt neutron decay constant, {alpha}, was evaluated from the measurement data of pulsed neutron source experiments. We also calculated distribution of neutron flux and {sup 3}He reaction rates at the location of PSPC by using continuous energy Monte Carlo code MCNP. The measurement data was compared with the calculation results. As results of comparison, calculated values agreed generally with measurement data of PSPC with Cd cover in the region above half of solution height, but the difference between calculated value and measurement data was large in the region below half of solution height. On the other hand, calculated value agreed well with measurement data of PSPC without Cd cover. (author)

  18. Surface and Downhole Prospecting Tools for Planetary Exploration: Tests of Neutron and Gamma Ray Probes - Research Paper

    Energy Technology Data Exchange (ETDEWEB)

    R. C. Elphic; P. Chu; S. Hahn; M. R. James; D. J. Lawrence; T. H. Prettyman; J. B. Johnson; R. K. Podgorney

    2008-06-01

    The ability to locate and characterize icy deposits and other hydrogenous materials on the Moon and Mars will help us understand the distribution of water and, therefore, possible habitats at Mars, and may help us locate primitive prebiotic compounds at the Moon’s poles. We have developed a rover-borne neutron probe that localizes a near-surface icy deposit and provides information about its burial depth and abundance. We have also developed a borehole neutron probe to determine the stratigraphy of hydrogenous subsurface layers while operating within a drill string segment. In our field tests, we have used a neutron source to “illuminate” surrounding materials and gauge the instruments’ efficacy, and we can simulate accurately the observed instrument responses using a Monte Carlo nuclear transport code (MCNPX). An active neutron source would not be needed for lunar or martian near-surface exploration: cosmic-ray interactions provide sufficient neutron flux to depths of several meters and yield better depth and abundance sensitivity than an active source. However, for deep drilling (>10 m depth), a source is required. We also present initial tests of a borehole gamma ray lithodensity tool and demonstrate its utility in determining soil or rock densities and composition.

  19. The Manuel Lujan Jr. Neutron Scattering Center (LANSCE) experiment reports 1993 run cycle. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    Farrer, R.; Longshore, A. [comps.

    1995-06-01

    This year the Manuel Lujan Jr. Neutron Scattering Center (LANSCE) ran an informal user program because the US Department of Energy planned to close LANSCE in FY1994. As a result, an advisory committee recommended that LANSCE scientists and their collaborators complete work in progress. At LANSCE, neutrons are produced by spallation when a pulsed, 800-MeV proton beam impinges on a tungsten target. The proton pulses are provided by the Clinton P. Anderson Meson Physics Facility (LAMPF) accelerator and a associated Proton Storage Ring (PSR), which can Iter the intensity, time structure, and repetition rate of the pulses. The LAMPF protons of Line D are shared between the LANSCE target and the Weapons Neutron Research (WNR) facility, which results in LANSCE spectrometers being available to external users for unclassified research about 80% of each annual LAMPF run cycle. Measurements of interest to the Los Alamos National Laboratory (LANL) may also be performed and may occupy up to an additional 20% of the available beam time. These experiments are reviewed by an internal program advisory committee. This year, a total of 127 proposals were submitted. The proposed experiments involved 229 scientists, 57 of whom visited LANSCE to participate in measurements. In addition, 3 (nuclear physics) participating research teams, comprising 44 scientists, carried out experiments at LANSCE. Instrument beam time was again oversubscribed, with 552 total days requested an 473 available for allocation.

  20. Penning trap mass measurements and laser spectroscopy on neutron-rich fission products extracted from the research reactor TRIGA-Mainz

    Energy Technology Data Exchange (ETDEWEB)

    Eibach, Martin; Ketelaer, Jens; Ketter, Jochen; Knuth, Konstantin [Institut fuer Physik, Universitaet Mainz (Germany); Blaum, Klaus; Nagy, Szilard [Max-Planck-Institut fuer Kernphysik, Heidelberg (Germany); Eberhardt, Klaus; Noertershaeuser, Wilfried [Institut fuer Kernchemie, Universitaet Mainz (Germany); Herfurth, Frank [GSI, Helmholtzzentrum fuer Schwerionenforschung GmbH, Darmstadt (Germany); Smorra, Christian [Physikalisches Institut, Universitaet Heidelberg (Germany); Institut fuer Kernchemie, Universitaet Mainz (Germany)

    2009-07-01

    TRIGA-SPEC is a setup for Penning trap mass spectrometry and collinear laser spectroscopy on short-lived neutron-rich nuclides located at the research reactor TRIGA-Mainz. It is dedicated to the determination of nuclear ground-state properties like masses and charge-radii. The nuclides are produced by neutron-induced fission of an actinide target located in a target chamber near the reactor core. It is required to extract the nuclides fast and with high efficiency from the target chamber in order to make precision experiments on short-living species with half-lives in the order of 1s. To this end, they are flushed out with a helium gas jet containing carbon aerosols and transported through a skimmer region to an ECR ion source. The characterisation of the carbon aerosol generator and the verification of transported fission products are presented.

  1. The power distribution and neutron fluence measurements and calculations in the VVER-1000 Mock-Up on the LR-0 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Kostal, M.; Juricek, V.; Rypar, V.; Svadlenkova, M. [Research Center Rez Ltd., 250 68 Husinec-Rez 130 (Czech Republic); Cvachovec, F. [Univ. of Defence, Kounicova 65, 662 10 Brno (Czech Republic)

    2011-07-01

    The power density distribution in a reactor has significant influence on core structures and pressure vessel mechanical resistance, as well as on the physical characteristics of nuclear fuel. This quantity also has an effect on the leakage neutron and photon field. This issue has become of increasing importance, as it touches on actual questions of the VVER nuclear power plant life time extension. This paper shows the comparison of calculated and experimentally determined pin by pin power distributions. The calculation has been performed with deterministic and Monte Carlo approaches. This quantity is accompanied by the neutron and photon flux density calculation and measurements at different points of the light water zero-power (LR-0) research reactor mock-up core, reactor built-in component (core barrel), and reactor pressure vessel and model. The effect of the different data libraries used for calculation is discussed. (authors)

  2. 基于任务的潜用导弹武器系统保障性仿真评价%Simulation evaluation research on supportability of missile weapon system based on mission

    Institute of Scientific and Technical Information of China (English)

    衡辉; 魏勇; 王新华; 杨迎化

    2013-01-01

    The defects existed in the traditional research of supportability were analyzed,some new evaluation indexes,including operational availability,operational readiness,mission completion success probability,were advanced,and the simulation model was established based on mission.Taking the operational mission,the structure and maintenance process as the foundation,a kind of simulating principle of missile weapon system was set up based on mission by using the theory of Monte-Carlo,Discrete Event and so on.The maintenance support simulation experiment was analyzed by an example.The evaluative parameters of mission capability on duty and support capabilities were acquired 、 Results of its application show that the method is feasible,can offer the decision for useful department and managing department.%分析传统保障性评价存在的缺陷,提出基于任务的使用可用度、战备完好率及任务成功率3个评价指标,建立相应的仿真统计模型.以使用任务、系统结构、维修保障过程分析为基础,引用离散事件、蒙特卡洛等理论建立一种基于任务的保障性评价仿真原理.通过一个实例对导弹武器系统的维修保障仿真试验进行分析,得出了导弹武器系统的执行任务能力和保障能力评价参数.仿真表明该方法是可行的,可为使用、维修保障部门评价装备的任务成功性和战备完好性等提供理论依据和方法支持.

  3. Taser and Conducted Energy Weapons.

    Science.gov (United States)

    LeClair, Thomas G; Meriano, Tony

    2015-01-01

    It is clear that CEWs are an increasingly prevalent law enforcement tool, adopted to address a complex and challenging problem. The potential for serious injury from a single deployment of a CEW is extremely low. The debate regarding the link between these electrical weapons and sudden in-custody death is likely to continue because their use is often in complex and volatile situations. Any consideration of injuries has to be put into that context. One must also consider what injuries to a subject would result if an alternative force method was used. Furthermore, the potential benefits of CEWs, including reduction in injuries to the public and law-enforcement officers, need to be considered.

  4. Air guns: toys or weapons?

    Science.gov (United States)

    Aslan, Sahin; Uzkeser, Mustafa; Katirci, Yavuz; Cakir, Zeynep; Bilir, Ozlem; Bilge, Fatih; Cakir, Murtaza

    2006-09-01

    Air guns and blank guns may appear relatively harmless at first glance, but they are, in fact, potentially destructive, even lethal, weapons. Approximately 2 to 2.5 million nonpowder firearms are sold annually, and again approximately 12.9 per 100,000 population are treated for such injuries in hospital emergency departments each year in the United States. Unfortunately, these guns are considered to be a toy for children. Therefore, incidents of air gun injuries are gradually increasing. Although such injuries may initially be considered trivial, it may signify severe internal tissue pathologies. These apparently trivial injuries may have catastrophic consequences if unnoticed. In this study, we report 4 cases with head injury due to a shot by these guns. The cases indicate that these people had used the guns belonging to their parents for the purpose of suicide. The cases also show that these machines are not innocent.

  5. Electronic eyebox for weapon sights

    Science.gov (United States)

    Szapiel, Stan; Greenhalgh, Catherine; Wagner, Kevin; Nobes, Ryan

    2016-05-01

    We expand the effective size of the eyebox of a magnified telescopic weapon sight by following the movements of the operator's eye to create a larger, `electronic eyebox'. The original eyebox of the telescope is dynamically relocated in space so that proper overlap between the pupil of the eye and the exit pupil of the device is maintained. Therefore, the operator will perceive the entire field of view of the instrument in a much bigger spatial region than the one defined by the original eyebox. Proof-of-the-concept results are presented with a more than 3.5X enlargement of the eyebox volume along with recommendations for the next phase of development.

  6. Research on anisotropy of fusion-produced protons and neutrons emission from high-current plasma-focus discharges

    Energy Technology Data Exchange (ETDEWEB)

    Malinowski, K., E-mail: karol.malinowski@ncbj.gov.pl; Sadowski, M. J.; Szydlowski, A. [National Centre for Nuclear Research (NCBJ), 05-400 Otwock (Poland); Institute of Plasma Physics and Laser Microfusion (IFPiLM), 01-497 Warsaw (Poland); Skladnik-Sadowska, E.; Czaus, K.; Kwiatkowski, R.; Zaloga, D. [National Centre for Nuclear Research (NCBJ), 05-400 Otwock (Poland); Paduch, M.; Zielinska, E. [Institute of Plasma Physics and Laser Microfusion (IFPiLM), 01-497 Warsaw (Poland)

    2015-01-15

    The paper concerns fast protons and neutrons from D-D fusion reactions in a Plasma-Focus-1000U facility. Measurements were performed with nuclear-track detectors arranged in “sandwiches” of an Al-foil and two PM-355 detectors separated by a polyethylene-plate. The Al-foil eliminated all primary deuterons, but was penetrable for fast fusion protons. The foil and first PM-355 detector were penetrable for fast neutrons, which were converted into recoil-protons in the polyethylene and recorded in the second PM-355 detector. The “sandwiches” were irradiated by discharges of comparable neutron-yields. Analyses of etched tracks and computer simulations of the fusion-products behavior in the detectors were performed.

  7. Production of a faithful realistic phantom to human head and thermal neutron flux measurement on the brain surface. Cooperative research

    Energy Technology Data Exchange (ETDEWEB)

    Yamamoto, Kazuyoshi; Kumada, Hiroaki; Kishi, Toshiaki; Torii, Yoshiya; Uchiyama, Junzo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Endo, Kiyoshi; Yamamoto, Tetsuya; Matsumura, Akira; Nose, Tadao [Tsukuba Univ., Tsukuba, Ibaraki (Japan)

    2002-12-01

    Thermal neutron flux is determined using the gold wires in current BNCT irradiation, so evaluation of arbitrary points after the irradiation is limited in the quantity of these detectors. In order to make up for the weakness, dose estimation of a patient is simulated by a computational dose calculation supporting system. In another way without computer simulation, a medical irradiation condition can be replicate experimentally using of realistic phantom which was produced from CT images by rapid prototyping technique. This phantom was irradiated at a same JRR-4 neutron beam as clinical irradiation condition of the patient and the thermal neutron distribution on the brain surface was measured in detail. This experimental evaluation technique using a realistic phantom is applicable to in vitro cell irradiation experiments for radiation biological effects as well as in-phantom experiments for dosimetry under the nearly medical irradiation condition of patient. (author)

  8. Production of a faithful realistic phantom to human head and thermal neutron flux measurement on the brain surface. Cooperative research

    CERN Document Server

    Yamamoto, K; Kishi, T; Kumada, H; Matsumura, A; Nose, T; Torii, Y; Uchiyama, J; Yamamoto, T

    2002-01-01

    Thermal neutron flux is determined using the gold wires in current BNCT irradiation, so evaluation of arbitrary points after the irradiation is limited in the quantity of these detectors. In order to make up for the weakness, dose estimation of a patient is simulated by a computational dose calculation supporting system. In another way without computer simulation, a medical irradiation condition can be replicate experimentally using of realistic phantom which was produced from CT images by rapid prototyping technique. This phantom was irradiated at a same JRR-4 neutron beam as clinical irradiation condition of the patient and the thermal neutron distribution on the brain surface was measured in detail. This experimental evaluation technique using a realistic phantom is applicable to in vitro cell irradiation experiments for radiation biological effects as well as in-phantom experiments for dosimetry under the nearly medical irradiation condition of patient.

  9. 防空导弹武控设备实现CBM方法的探讨%Research on the Condition Based Maintenance for Weapon Control Equipment of Air-defense Missile

    Institute of Scientific and Technical Information of China (English)

    曲宏宇; 向哲

    2012-01-01

    针对解决防空导弹武控设备目前维修方式中的诸多问题,基于状态的维修(CBM)方式是有效解决途径之一。分析了对防空导弹武控设备进行CBM时的状态监测、失效模型建立、故障预测和维修决策等关键技术问题,探讨了防空导弹武控设备实现CBM的技术对策。结果表明,CBM具有诸多优点,它的实践应用必将引发武控设备维修技术的根本变革,促进高新技术在防空导弹武控设备维修领域的应用。%The condition based maintenance(CBM) is one of effective maintenance methods for weapon control equipment of air-defense missile.The key techniques is analyzed about inspecting the condition,establishing invalidation modal,forecasting malfunction,maintenance decision-making of CBM that is used for weapon control equipment of air-defense missile,the technique countermeasure of carrying CBM is introduced.The results show CBM is effective,which will result in radical change in maintenance technique of weapon control equipment,and promote using of new techniques in maintenance for weapon control equipment of air-defense missile.

  10. 模糊优化理论的武器-目标分配模型及求解算法%Research on Weapon-target Assignment Model and Algorithm Based on the Fuzzy Optimization Theory

    Institute of Scientific and Technical Information of China (English)

    黄国锐; 李朋辉; 丁俊香; 韩玮

    2013-01-01

    Weapon-target assignment is a typical NP-complete problem, with the incrase in the number of weapons and targets, as well as the existence of the diversity of evaluation criterion for the allocation result, traditional optimzation algorithm such as implicit enumeration method, cutting plane method, branch and bound method is difficult to solve the problem effectively. This paper desctibes the multi-objiective hybrid optimization theory based on the fuzzy optimization method, establishes the optimal weapon-target assignment model of multi-indicator and applies the ant colony algorithm to solve problem, which provides an effective method to solve the complex problem of weapon-target assignment.%武器-目标分配问题是一个典型的NP完全问题,随着武器和目标数量的增多,以及分配结果评价标准多样性的存在,传统的优化求解算法如隐枚举法、割平面法、分支定界法等很难进行有效地求解.介绍一种基于模糊优选技术的多目标混合优化理论,运用该理论建立了多个指标下的最佳武器-目标分配模型,并将蚁群算法应用于对模型的求解,为解决复杂的武器-目标分配问题提供了一种有效方法.

  11. Neutron dosimetry; Dosimetria de neutrons

    Energy Technology Data Exchange (ETDEWEB)

    Fratin, Luciano

    1993-12-31

    A neutron irradiation facility was designed and built in order to establish a procedure for calibrating neutron monitors and dosemeters. A 185 GBq {sup 241} Am Be source of known is used as a reference source. The irradiation facility using this source in the air provides neutron dose rates between 9 nSv s{sup -1} and 0,5 {sup {mu}}Sv s{sup -1}. A calibrated 50 nSv s{sup -1} thermal neutron field is obtained by using a specially designed paraffin block in conjunction with the {sup 241} Am Be source. A Bonner multisphere spectrometer was calibrated, using a procedure based on three methods proposed by international standards. The unfold {sup 241} Am Be neutron spectrum was determined from the Bonner spheres data and resulted in a good agreement with expected values for fluence rate, dose rate and mean energy. A dosimetric system based on the electrochemical etching of CR-39 was developed for personal dosimetry. The dosemeter badge using a (n,{alpha}) converter, the etching chamber and high frequency power supply were designed and built specially for this project. The electrochemical etching (ECE) parameters used were: a 6N KOH solution, 59 deg C, 20 kV{sub pp} cm{sup -1}, 2,0 kHz, 3 hours of ECE for thermal and intermediate neutrons and 6 hours for fast neutrons. The calibration factors for thermal, intermediate and fast neutrons were determined for this personal dosemeter. The sensitivities determined for the developed dosimetric system were (1,46{+-} 0,09) 10{sup 4} tracks cm{sup -2} mSv{sup -1} for thermal neutrons, (9{+-}3) 10{sup 2} tracks cm{sup -2} mSV{sup -1} for intermediate neutrons and (26{+-}4) tracks cm{sup -2} mSv{sup -1} for fast neutrons. The lower and upper limits of detection were respectively 0,002 mSv and 0,6 mSv for thermal neutrons, 0,04 mSv and 8 mSv for intermediate neutrons and 1 mSv and 12 mSv for fast neutrons. In view of the 1990`s ICRP recommendations, it is possible to conclude that the personal dosemeter described in this work is

  12. Characterization of Neutron and Gamma Dose in the Irradiation Cell of Texas A and M University Research Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Vasudevan, Latha; Reece, Warren D. [Nuclear Science Center, Texas A and M University, College Station, Texas (United States); Chirayath, Sunil S. [Nuclear Security Science and Policy Institute, Texas A and M University, College Station, Texas (United States); Aghara, Sukesh [Prairie View A and M University, Prairie View, Texas (United States)

    2011-07-01

    The Monte Carlo N-Particle (MCNP) code was used to develop a three dimensional computational model of the Texas A and M University Nuclear Science Center Reactor (NSCR) operating against the irradiation (dry cell) at steady state thermal power of 1 MW. The geometry of the NSCR core and the dry cell were modeled in detail. NSCR is used for a wide variety of experiments that utilizes the dry cell for neutron as well as gamma irradiation of samples. Information on the neutron and gamma radiation environment inside the dry cell is required to facilitate irradiation of samples. This paper presents the computed neutron flux, neutron and gamma dose rate, and foil reaction rates in the dry cell, obtained through MCNP5 simulations of the NSCR core. The neutron flux was measured using foil activation method and the reaction rates obtained from {sup 197}Au(n,{gamma}){sup 198}Au and {sup 54}Fe(n,p){sup 54}Mn were compared with the model and they showed agreement within {approx} 20%. The gamma dose rate at selected locations inside the dry cell was measured using radiochromic films and the results indicate slightly higher dose rates than predicted from the model. This is because the model calculated only prompt gamma dose rates during reactor operation while the radiochromic films measured gammas from activation products and fission product decayed gammas. The model was also used to calculate the neutron energy spectra for the energy range from 0.001 eV- 20 MeV. (authors)

  13. An algorithm research of ship formotion's cooperatine anti- air weapons distribution optimitation%舰艇编队协同防空武器优化分配算法

    Institute of Scientific and Technical Information of China (English)

    窦强; 马英超; 王海川

    2012-01-01

    In order to improve the ship formation' s cooperative anti-air weapons efficiency, a 0-1 planning model for weapon optimal assignment and GA steps to solve it have been built based on the Principle of handling the most targets in the shortest time. Calculation shows that, the 0-1 planning model and GA steps have strong adaptability and fast convergence rate. The algorithm gives an effective method to solve large scale ship formation' s weapon assignment problems.%为提高舰艇编队协同防空武器的使用效率,基于最短时间内毁伤最多目标的原则,建立了武器优化分配的0-1规划模型,并给出了遗传算法求解该模型的具体步骤.计算表明,0-1规划模型及遗传算法具有适应性强、收敛速度快等优点.算法为解决舰艇编队较大规模武器优化分配问题提供了一种有效的方法.

  14. Research on the Capability Generation of Weapon System-of-Systems Based on Fuzzy Consensus%基于模糊共识的武器装备体系能力生成研究

    Institute of Scientific and Technical Information of China (English)

    黄魏; 梁晓庆; 谭跃进

    2011-01-01

    武器装备体系能力生成是武器装备体系构建与发展的基础,是专家群体研讨并最终形成武器装备体系能力发展的共识过程,专家意见共识的形成是武器装备体系能力生成的核心环节.为便于专家理解并对各种方案进行比较,采用模糊共识的思想,通过建立专家的模糊偏好矩阵,计算专家意见的一致度,在此基础上获得专家意见的模糊共识度.%The capability generation of weapon system-of-systems is foundation of construct and development of weapon system-of-systems. It is the process of expert group discussion then form consensus of capability development. The forming of expert opinion consensus is the significant segment of capability generation of weapon system-of-systems. In order to facilitate the understanding of experts and to compare various options, adopts the idea of fuzzy consensus, through the establishment of the expert's fuzzy preference matrix, the calculation of the same degree of expert opinion, then acquire fuzzy degree of consensus.

  15. 基于不完全信息空战的火力分配建模与应用%Research on Weapon-Target Assignment Modeling and Application Based on Incomplete Information Air Combat

    Institute of Scientific and Technical Information of China (English)

    隋永华; 郭雷; 俞利新; 王海晏

    2012-01-01

    To solve the problem of weapon-target assignment in an incomplete information air combat, the common weapon-target assignment model is analized, the defect of which is pointed out, and an improved weapon-target assignment model is built. The computation method of the key arguments of the model is proposed according to the character of incomplete information air combat. The improved mode can work efficiently based on the limited papameters obtained easily in the condition of incomplete information. Finally,the efficiency of the model is validated through a typical air combat example.%为了解决不完全信息空战中的火力分配问题,分析了常规空战火力分配模型,指出了其中的不足,建立了一种改进的火力分配模型.针对不完全信息空战特点,给出了其中关键参数的确定方法.该改进模型可有效利用战机在不完全信息条件下容易获取的有限参数进行火力分配,具有很强的实用性.最后通过典型应用实例验证了模型的有效性.

  16. Research on Weapon Target Assignment for Surface Warship Formation with Cooperative Engagement Capability%CEC条件下舰艇编队目标武器分配研究

    Institute of Scientific and Technical Information of China (English)

    王玮; 董天忠; 张玉芝

    2009-01-01

    在分析CEC条件下舰艇编队目标武器分配模式的基础上,综合运用MAS理论与方法,建立了舰艇编队目标武器分配MAS模型,即利用Agent描述舰艇编队的各种物理资源或逻辑资源,通过网络及Agent通讯协议将多个Agent连接成一个整体系统,设计了映射实体功能的Agent结构,从而为舰艇编队目标武器分配决策提供了一条新途径.%On the base of analyzing the mode of weapon target assignment for surface warship formation with cooperative engagement capability, a MAS model of the weapon target assignment for warship formation is proposed by means of the MAS theory and method, it is described which includes all kinds of physical or logical resource by the Agent, many agent subsystem is connected into a integrated system through network and communication protocols of the Agent. The Agent structure of a mapping entity functions has been designed, therefore provide a new way for the decision of the weapon target assignment for warship formation.

  17. Research on Evaluation Method about Handing Performance of Man-machine Interface of Weapons%武器装备人机界面操控性评价方法研究

    Institute of Scientific and Technical Information of China (English)

    汪汇川; 解维河; 赵勇

    2013-01-01

    针对武器装备人机界面操控性难以有效评价的问题,提出人机界面操控易用性的评价指标,利用信息距离对易用性进行分析,并建立武器装备人机界面易用性的评估模型,并通过实例进行武器装备易用性评价分析,为武器装备人机界面操控性设计优化及检验标准的制定提供了指导.%For the problem about evaluation of man-machine interface's handing performance of weapons, the ease-to-use performance indicators is maked, the ease-to-use performance is analyzed by the distance of information-state transition, weapons'man-machine interface assessment model is established, the method is demonstrated by the practical example, to provide a reference for the optimization of handing performance of man-machine interface and the development of standards about the handing performance of man-machine interface of weapons.

  18. Neutronic analysis for core conversion (HEU–LEU) of the low power research reactor using the MCNP4C code

    OpenAIRE

    Aldawahra Saadou; Khattab Kassem; Saba Gorge

    2015-01-01

    Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source reactor (MNSR) have been performed using the MCNP4C code. The HEU fuel (UAl4-Al, 90% enriched with Al clad) and LEU (UO2 12.6% enriched with zircaloy-4 alloy clad) cores have been analyzed in this study. The existing HEU core of MNSR was analyzed to validate the neutronic model of reactor, while the LEU core was studied to prove the possibility of fuel conversion of the existing HEU core. The propos...

  19. Toward a nuclear weapons free world?

    Energy Technology Data Exchange (ETDEWEB)

    Maaranen, S.A. [Los Alamos National Lab., NM (United States). Center for International Security Affairs

    1996-09-01

    Doubts about the wisdom of relying on nuclear weapons are as old as nuclear weapons themselves. But despite this questioning, nuclear weapons came to be seen as the indispensable element of American (indeed Western) security during the Cold War. By the 1970s and 1980s, however, discontent was growing about the intense US-Soviet nuclear arms competition, as it failed to provide any enduring improvement in security; rather, it was seen as creating ever greater risks and dangers. Arms control negotiations and limitations, adopted as a means to regulate the technical competition, may also have relieved some of the political pressures and dangers. But the balance of terror, and the fears of it, continued. The Strategic Defense Initiative (SDI) under President Reagan was a very different approach to escaping from the precarious protection of nuclear weapons, in that it sought a way to continue to defend the US and the West, but without the catastrophic risks of mutual deterrence. As such, SDI connoted unhappiness with the precarious nuclear balance and, for many, with nuclear weapons in general. The disappearance of the Warsaw Pact, the disintegration of the Soviet Union, and the sudden end of the Cold War seemed to offer a unique opportunity to fashion a new, more peaceful world order that might allow for fading away of nuclear weapons. Scholars have foreseen two different paths to a nuclear free world. The first is a fundamental improvement in the relationships between states such that nuclear weapons are no longer needed. The second path is through technological development, e.g., missile defenses which could provide effective protection against nuclear attacks. The paper discusses nuclear weapon policy in the US, views of other nuclear states, the future of nuclear weapons, and issues in a less-nuclear world.

  20. Measurement of neutron scattering lengths using neutron interferometry

    Science.gov (United States)

    Shahi, Chandra B.

    This thesis describes the details on building a new Neutron Interferometry and Optics Facility (NIOFa), the measurement of the incoherent neutron scattering length bi of 3He, and the measurement of the coherent neutron scattering length bc of 4He at National Institute of Standards and Technology (NIST) Center for Neutron Research (NCNR). A new monochromatic beamline and facility has been installed at the NCNR devoted to neutron interferometry in the research areas of spin control, spin manipulation, quantum mechanics, quantum information science, spintronics, and material science. This facility is possible in part because of advances in decoherence free subspace interferometer designs that have demonstrated consistent contrast in the presence of vibrational noise; a major environmental constraint that has prevented neutron interferometry from being applied at other neutron facilities. This new facility, NIOFa, is located in the guide hall of the NCNR upstream of the existing Neutron Interferometry and Optics Facility (NIOF) and has several advantages over the NIOF including higher incident flux, better neutron polarization, and increased accessibility. The measurement of the incoherent neutron scattering length bi of 3He was done using a (220) single silicon crystal skew symmetric interferometer. This experiment requires both a polarized beam and a polarized target. We report bi = -2.35 +/- 0.014 (stat.) +/- 0.014 (syst.). This experiment is a revision of the previous experiment which was done in 2008, and partially explains the non-zero phase shift seen in 2008 experiment even if target cell was completely unpolarized. The measurement of the coherent neutron scattering length b c of the 4He was done using a (111) single silicon crystal interferometer. The neutron interferometry and optics facility at NIST had been used previously to determine the coherent scattering lengths for n- 1H, n-2H, and n-3He to less than 1% relative uncertainty. We report bc of the 4He

  1. Reactor neutrons in nuclear astrophysics

    Science.gov (United States)

    Reifarth, René; Glorius, Jan; Göbel, Kathrin; Heftrich, Tanja; Jentschel, Michael; Jurado, Beatriz; Käppeler, Franz; Köster, Ulli; Langer, Christoph; Litvinov, Yuri A.; Weigand, Mario

    2017-09-01

    The huge neutron fluxes offer the possibility to use research reactors to produce isotopes of interest, which can be investigated afterwards. An example is the half-lives of long-lived isotopes like 129I. A direct usage of reactor neutrons in the astrophysical energy regime is only possible, if the corresponding ions are not at rest in the laboratory frame. The combination of an ion storage ring with a reactor and a neutron guide could open the path to direct measurements of neutron-induced cross sections on short-lived radioactive isotopes in the astrophysically interesting energy regime.

  2. Neutron reflectometry

    DEFF Research Database (Denmark)

    Klösgen-Buchkremer, Beate Maria

    2014-01-01

    films or films with magnetic properties. The reason is the peculiar property of neutron light since the mass of a neutron is close to the one of a proton, and since it bears a magnetic moment. The optical properties of matter, when interacting with neutrons, are described by a refractive index......Neutron (and X-ray) reflectometry constitute complementary interfacially sensitive techniques that open access to studying the structure within thin films of both soft and hard condensed matter. Film thickness starts oxide surfaces on bulk substrates, proceeding to (pauci-)molecular layers and up...... to hundreds of nanometers. Thickness resolution for flat surfaces is in the range of few Ǻngstrøm, and as a peculiar benefit, the presence and properties of buried interfaces are accessible. Focus here will be on neutron reflectometry, a technique that is unique in applications involving composite organic...

  3. Weapon container catalog. Volumes 1 & 2

    Energy Technology Data Exchange (ETDEWEB)

    Brown, L.A.; Higuera, M.C.

    1998-02-01

    The Weapon Container Catalog describes H-gear (shipping and storage containers, bomb hand trucks and the ancillary equipment required for loading) used for weapon programs and for special use containers. When completed, the catalog will contain five volumes. Volume 1 for enduring stockpile programs (B53, B61, B83, W62, W76, W78, W80, W84, W87, and W88) and Volume 2, Special Use Containers, are being released. The catalog is intended as a source of information for weapon program engineers and also provides historical information. The catalog also will be published on the SNL Internal Web and will undergo periodic updates.

  4. [New challenges in the biological weapons convention].

    Science.gov (United States)

    Sissonen, Susanna; Raijas, Tiina; Haikala, Olli; Hietala, Heikki; Virri, Markku; Nikkari, Simo

    2012-01-01

    Microbes and their toxins are biological weapons that can cause disease in humans, animals or plants, and which can be used with hostile intent in warfare and terrorism. Biological agents can be used as weapons of mass destruction and therefore, immense human and social and major economical damage can be caused. Rapid development of life sciences and technologies during the recent decades has posed new challenges to the Biological Weapons Convention. The Convention states that the States Parties to the BWC strive to ensure that the Convention remains relevant and effective, despite changes in science, technology or politics.

  5. The Spear: An Effective Weapon Since Antiquity

    OpenAIRE

    Robert E. Dohrenwend

    2012-01-01

    The spear is perhaps man’s oldest weapon, and may even be his oldest tool. Over the hundreds of thousands of years of the weapon’s existence, it evolved from a pointed stick into an efficient hunting missile, and then became the most effective hand-held bladed weapon humans ever devised. The spear and its use is the only martial art originally devised for use against species other than our own, and more than any other weapon, the spear emphasizes the relationship between hunting and warfare. ...

  6. The Importance of Designating Cyberspace Weapon Systems

    Science.gov (United States)

    2013-10-01

    PerspectiveSpace Focus Cyberspace Vulnerability Assessment / Hunter Weapon System The Air Force Cyberspace Vulnerability Assessment ( CVA ) / Hunter  weapon...system can perform defensive sorties worldwide via remote or on-site access. The  CVA /Hunter weapon sys- tem is operated by one active duty unit, the...support all of the mission crews. Developed by the for- mer Air Force Information Operations Center, the  CVA /Hunter  weapon system was fielded to the 688th

  7. Monoamine oxidase A genotype is associated with gang membership and weapon use.

    Science.gov (United States)

    Beaver, Kevin M; DeLisi, Matt; Vaughn, Michael G; Barnes, J C

    2010-01-01

    A functional polymorphism in the promoter region of the monoamine oxidase A (MAOA) gene has been found to be associated with a broad range of antisocial phenotypes, including physical violence. At the same time, it is well known that gang members represent some of the most serious violent offenders. Even so, no research has ever examined the association between MAOA and gang membership. The aim of this study is to examine the association between MAOA and gang membership and between MAOA and weapon use. We examined the effects of MAOA by using a molecular genetic association research design. A nonclinical sample was used in this study. Participants were drawn from the National Longitudinal Study of Adolescent Health (1155 females, 1041 males). The outcome measures of this study are gang membership and weapon use. The low MAOA activity alleles conferred an increased risk of joining a gang and using a weapon in a fight for males but not for females. Moreover, among male gang members, those who used weapons in a fight were more likely to have a low MAOA activity allele when compared with male gang members who do not use weapons in a fight. Male carriers of low MAOA activity alleles are at risk for becoming a gang member and, once a gang member, are at risk for using weapons in a fight. Copyright 2010 Elsevier Inc. All rights reserved.

  8. Neutron Nucleic Acid Crystallography.

    Science.gov (United States)

    Chatake, Toshiyuki

    2016-01-01

    The hydration shells surrounding nucleic acids and hydrogen-bonding networks involving water molecules and nucleic acids are essential interactions for the structural stability and function of nucleic acids. Water molecules in the hydration shells influence various conformations of DNA and RNA by specific hydrogen-bonding networks, which often contribute to the chemical reactivity and molecular recognition of nucleic acids. However, X-ray crystallography could not provide a complete description of structural information with respect to hydrogen bonds. Indeed, X-ray crystallography is a powerful tool for determining the locations of water molecules, i.e., the location of the oxygen atom of H2O; however, it is very difficult to determine the orientation of the water molecules, i.e., the orientation of the two hydrogen atoms of H2O, because X-ray scattering from the hydrogen atom is very small.Neutron crystallography is a specialized tool for determining the positions of hydrogen atoms. Neutrons are not diffracted by electrons, but are diffracted by atomic nuclei; accordingly, neutron scattering lengths of hydrogen and its isotopes are comparable to those of non-hydrogen atoms. Therefore, neutron crystallography can determine both of the locations and orientations of water molecules. This chapter describes the current status of neutron nucleic acid crystallographic research as well as the basic principles of neutron diffraction experiments performed on nucleic acid crystals: materials, crystallization, diffraction experiments, and structure determination.

  9. Ukraine experimental neutron source facility.

    Energy Technology Data Exchange (ETDEWEB)

    Gohar, Y.; Bolshinsky, I.; Nekludov, I.; Karnaukhov, I. (Nuclear Engineering Division); (INL); (Kharkov Institute of Physics and Technology)

    2008-01-01

    Kharkov Institute of Physics and Technology (KIPT) of Ukraine has a plan to construct an experimental neutron source facility. The facility has been developed for producing medical isotopes, training young nuclear professionals, supporting the Ukraine nuclear industry, providing capability for performing reactor physics, material research, and basic science experiments. Argonne National Laboratory (ANL) of USA is collaborating with KIPT on developing this facility. A driven subcritical assembly utilizing the KIPT electron accelerator with a target assembly is used to generate the neutron source. The target assembly utilizes tungsten or uranium for neutron production through photonuclear reactions with 100-KW of electron beam power. The neutron source intensity, spectrum, and spatial distribution have been studied to maximize the neutron yield and satisfy different engineering requirements. The subcritical assembly is designed to obtain the highest possible neutron flux intensity with a subcriticality of 0.98. Low enrichment uranium is used for the fuel material because it enhances the neutron source performance. Safety, reliability, and environmental considerations are included in the facility conceptual design. Horizontal neutron channels are incorporated for performing basic research including cold neutron source. This paper describes the conceptual design and summarizes some of the related analyses.

  10. 48 CFR 217.173 - Multiyear contracts for weapon systems.

    Science.gov (United States)

    2010-10-01

    ... weapon systems. 217.173 Section 217.173 Federal Acquisition Regulations System DEFENSE ACQUISITION... Mulityear Contracting 217.173 Multiyear contracts for weapon systems. As authorized by 10 U.S.C. 2306b(h... contract for— (a) A weapon system and associated items, services, and logistics support for a weapon system...

  11. Application of a Dynamic Programming Algorithm for Weapon Target Assignment

    Science.gov (United States)

    2016-02-01

    UNCLASSIFIED UNCLASSIFIED Application of a Dynamic Programming Algorithm for Weapon Target Assignment Lloyd Hammond Weapons and...Combat Systems Division Defence Science and Technology Group DST Group-TR-3221 ABSTRACT Threat evaluation and weapon assignment...dynamic programming algorithm for Weapon Target Assignment which, after more rigorous testing, could be used as a concept demonstrator and as an auxiliary

  12. 36 CFR 1002.4 - Weapons, traps and nets.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Weapons, traps and nets. 1002... AND RECREATION § 1002.4 Weapons, traps and nets. (a)(1) Except as otherwise provided in this section, the following are prohibited: (i) Possessing a weapon, trap or net. (ii) Carrying a weapon, trap or...

  13. 43 CFR 15.11 - Explosives and dangerous weapons.

    Science.gov (United States)

    2010-10-01

    ... 43 Public Lands: Interior 1 2010-10-01 2010-10-01 false Explosives and dangerous weapons. 15.11... § 15.11 Explosives and dangerous weapons. No person shall carry, use or possess within the Preserve... other kind of weapon potentially harmful to the reef structure. The use of such weapons from beyond the...

  14. A different kind of weapon focus: simulated training with ballistic weapons reduces change blindness.

    Science.gov (United States)

    Taylor, J Eric T; Witt, Jessica K; Pratt, Jay

    2017-01-01

    Attentional allocation is flexibly altered by action-related priorities. Given that tools - and specifically weapons - can affect attentional allocation, we asked whether training with a weapon or holding a weapon during search would affect change detection. In three experiments, participants searched for changes to agents, shootable objects, or environments in the popular flicker paradigm. Participants trained with a simulated weapon or watched a video from the same training perspective and then searched for changes while holding a weapon or a control object. Results show an effect of training, highlighting the importance of sensorimotor experience for the action-relevant allocation of attention, and a possible interaction between training and the object held during search. Simulated training with ballistic weapons reduces change blindness. This result has implications for the interaction between tool use and attentional allocation.

  15. Physics of Neutron Star Crusts

    Directory of Open Access Journals (Sweden)

    Chamel Nicolas

    2008-12-01

    Full Text Available The physics of neutron star crusts is vast, involving many different research fields, from nuclear and condensed matter physics to general relativity. This review summarizes the progress, which has been achieved over the last few years, in modeling neutron star crusts, both at the microscopic and macroscopic levels. The confrontation of these theoretical models with observations is also briefly discussed.

  16. Basic concept for an accelerator-driven subcritical system to be used as a long-pulse neutron source for Condensed Matter research

    Energy Technology Data Exchange (ETDEWEB)

    Vivanco, R., E-mail: raul.vivanco.sanchez@gmail.com [ESS-BILBAO, Parque Tecnológico Bizkaia, Laida Bidea, Edificio 207 B Planta Baja, 48160 Derio (Spain); Instituto de Fusión Nuclear - UPM, ETS Ingenieros Industriales, C/ José Gutiérrez Abascal, 2, 28006 Madrid Spain (Spain); Ghiglino, A.; Vicente, J.P. de; Sordo, F.; Terrón, S.; Magán, M. [ESS-BILBAO, Parque Tecnológico Bizkaia, Laida Bidea, Edificio 207 B Planta Baja, 48160 Derio (Spain); Instituto de Fusión Nuclear - UPM, ETS Ingenieros Industriales, C/ José Gutiérrez Abascal, 2, 28006 Madrid Spain (Spain); Perlado, J.M. [Instituto de Fusión Nuclear - UPM, ETS Ingenieros Industriales, C/ José Gutiérrez Abascal, 2, 28006 Madrid Spain (Spain); Bermejo, F.J. [Instituto de Estructura de la Materia, IEM-CSIC, Consejo Superior de Investigaciones Científicas, Serrano 123, 28006 Madrid (Spain)

    2014-12-11

    A model for an accelerator-driven subcritical system to be operated as a source of cold neutrons for Condensed Matter research is developed at the conceptual level. Its baseline layout relies upon proven accelerator, spalattion target and fuel array technologies, and consists in a proton accelerator able to deliver some 67.5 mA of proton beam with kinetic energy 0.6 GeV, a pulse length of 2.86 ms, and repetition rate of 14 Hz. The particle beam hits a target of conventional design that is surrounded by a multiplicative core made of fissile/fertile material, composed by a subcritical array of fuel bars made of aluminium Cermet cooled by light water poisoned with boric acid. Relatively low enriched uranium is chosen as fissile material. An optimisation of several parameters is carried out, using as components of the objective function several characteristics pertaining the cold neutron pulse. The results show that the optimal device will deliver up to 80% of the cold neutron flux expected for some of the ongoing projects using a significantly lower proton beam power than that managed in such projects. The total power developed within the core rises up to 22.8 MW, and the criticality range shifts to a final k{sub eff} value of around 0.9 after the 50 days cycle.

  17. Neutronic simulation of a research reactor core of (232Th, 235U)O2 fuel using MCNPX2.6 code

    Indian Academy of Sciences (India)

    Seyed Amir Hossein Feghhi; Marzieh Rezazadeh; Yachine Kadi; Claudio Tenreiro; Morteza Aref; Zohreh Gholamzadeh

    2013-01-01

    The small reactor design for the remote and less developed areas of the user countries should have simple features in view of the lack of infra-structure and resources. Many researchers consider long core life with no on-site refuelling activity as a primary feature for the small reactor design. Long core life can be achieved by enhancing internal conversion rate of fertile to fissile materials. For that purpose, thorium cycle can be adopted because a high fissile production rate of 233U converted from 232Th can be expected in the thermal energy region. A simple nuclear reactor core arranged 19 assemblies in hexagonal structure, using thorium-based fuel and heavy water as coolant and moderator was simulated using MCNPX2.6 code, aiming an optimized critical assembly. Optimized reflector thickness and gap between assemblies were determined to achieve minimum neutron leakage and void reactivity. The result was a more compact core, where assemblies were designed having 19-fuel pins in 1.25 pitch-to-diameter ratio. Optimum reflector thickness of 15 cm resulted in minimal neutron leakage in view of economic limitations. A 0.5 cm gap between assembles achieved more safety and 2.2% enrichment requirements. The present feasibility study suggests a thermal core of acceptable neutronic parameters to achieve a simple and safe core.

  18. Neutronic Analyses for HEU to LEU fuel conversion of the Massachusetts Institute of Technology.

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, E. H.; Newton, T. H.; Bergeron, A.; Horelik, N.; Stevens, J. G (Nuclear Engineering Division); ( NS)

    2011-03-02

    The Massachusetts Institute of Technology (MIT) reactor (MITR-II), based in Cambridge, Massachusetts, is a research reactor designed primarily for experiments using neutron beam and in-core irradiation facilities. It delivers a neutron flux comparable to current LWR power reactors in a compact 6 MW core using Highly Enriched Uranium (HEU) fuel. In the framework of its non-proliferation policies, the international community presently aims to minimize the amount of nuclear material available that could be used for nuclear weapons. In this geopolitical context, most research and test reactors both domestic and international have started a program of conversion to the use of Low Enriched Uranium (LEU) fuel. A new type of LEU fuel based on a mixture of uranium and molybdenum (UMo) is expected to allow the conversion of compact high performance reactors like the MITR-II. This report presents the results of steady state neutronic safety analyses for conversion of MITR-II from the use of HEU fuel to the use of U-Mo LEU fuel. The objective of this work was to demonstrate that the safety analyses meet current requirements for an LEU core replacement of MITR-II.

  19. Studies of fission fragment properties at the Los Alamos Neutron Science Center (LANSCE)

    Science.gov (United States)

    Tovesson, Fredrik; Mayorov, Dmitriy; Duke, Dana; Manning, Brett; Geppert-Kleinrath, Verena

    2017-09-01

    Nuclear data related to the fission process are needed for a wide variety of research areas, including fundamental science, nuclear energy and non-proliferation. While some of the relevant data have been measured to the required accuracies there are still many aspects of fission that need further investigation. One such aspect is how Total Kinetic Energy (TKE), fragment yields, angular distributions and other fission observables depend on excitation energy of the fissioning system. Another question is the correlation between mass, charge and energy of fission fragments. At the Los Alamos Neutron Science Center (LANSCE) we are studying neutron-induced fission at incident energies from thermal up to hundreds of MeV using the Lujan Center and Weapons Neutron Research (WNR) facilities. Advanced instruments such as SPIDER (time-of-flight and kinetic energy spectrometer), the NIFFTE Time Projection Chamber (TPC), and Frisch grid Ionization Chambers (FGIC) are used to investigate the properties of fission fragments, and some important results for the major actinides have been obtained.

  20. General Design for CARR Neutron Guide System

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    A neutron guide system has been designed and partly installed at the China Advanced Research Reactor (CARR) to transport cold neutrons from the cold neutron source (CNS) to several instruments,which are situated in a separate guide hall of 30 m×60 m.

  1. Development of neutron optical components at ILL

    CERN Document Server

    Courtois, P; Humblot, H; Alianelli, L; Pfeiffer, F O

    2002-01-01

    The neutron optics laboratory at ILL carries out an innovative research program in various fields of neutron optics with the aim of developing new and improved tools for neutron instrumentation. An overview of some recent highlights is presented, indicating the breadth of the potential applications. (orig.)

  2. Investigation of neutronic and safety parameters variation in 5 MW research reactor due to U{sub 3}O{sub 8}Al fuel conversion to ThO{sub 2} + U{sub 3}O{sub 8}Al

    Energy Technology Data Exchange (ETDEWEB)

    Gholamzadeh, Zohreh; Alipoor, Zahra; Mirvakili, Seyed Mohammad [Nuclear Science and Technology Research Institute, Tehran (Iran, Islamic Republic of). Reactor Research School; Feghhi, Seyed Amir Hossein [Shahid Beheshti Univ., Tehran (Iran, Islamic Republic of). Dept. of Radiation Application; Vahedi, M.; Bagheri, H. [Univ. of Science and Technology, Tehran (Iran, Islamic Republic of). Energy Dept.; Tenreiro, Claudio [Talca Univ. (Chile). Energy Dept.

    2017-05-15

    Thorium-based fuels could comprise several advantages and are being investigated as a potentially competitive option with uranium-based fuels for research or power reactors. The present study investigates computationally the application of two different thorium-based fuels in a research reactor. Void and temperature reactivity coefficients, safety factor, power peaking factor, neutron generation time, effective delayed neutron fraction and {sup 135}Xe worth parameter were investigated for the fuel conversions. The results showed both the investigated fuels would not significantly disturb neutronic and safety parameters of the modeled core in comparison with its routine fuel loading. However, 235-enriched thorium based fuel concluded in noticeably reduction of High Level Waste (HLW) but 233-enriched type could be taken in attention because of its longer fuel cycle (∝15 %) and integrated neutron flux (∝23 %).

  3. Controlling Weapons-Grade Fissile Material

    Science.gov (United States)

    Rotblat, J.

    1977-01-01

    Discusses the problems of controlling weapons-grade fissionable material. Projections of the growth of fission nuclear reactors indicates sufficient materials will be available to construct 300,000 atomic bombs each containing 10 kilograms of plutonium by 1990. (SL)

  4. Weapons dismantlement issues in independent Ukraine

    Energy Technology Data Exchange (ETDEWEB)

    Zack, N.R. [Los Alamos National Lab., NM (United States); Kirk, E.J. [American Association for the Advancement of Science, Washington, DC (United States)

    1994-07-01

    The American Association for the Advancement of Science sponsored a seminar during September 1993, in Kiev, Ukraine, entitled ``Toward a Nuclear Free Future -- Barriers and Problems.`` It brought together Ukrainians, Belarusians, and Americans to discuss the legal, political, safeguards and security, economic, and technical dimensions of nuclear weapons dismantlement and destruction. US representatives initiated discussions on legal and treaty requirements and constraints, safeguards and security issues surrounding dismantlement, storage and disposition of nuclear materials, warhead transportation, and economic considerations. Ukrainians gave presentations on arguments for and against the Ukraine keeping nuclear weapons, Ukrainian Parliament non-approval of START I, alternative strategies for dismantling silos and launchers, and economic and security implications of nuclear weapons removal from the Ukraine. Participants from Belarus discussed proliferation and control regime issues, This paper will highlight and detail the issues, concerns, and possible impacts of the Ukraine`s dismantlement of its nuclear weapons.

  5. Computational Challenges in Nuclear Weapons Simulation

    Energy Technology Data Exchange (ETDEWEB)

    McMillain, C F; Adams, T F; McCoy, M G; Christensen, R B; Pudliner, B S; Zika, M R; Brantley, P S; Vetter, J S; May, J M

    2003-08-29

    After a decade of experience, the Stockpile Stewardship Program continues to ensure the safety, security and reliability of the nation's nuclear weapons. The Advanced Simulation and Computing (ASCI) program was established to provide leading edge, high-end simulation capabilities needed to meet the program's assessment and certification requirements. The great challenge of this program lies in developing the tools and resources necessary for the complex, highly coupled, multi-physics calculations required to simulate nuclear weapons. This paper describes the hardware and software environment we have applied to fulfill our nuclear weapons responsibilities. It also presents the characteristics of our algorithms and codes, especially as they relate to supercomputing resource capabilities and requirements. It then addresses impediments to the development and application of nuclear weapon simulation software and hardware and concludes with a summary of observations and recommendations on an approach for working with industry and government agencies to address these impediments.

  6. Europium-155 in Debris from Nuclear Weapons

    DEFF Research Database (Denmark)

    Aarkrog, Asker; Lippert, Jørgen Emil

    1967-01-01

    The lithium-drifted germanium detector enables determination of europium-155 on a routine basis in environmental samples contaminated with debris from nuclear weapons. From measurements of europium-155, cesium-144, and strontium-90 in air filters collected between 1961 and 1966, the yield...... of europium-155 from weapons was estimated at 1400 atoms per 10$^{6}$ fissions, which is close to the yield of europium-155 from fast fission of uranium-238....

  7. Correlates of weapon carrying among high school students in the United States

    Science.gov (United States)

    Muula, Adamson S; Rudatsikira, Emmanuel; Siziya, Seter

    2008-01-01

    Background Deaths and injuries arising from interpersonal violence among adolescents are major public health concerns in the United States. The bearing of weapons among adolescents is a critical factor in many of these deaths and injuries. Methods A secondary analysis of the 2005 United States Youth Risk Behavior Surveillance System Survey data was carried out to examine the variables associated with self-reported history of weapon carrying on school property among high school students. We used logistic regression analysis to assess the associations. Results Of the 13,707 respondents who participated in the survey, 10.2% of males and 2.6% of females reported carrying a weapon on school property. In multivariate logistic regression analysis, males were more likely to report having carried a weapon than females (odds ratio (OR) = 5.58; 95% confidence interval (CI) [4.23, 7.62]). Self-reported race/ethnicity was also associated with weapon carrying. Other variables positively associated with weapon carrying at school were substance use (OR = 1.77; 95% CI [1.16, 2.68]), depression (OR = 1.44; 95% CI [1.10, 1.89]), suicidal ideation (OR = 1.64; 95% CI [1.23, 2.19]), having had property stolen or deliberately damaged at school (OR = 1.55; 95% CI [1.21, 1.98]), having been raped (OR = 1.70; 95% CI [1.22, 2.37]), having been threatened or injured with a weapon on school property (OR = 2.19; 95% CI [1.63, 2.95]), and having engaged in physical fighting (OR = 2.02; 95% CI [1.56, 2.63]). Conclusion This research identifies factors that are associated with weapon bearing among adolescents in the United States. These factors may be important in the design of interventions aimed at improving school safety and adolescent health. PMID:18605995

  8. Development of fast neutron pinhole camera using nuclear emulsion for neutron emission profile measurement in KSTAR

    Science.gov (United States)

    Izumi, Y.; Tomita, H.; Nakayama, Y.; Hayashi, S.; Morishima, K.; Isobe, M.; Cheon, M. S.; Ogawa, K.; Nishitani, T.; Naka, T.; Nakano, T.; Nakamura, M.; Iguchi, T.

    2016-11-01

    We have developed a compact fast neutron camera based on a stack of nuclear emulsion plates and a pinhole collimator. The camera was installed at J-port of Korea superconducting tokamak advanced research at National Fusion Research Institute, Republic of Korea. Fast neutron images agreed better with calculated ones based on Monte Carlo neutron simulation using the uniform distribution of Deuterium-Deuterium (DD) neutron source in a torus of 40 cm radius.

  9. ENVIRONMENTAL CONTAMINATION FROM WEAPON TESTS

    Energy Technology Data Exchange (ETDEWEB)

    none

    1958-10-01

    The program of the Atomic Energy Commission on environmental contamination from weapons tests is designed for the overall evaluation of the hazard to humans from test operations. It is limited to studies of the deposition of activity at long range rather than the problems associated with immediate, close-in fallout. The program has largely been a study of Sr{sup 90}, since considerations based on experience and measurement indicate that it is the isotope of greatest potential hazard. Data are presented pertinent to the monitoring of long-range fallout, particularly Sr{sup 90} and Cs{sup 137}. Values are tabulated for the fallout deposition, air concentrations, water concentrations, and the amounts in foods and human bone. In addition, results are given for some experimental investigations. The report of these results is not interpretative although certain papers that do attempt to interpret the present situation with respect to Sr{sup 90} in particular are reprinted. Bibliographies are presented covering the period since the 1957 hearings before the Joint Committee on Atomic Energy concerning the nature of radioactive fallout and its effects on man. A document list of submissions to the United Nations Scientific Committee on the Effects of Atomic Radiation is given to illustrate the work done in other countries. Several papers on the subject, which have not been generally available, are reprinted.

  10. Research on Reliability Optimization of Antiaircraft Weapon System Based on Heuristic Algorithm%启发式算法的防空武器系统可靠性优化

    Institute of Scientific and Technical Information of China (English)

    郭强; 蒋里强; 高建军

    2013-01-01

    针对复杂武器系统可靠性分配最优化问题,以系统的可靠度最大为目标函数,综合考虑系统的费用、质量等约束条件,建立了武器系统的可靠性冗余分配最优化模型,提出了基于启发式方法的求解算法,通过改进各级子系统的可靠性从而使总的系统可靠性最大.算法设计比较简便,易于编程实现.通过对防空武器系统的可靠性分配优化问题进行实例分析,结果表明算法是有效、实用的.为大型复杂武器系统的可靠性设计和优化研究提供了科学有效的方法.%Aiming at the reliability redundancy optimization allotment of the complicated weapon system, using the biggest reliability as the target value, synthesize expenses, quality .etc. to control as condition, the model optimization about the reliability redundancy optimization allotment of the weapon system is builded up; put forward the heuristic algorithm solving calculated way according to opposite increase quantity through. Tthe reliability that passes the improvement all levels subsystem makes the total system reliability biggest, carrying on a solid example analysis to the reliability redundancy optimization allotment of the antiaircraft weapon system.

  11. Development of a database for prompt gamma-ray neutron activation analysis: Summary report of the third research coordination meeting

    Energy Technology Data Exchange (ETDEWEB)

    Lindstrom, Richard M.; Firestone, Richard B.; Pavi, ???

    2003-04-01

    The main discussions and conclusions from the Third Co-ordination Meeting on the Development of a Database for Prompt Gamma-ray Neutron Activation Analysis are summarized in this report. All results were reviewed in detail, and the final version of the TECDOC and the corresponding software were agreed upon and approved for preparation. Actions were formulated with the aim of completing the final version of the TECDOC and associated software by May 2003.

  12. Modern weapons and military equipment for issue no. 3-2015

    OpenAIRE

    ЙЕВТИЧ МИЛОШ М.

    2015-01-01

    Optimal features for concealed carry weapons. The specificity of jobs and tasks that require concealed carrying of weapons by officials require specific criteria when choosing personal weapons specialist.

  13. MODERN WEAPONS AND MILITARY EQUIPMENT FOR ISSUE NO. 3-2015

    OpenAIRE

    2015-01-01

    Optimal features for concealed carry weapons. The specificity of jobs and tasks that require concealed carrying of weapons by officials require specific criteria when choosing personal weapons specialist.

  14. Color image fusion for concealed weapon detection

    Science.gov (United States)

    Toet, Alexander

    2003-09-01

    Recent advances in passive and active imaging sensor technology offer the potential to detect weapons that are concealed underneath a person's clothing or carried along in bags. Although the concealed weapons can sometimes easily be detected, it can be difficult to perceive their context, due to the non-literal nature of these images. Especially for dynamic crowd surveillance purposes it may be impossible to rapidly asses with certainty which individual in the crowd is the one carrying the observed weapon. Sensor fusion is an enabling technology that may be used to solve this problem. Through fusion the signal of the sensor that depicts the weapon can be displayed in the context provided by a sensor of a different modality. We propose an image fusion scheme in which non-literal imagery can be fused with standard color images such that the result clearly displays the observed weapons in the context of the original color image. The procedure is such that the relevant contrast details from the non-literal image are transferred to the color image without altering the original color distribution of this image. The result is a natural looking color image that fluently combines all details from both input sources. When an observer who performs a dynamic crowd surveillance task, detects a weapon in the scene, he will also be able to quickly determine which person in the crowd is actually carrying the observed weapon (e.g. "the man with the red T-shirt and blue jeans"). The method is illustrated by the fusion of thermal 8-12 μm imagery with standard RGB color images.

  15. The world’s first pelletized cold neutron moderator at a neutron scattering facility

    Energy Technology Data Exchange (ETDEWEB)

    Ananiev, V.; Belyakov, A.; Bulavin, M.; Kulagin, E.; Kulikov, S.; Mukhin, K.; Petukhova, T.; Sirotin, A.; Shabalin, D.; Shabalin, E.; Shirokov, V.; Verhoglyadov, A., E-mail: verhoglyadov_al@mail.ru

    2014-02-01

    In July 10, 2012 cold neutrons were generated for the first time with the unique pelletized cold neutron moderator CM-202 at the IBR-2M reactor. This new moderator system uses small spherical beads of a solid mixture of aromatic hydrocarbons (benzene derivatives) as the moderating material. Aromatic hydrocarbons are known as the most radiation-resistant hydrogenous substances and have properties to moderate slow neutrons effectively. Since the new moderator was put into routine operation in September 2013, the IBR-2 research reactor of the Frank Laboratory of Neutron Physics has consolidated its position among the world’s leading pulsed neutron sources for investigation of matter with neutron scattering methods.

  16. Neutron counting with cameras

    Energy Technology Data Exchange (ETDEWEB)

    Van Esch, Patrick; Crisanti, Marta; Mutti, Paolo [Institut Laue Langevin, Grenoble (France)

    2015-07-01

    A research project is presented in which we aim at counting individual neutrons with CCD-like cameras. We explore theoretically a technique that allows us to use imaging detectors as counting detectors at lower counting rates, and transits smoothly to continuous imaging at higher counting rates. As such, the hope is to combine the good background rejection properties of standard neutron counting detectors with the absence of dead time of integrating neutron imaging cameras as well as their very good spatial resolution. Compared to Xray detection, the essence of thermal neutron detection is the nuclear conversion reaction. The released energies involved are of the order of a few MeV, while X-ray detection releases energies of the order of the photon energy, which is in the 10 KeV range. Thanks to advances in camera technology which have resulted in increased quantum efficiency, lower noise, as well as increased frame rate up to 100 fps for CMOS-type cameras, this more than 100-fold higher available detection energy implies that the individual neutron detection light signal can be significantly above the noise level, as such allowing for discrimination and individual counting, which is hard to achieve with X-rays. The time scale of CMOS-type cameras doesn't allow one to consider time-of-flight measurements, but kinetic experiments in the 10 ms range are possible. The theory is next confronted to the first experimental results. (authors)

  17. Neutron Star News and Puzzles

    CERN Document Server

    Prakash, Madappa

    2014-01-01

    Gerry Brown has had the most influence on my career in Physics, and my life after graduate studies. In this article, I give a brief account of some of the many ways in which Gerry shaped my research. Recent and on-going research on neutron stars in which the group built from scratch by Gerry at Stony Brook has made significant strides are reviewed. Selected puzzles about neutron stars that remain to be solved are noted.

  18. Neutron star news and puzzles

    Science.gov (United States)

    Prakash, Madappa

    2014-08-01

    Gerry Brown has had the most influence on my career in Physics, and my life after graduate studies. This article gives a brief account of some of the many ways in which Gerry shaped my research. Focus is placed on the significant strides on neutron star research made by the group at Stony Brook, which Gerry built from scratch. Selected puzzles about neutron stars that remain to be solved are noted.

  19. Advanced Neutron Source (ANS) Project

    Science.gov (United States)

    Campbell, J. H.

    1992-01-01

    This report discusses the following about the Advanced Neutron Source: Project Management; Research and Development; Fuel Development; Corrosion Loop Tests and Analyses; Thermal-Hydraulic Loop Tests; Reactor Control and Shutdown Concepts; Critical and Subcritical Experiments; Material Data, Structural Tests, and Analysis; Cold-Source Development; Beam Tube, Guide, and Instrument Development; Hot-Source Development; Neutron Transport and Shielding; I & C Research and Development; Design; and Safety.

  20. Proliferation concerns in the Russian closed nuclear weapons complex cities : a study of regional migration behavior.

    Energy Technology Data Exchange (ETDEWEB)

    Flores, Kristen Lee

    2004-07-01

    The collapse of the Soviet Union in 1991 left the legacy of the USSR weapons complex with an estimated 50 nuclear, chemical, and biological weapons cities containing facilities responsible for research, production, maintenance, and destruction of the weapons stockpile. The Russian Federation acquired ten such previously secret, closed nuclear weapons complex cities. Unfortunately, a lack of government funding to support these facilities resulted in non-payment of salaries to employees and even plant closures, which led to an international fear of weapons material and knowledge proliferation. This dissertation analyzes migration in 33 regions of the Russian Federation, six of which contain the ten closed nuclear weapons complex cities. This study finds that the presence of a closed nuclear city does not significantly influence migration. However, the factors that do influence migration are statistically different in regions containing closed nuclear cities compared to regions without closed nuclear cities. Further, these results show that the net rate of migration has changed across the years since the break up of the Soviet Union, and that the push and pull factors for migration have changed across time. Specifically, personal and residential factors had a significant impact on migration immediately following the collapse of the Soviet Union, but economic infrastructure and societal factors became significant in later years. Two significant policy conclusions are derived from this research. First, higher levels of income are found to increase outmigration from regions, implying that programs designed to prevent migration by increasing incomes for closed city residents may be counter-productive. Second, this study finds that programs designed to increase capital and build infrastructure in the new Russian Federation will be more effective for employing scientists and engineers from the weapons complex, and consequently reduce the potential for emigration of

  1. Calculating and measuring thermal neutrons exiting from neutron diffractometers collimators

    CERN Document Server

    Tafazolee, K

    2000-01-01

    process, effectiveness of them are studied for the enhancement of the available system. Final conclusion from the simulation process, indicates that the heavy water with the thickness of 50 to 60 cm. is the best moderator for gaining the better thermal neutrons flux for enhancement of P.N.D. in the T.R.R. Powder Neutron Diffractometer y (P.N.D.) is relatively good and practical way for identification of the 3 dimensional construction of materials. In order to exploit the capabilities of this method, in one of the neutron beam of the Tehran Research Reactor (T.R.R.), a collimator embedded inside the concrete wall, direct the neutrons produced in the core reactor towards a monochromator e. Neutrons having been monochromated by 2 nd collimator are then directed towards the sample. Then the pattern of diffracted neutrons from the sample are studied. In order to make the best out of it, neutrons coming to sit on the sample must be of the thermal type. That means the number/amount of thermal neutrons flux in compar...

  2. Neutron protein crystallography in JAERI

    Indian Academy of Sciences (India)

    I Tanaka

    2004-07-01

    Neutron diffraction provides an experimental method of directly locating hydrogen atoms in proteins. After developing an original neutron detector (neutron imaging plate) and a novel practical neutron monochromator (elastically bent perfect Si monochromator), BIX-type diffractometers which were equipped with these tools were e±ciently constructed at JRR-3 in Japan Atomic Energy Research Institute (JAERI), Japan and they have finished many protein crystallographic measurements and interesting results have come one after another. At the same time a method of growing large protein single crystals and a database of hydrogen and hydration have also been developed. In the near future, a pulsed neutron diffractometer for biological macromolecules has been proposed at J-PARC in JAERI.

  3. Neutron Repulsion

    CERN Document Server

    Manuel, Oliver K

    2011-01-01

    Earth is connected gravitationally, magnetically and electrically to its heat source - a neutron star that is obscured from view by waste products in the photosphere. Neutron repulsion is like the hot filament in an incandescent light bulb. Excited neutrons are emitted from the solar core and decay into hydrogen that glows in the photosphere like a frosted light bulb. Neutron repulsion was recognized in nuclear rest mass data in 2000 as the overlooked source of energy, the keystone of an arch that locked together these puzzling space-age observations: 1.) Excess 136Xe accompanied primordial helium in the stellar debris that formed the solar system (Fig. 1); 2.) The Sun formed on the supernova core (Fig. 2); 3.) Waste products from the core pass through an iron-rich mantle, selectively carrying lighter elements and lighter isotopes of each element into the photosphere (Figs. 3-4); and 4.) Neutron repulsion powers the Sun and sustains life (Figs. 5-7). Together these findings offer a framework for understanding...

  4. German neutron scattering conference. Programme and abstracts

    Energy Technology Data Exchange (ETDEWEB)

    Brueckel, Thomas (ed.)

    2012-07-01

    The German Neutron Scattering Conference 2012 - Deutsche Neutronenstreutagung DN 2012 offers a forum for the presentation and critical discussion of recent results obtained with neutron scattering and complementary techniques. The meeting is organized on behalf of the German Committee for Research with Neutrons - Komitee Forschung mit Neutronen KFN - by the Juelich Centre for Neutron Science JCNS of Forschungszentrum Juelich GmbH. In between the large European and international neutron scattering conferences ECNS (2011 in Prague) and ICNS (2013 in Edinburgh), it offers the vibrant German and international neutron community an opportunity to debate topical issues in a stimulating atmosphere. Originating from ''BMBF Verbundtreffen'' - meetings for projects funded by the German Federal Ministry of Education and Research - this conference series has a strong tradition of providing a forum for the discussion of collaborative research projects and future developments in the field of research with neutrons in general. Neutron scattering, by its very nature, is used as a powerful probe in many different disciplines and areas, from particle and condensed matter physics through to chemistry, biology, materials sciences, engineering sciences, right up to geology and cultural heritage; the German Neutron Scattering Conference thus provides a unique chance for exploring interdisciplinary research opportunities. It also serves as a showcase for recent method and instrument developments and to inform users of new advances at neutron facilities.

  5. Status Summary of 3He and Neutron Detection Alternatives for Homeland Security

    Energy Technology Data Exchange (ETDEWEB)

    Kouzes, Richard T.; Ely, James H.

    2010-04-28

    This is a short summary whitepaper on results of our alternatives work: Neutron detection is an important aspect of interdiction of radiological threats for homeland security purposes since plutonium, a material used for nuclear weapons, is a significant source of fission neutrons [Kouzes 2005]. Because of the imminent shortage of 3He, which is used in the most commonly deployed neutron detectors, a replacement technology for neutron detection is required for most detection systems in the very near future [Kouzes 2009a]. For homeland security applications, neutron false alarms from a detector can result in significant impact. This puts a strong requirement on any neutron detection technology not to generate false neutron counts in the presence of a large gamma ray-only source [Kouzes et al. 2008].

  6. Studies on application of neutron activation analysis -Applied research on air pollution monitoring and development of analytical method of environmental samples

    Energy Technology Data Exchange (ETDEWEB)

    Chung, Yong Sam; Moon, Jong Hwa; Chung, Young Ju; Jeong, Eui Sik; Lee, Sang Mi; Kang, Sang Hun; Cho, Seung Yeon; Kwon, Young Sik; Chung, Sang Wuk; Lee, Kyu Sung; Chun, Ki Hong; Kim, Nak Bae; Lee, Kil Yong; Yoon, Yoon Yeol; Chun, Sang Ki

    1997-09-01

    This research report is written for results of applied research on air pollution monitoring using instrumental neutron activation analysis. For identification and standardization of analytical method, 24 environmental samples are analyzed quantitatively, and accuracy and precision of this method are measured. Using airborne particulate matter and biomonitor chosen as environmental indicators, trace elemental concentrations of sample collected at urban and rural site monthly are determined ant then the calculation of statistics and the factor analysis are carried out for investigation of emission source. Facilities for NAA are installed in a new HANARO reactor, functional test is performed for routine operation. In addition, unified software code for NAA is developed to improve accuracy, precision and abilities of analytical processes. (author). 103 refs., 61 tabs., 19 figs.

  7. Project Report of Neutron Beam Application on China Advanced Research Reactor%中国先进研究堆中子束应用关键技术及若干科学问题立项报告

    Institute of Scientific and Technical Information of China (English)

    陈东风

    2016-01-01

    该研究的研究内容涵盖物理、化学、材料和工程等领域,拟解决以下3个方面的关键科学问题:(1)中子散射关键技术方法研究;(2)新型功能材料结构和性质关系的中子散射研究;(3)工程部件应力分布和中子成像的方法学研究。为此,项目设置6个子研究:(1)反应堆中子束优化及特殊样品环境研究;(2)单晶和多晶新材料的中子衍射研究;(3)强关联体系中原子与自旋动态的中子散射研究;(4)磁性材料的中子散射研究;(5)中子应力三维无损深度测量技术研究;(6)中子在物质中的衰减与中子成像研究。%Nowadays to study the relation between structures and properties of materials is one of the main tasks in Physics, Chemistry, material science and others research fields, and it is a usual way to get the information using particles interaction with matters, among which X ray and neutron are two basic ones. It is well know that the interaction principle of neutrons and photons with atoms is quite different, so more information will be obtained using both complementary tools. The neutron has the following properties: no charge, low energy, inherence magnetic moment, deep penetration, sensitivity on light element (such as H, C, N, O, etc), distinguishability on isotopes (such as 7Li、11B etc.) and near neighbor elements (such as Mn, Fe and so on). So neutron scattering technique can not only study the crystal structure, but also obtain the magnetic structure information; not only investigate the static microstructure of materials, but also prove the reliabilities of theoretical models. CARR is expected to be critical in 2009, 60 MW and 8×1014N/(cm2·S-1) unperturbed thermal neutron flux make it standing on an international advanced level. Using the four circle, powder, residual stress neutron diffractometers and neutron imaging instrument at CARR, in this project studies focus on three aspects: (1)the methodology study of

  8. The accelerator neutron source for boron neutron capture therapy

    Science.gov (United States)

    Kasatov, D.; Koshkarev, A.; Kuznetsov, A.; Makarov, A.; Ostreinov, Yu; Shchudlo, I.; Sorokin, I.; Sycheva, T.; Taskaev, S.; Zaidi, L.

    2016-11-01

    The accelerator based epithermal neutron source for Boron Neutron Capture Therapy (BNCT) is proposed, created and used in the Budker Institute of Nuclear Physics. In 2014, with the support of the Russian Science Foundation created the BNCT laboratory for the purpose to the end of 2016 get the neutron flux, suitable for BNCT. For getting 3 mA 2.3 MeV proton beam, was created a new type accelerator - tandem accelerator with vacuum isolation. On this moment, we have a stationary proton beam with 2.3 MeV and current 1.75 mA. Generation of neutrons is carried out by dropping proton beam on to lithium target as a result of threshold reaction 7Li(p,n)7Be. Established facility is a unique scientific installation. It provides a generating of neutron flux, including a monochromatic energy neutrons, gamma radiation, alpha-particles and positrons, and may be used by other research groups for carrying out scientific researches. The article describes an accelerator neutron source, presents and discusses the result of experiments and declares future plans.

  9. 小口径速射舰炮武器系统反导射击方法研究%Antimissile Firing Method Research of Minor-caliber Rapid,-firing Naval Gun Weapon System

    Institute of Scientific and Technical Information of China (English)

    刘德耀; 孙朝江; 赵岩

    2011-01-01

    小口径速射舰炮受弹鼓容量及舰炮发射系统限制,一般不能在舰炮武器系统有效射击范围内全航路持续射击,这就要求对射击方法进行研究.应用蒙特卡洛法,在MATLAB软件平台上计算了小口径速射舰炮武器系统对匀速直线运动导弹的命中概率与弹丸相遇点距离间的关系,提出了以全航路最大概率命中导弹有效部位为基础制定射击终止点,反推射击起始点的射击方法,提高了舰炮武器系统在全航路射弹数限定条件下的命中概率;以舰炮武器系统跟踪器最大跟踪角速度限制因素为例,分析了导弹运动速度、航路捷径与射击区域的对应关系,并应用本方法对导弹典型航路的射击方案进行了仿真.仿真结果表明该方法在一定条件下能有效提高舰炮武器系统对导弹的全航路命中概率.%The magazine capacity and the launch system of naval gun are limit the minor-caliber rapid-firing naval gun to full-track continuous firing in the effective firing range of the naval gun weapon system, so we study the firing method. By means of Monte Carlo calculated the relationship between hit probability of minor-caliber rapid-firing naval gun weapon system on the missile of constant velocity movement and the distance of bullet meeting point in MATLAB. Based on full-track maximum probability hit the effective place of missile to set firing ending, to deduce firing beginning was presented and the method improved the hit probability of naval gun weapon system under the ammunition's limiting condition. Take the limiting factor of tracker's maximum tracking angular velocity as an example to analysis the relation of missile moving speed and track shortcut and firing area. And adopt this method to simulation the fire method of typical track of missile. Simulation results show that the method can effective increase full-track hit probability of naval gun weapon system on missile below some conditions.

  10. Auditing nuclear weapons quality programs at Los Alamos

    Energy Technology Data Exchange (ETDEWEB)

    Davis, A.H.

    1988-01-01

    Some of the problems involved in introducing quality assurance on a broad scale in a national laboratory are discussed. A philosophy of how QA can be utilized beneficially in research and development activities is described briefly, and our experiences at Los Alamos in applying QA to nuclear weapons activities are outlines. The important role of audits is emphasized; audits are used not merely to determine the effectiveness of QA programs but also to explain and demonstrate the usefulness of QA to a generally sceptical body of engineers and scientists. Finally, some ways of easing the application of QA in the future are proposed. 1 ref.

  11. Neutron diffraction

    Energy Technology Data Exchange (ETDEWEB)

    Heger, G. [Rheinisch-Westfaelische Technische Hochschule Aachen, Inst. fuer Kristallographie, Aachen (Germany)

    1996-12-31

    X-ray diffraction using conventional laboratory equipment and/or synchrotron installations is the most important method for structure analyses. The purpose of this paper is to discuss special cases, for which, in addition to this indispensable part, neutrons are required to solve structural problems. Even though the huge intensity of modern synchrotron sources allows in principle the study of magnetic X-ray scattering the investigation of magnetic structures is still one of the most important applications of neutron diffraction. (author) 15 figs., 1 tab., 10 refs.

  12. Neutronics of pulsed spallation neutron sources

    CERN Document Server

    Watanabe, N

    2003-01-01

    Various topics and issues on the neutronics of pulsed spallation neutron sources, mainly for neutron scattering experiments, are reviewed to give a wide circle of readers a better understanding of these sources in order to achieve a high neutronic performance. Starting from what neutrons are needed, what the spallation reaction is and how to produce slow-neutrons more efficiently, the outline of the target and moderator neutronics are explained. Various efforts with some new concepts or ideas have already been devoted to obtaining the highest possible slow-neutron intensity with desired pulse characteristics. This paper also reviews the recent progress of such efforts, mainly focused on moderator neutronics, since moderators are the final devices of a neutron source, which determine the source performance. Various governing parameters for neutron-pulse characteristics such as material issues, geometrical parameters (shape and dimensions), the target-moderator coupling scheme, the ortho-para-hydrogen ratio, po...

  13. The Manuel Lujan, Jr. Neutron Scattering Center, LANSCE experiment reports: 1990 Run Cycle

    Energy Technology Data Exchange (ETDEWEB)

    DiStravolo, M.A. (comp.)

    1991-10-01

    This year was the third in which LANSCE ran a formal user program. A call for proposals was issued before the scheduled run cycles, and experiment proposals were submitted by scientists from universities, industry, and other research facilities around the world. An external program advisory committee, which LANSCE shares with the Intense Pulsed Neutron Source (IPNS), Argonne National Laboratory examined the proposals and made recommendations. At LANSCE, neutrons are produced by spallation when a pulsed, 800-MeV proton beam impinges on a tungsten target. The proton pulses are provided by the Clinton P. Anderson Meson Physics Facility (LAMPF) accelerator and an associated Proton Storage Ring (PSR), which can alter the intensity, time structure, and repetition rate of the pulses. The LAMPF protons of Line D are shared between the LANSCE target and the Weapons Neutron Research facility, which results in LANSCE spectrometers being available to external users for unclassified research about 80% of each six-month LAMPF run cycle. Measurements of interest to the Los Alamos National Laboratory may also be performed and may occupy up to an additional 20% of the available beam time. These experiments are reviewed by an internal program advisory committee. One hundred thirty-four proposals were submitted for unclassified research and twelve proposals for research of a programmatic nature to the Laboratory. Our definition of beam availability is when the proton current from the PSR exceeds 50% of the planned value. The PSR ran at 65{mu}A current (average) at 20 Hz for most of 1990. All of the scheduled experiments were performed and experiments in support of the LANSCE research program were accomplished during the discretionary periods.

  14. The Manuel Lujan, Jr. Neutron Scattering Center (LANSCE) experiment reports 1992 run cycle. Progress report

    Energy Technology Data Exchange (ETDEWEB)

    DiStravolo, M.A. [comp.

    1993-09-01

    This year was the fifth in which LANSCE ran a formal user program. A call for proposals was issued before the scheduled run cycles, and experiment proposals were submitted by scientists from universities, industry, and other research facilities around the world. An external program advisory committee, which LANSCE shares with the Intense Pulsed Neutron Source (IPNS), Argonne National Laboratory, examined the proposals and made recommendations. At LANSCE, neutrons are produced by spallation when a pulsed, 800-MeV proton beam impinges on a tungsten target. The proton pulses are provided by the Clinton P. Anderson Meson Physics Facility (LAMPF) accelerator and an associated Proton Storage Ring (PSR), which can alter the intensity, time structure, and repetition rate of the pulses. The LAMPF protons of Line D are shared between the LANSCE target and the Weapons Neutron Research (WNR) facility, which results in LANSCE spectrometers being available to external users for unclassified research about 80% of each annual LAMPF run cycle. Measurements of interest to the Los Alamos National Laboratory may also be performed and may occupy up to an additional 20% of the available beam time. These experiments are reviewed by an internal program advisory committee. One hundred sixty-seven proposals were submitted for unclassified research and twelve proposals for research of a programmatic interest to the Laboratory; six experiments in support of the LANSCE research program were accomplished during the discretionary periods. Oversubscription for instrument beam time by a factor of three was evident with 839 total days requested and only 371 available for allocation.

  15. Neutron scattering instruments for the Spallation Neutron Source (SNS)

    Energy Technology Data Exchange (ETDEWEB)

    Crawford, R.K.; Fornek, T. [Argonne National Lab., IL (United States); Herwig, K.W. [Oak Ridge National Lab., TN (United States)

    1998-07-01

    The Spallation Neutron Source (SNS) is a 1 MW pulsed spallation source for neutron scattering planned for construction at Oak Ridge National Laboratory. This facility is being designed as a 5-laboratory collaboration project. This paper addresses the proposed facility layout, the process for selection and construction of neutron scattering instruments at the SNS, the initial planning done on the basis of a reference set of ten instruments, and the plans for research and development (R and D) to support construction of the first ten instruments and to establish the infrastructure to support later development and construction of additional instruments.

  16. Sea-dumped chemical weapons: environmental risk, occupational hazard.

    Science.gov (United States)

    Greenberg, M I; Sexton, K J; Vearrier, D

    2016-01-01

    for decades. Rates of solubility and hydrolysis and levels of innate toxicity of a chemical agent are used to predict the risk to the marine environments. The organoarsenicals eventually breakdown into arsenic, and thus present an indefinite timeline for contamination. Generally, studies assaying sediment and water levels of parent chemical agents and breakdown products at dumpsites have found minimal amounts of relevant chemicals, although arsenic levels are typically higher in dumpsites than reference areas. Studies of marine organisms have not shown concerning amounts of chemical agents or breakdown products in tissue, but have shown evidence of chronic toxicity. There is believed to be minimal risk posed by seafood consumption. Microbiota assays of dumpsites are significantly altered in species composition compared to reference sites, which may imply unseen but significant changes to ecosystems of dumpsites. Human health concerns: The major human health risk at this time appears to arise from acute exposure to an agent by either accidental recovery of a chemical weapon on a fishing vessel, or by munitions washed ashore onto beaches. Improving technology continues to make the deep sea more accessible, thus increasing the risk of disturbing munitions lying on or buried in the seabed. Pipe laying, cable burying, drilling, scuba diving, trawling, and undersea scientific research are the activities posing the most risk. The long-term threat to the benthic habitat via increased arsenic concentrations, shifts in microbiota speciation, and chronic toxicity to vertebrates and invertebrates is not currently understood. The risk to the environment of massive release via disturbance remains a distinct possibility. Terrorist recovery and re-weaponization of chemical agents is a remote possibility.

  17. Task Analyses of Three Selected Weapons Systems.

    Science.gov (United States)

    1976-10-01

    using weapons is a joint function of the specific weapon system, the goals (missions) of the system, and the environment in which it is used. The first...Identification of fire mission profiles which state general job functions for each type of typical mission. Documentary sources such as Field Manuals...nd Arin,,, Ui, Guni i A,!i" tant uuPnrr No. I Can; n , r Grup - ( nile. .rs and Prir Diff,-ront S, tm: -inch L,,t.’r _, Fort Hood l::t Cavall, I

  18. #TheWeaponizationOfSocialMedia

    DEFF Research Database (Denmark)

    Nissen, Thomas Elkjer

    In today’s conflict environment, transformed by information technology and of who can communicate and how, states, non-state actors, ad hoc activist networks and individuals create effect(s) in and through social network media in support of their objectives. #TheWeaponizationOfSocialMedia develops...... a framework for understanding how social network media shapes global politics and contemporary conflicts by examining their role as a platform for conduction intelligence collection, targeting, cyber-operations, psychological warfare and command and control activities. Through these, the weaponization...

  19. Introduction to neutron scattering. Lecture notes of the introductory course

    Energy Technology Data Exchange (ETDEWEB)

    Furrer, A. [ed.

    1996-12-31

    These proceedings enclose ten papers presented at the 1. European Conference on Neutron scattering (ECNS `96). The aim of the Introductory Course was fourfold: - to learn the basic principles of neutron scattering, - to get introduced into the most important classes of neutron scattering instruments, -to learn concepts and their transformation into neutron scattering experiments in various fields of condensed matter research, - to recognize the limitations of the neutron scattering technique as well as to the complementarity of other methods. figs., tabs., refs.

  20. Assessment of the neutron activation of a stainless steel sample in a Research Nuclear Reactor using the Monte Carlo method and CINDER'90

    Science.gov (United States)

    Lázaro, Ignacio; Ródenas, José; Marques, José G.; Gallardo, Sergio

    2014-06-01

    Materials in a nuclear reactor are activated by neutron irradiation. When they are withdrawn from the reactor and placed in some storage, the potential dose received by workers in the surrounding area must be taken into account. In previous papers, activation of control rods in a NPP with BWR and dose rates around the storage pool have been estimated using the MCNP5 code based on the Monte Carlo method. Models were validated comparing simulation results with experimental measurements. As the activation is mostly produced in stainless steel components of control rods the activation model can be also validated by means of experimental measurements on a stainless steel sample after being irradiated in a reactor. This has been done in the Portuguese Research Reactor at Instituto Tecnológico e Nuclear. The neutron activation has been calculated by two different methods, Monte Carlo and CINDER'90, and results have been compared. After irradiation, dose rates at the water surface of the reactor pool were measured, with the irradiated stainless steel sample submerged at different positions under water. Experimental measurements have been compared with simulation results using Monte Carlo. The comparison shows a good agreement confirming the validation of models.

  1. From weapons to white dwarfs

    Science.gov (United States)

    Cartlidge, Edwin

    2016-10-01

    Military research centres that use giant lasers to study conditions inside nuclear warheads are increasingly opening their doors to university students. Edwin Cartlidge asks what the labs and the researchers have to gain from the arrangement

  2. Igniting the Light Elements: The Los Alamos Thermonuclear Weapon Project, 1942-1952

    Energy Technology Data Exchange (ETDEWEB)

    Fitzpatrick, Anne C. [Virginia Polytechnic Inst. and State Univ. (Virginia Tech), Blacksburg, VA (United States)

    1999-07-01

    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 US 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. Adapting Thomas P. Hughes's ''large technological systems'' thesis, I focus on the technical, social, political, and human problems that nuclear weapons scientists faced while pursuing the thermonuclear project, demonstrating why the early American thermonuclear bomb project was an immensely complicated scientific and technological undertaking. I concentrate mainly on Los Alamos Scientific Laboratory's Theoretical, or T, Division, and its members' attempts to complete an accurate mathematical treatment of the ''Super''--the most difficult problem in physics in the postwar period--and other fusion weapon theories. Although tackling a theoretical problem, theoreticians had to address technical and engineering issues as well. I demonstrate the relative value and importance of H-bomb research over time in the postwar era to

  3. Implementing the chemical weapons convention

    Energy Technology Data Exchange (ETDEWEB)

    Kellman, B.; Tanzman, E. A.

    1999-12-07

    In 1993, as the CWC ratification process was beginning, concerns arose that the complexity of integrating the CWC with national law could cause each nation to implement the Convention without regard to what other nations were doing, thereby causing inconsistencies among States as to how the CWC would be carried out. As a result, the author's colleagues and the author prepared the Manual for National Implementation of the Chemical Weapons Convention and presented it to each national delegation at the December 1993 meeting of the Preparatory Commission in The Hague. During its preparation, the Committee of CWC Legal Experts, a group of distinguished international jurists, law professors, legally-trained diplomats, government officials, and Parliamentarians from every region of the world, including Central Europe, reviewed the Manual. In February 1998, they finished the second edition of the Manual in order to update it in light of developments since the CWC entered into force on 29 April 1997. The Manual tries to increase understanding of the Convention by identifying its obligations and suggesting methods of meeting them. Education about CWC obligations and available alternatives to comply with these requirements can facilitate national response that are consistent among States Parties. Thus, the Manual offers options that can strengthen international realization of the Convention's goals if States Parties act compatibly in implementing them. Equally important, it is intended to build confidence that the legal issues raised by the Convention are finite and addressable. They are now nearing competition of an internet version of this document so that interested persons can access it electronically and can view the full text of all of the national implementing legislation it cites. The internet address, or URL, for the internet version of the Manual is http: //www.cwc.ard.gov. This paper draws from the Manual. It comparatively addresses approximately thirty

  4. 10 CFR Appendix H to Part 73 - Weapons Qualification Criteria

    Science.gov (United States)

    2010-01-01

    ... position, then fire 2 rounds and reholster 2 15 yards 2 5 seconds Standing, draw weapon, move to kneeling...) Standing, draw weapon, fire 2 rounds, move to kneeling position and fire 2 rounds, reload and reholster Minimum qualifying = 70%. 4 15 yards 2 5 seconds Draw weapon and fire 2 rounds standing, come to low...

  5. 25 CFR 11.444 - Carrying concealed weapons.

    Science.gov (United States)

    2010-04-01

    ... 25 Indians 1 2010-04-01 2010-04-01 false Carrying concealed weapons. 11.444 Section 11.444 Indians... ORDER CODE Criminal Offenses § 11.444 Carrying concealed weapons. A person who goes about in public places armed with a dangerous weapon concealed upon his or her person is guilty of a misdemeanor unless...

  6. Someone at School Has a Weapon. What Should I Do?

    Science.gov (United States)

    ... for You Shyness Someone at School Has a Weapon. What Should I Do? KidsHealth > For Teens > Someone at School Has a Weapon. What Should I Do? Print A A A ... Why do students bring guns, knives, or other weapons to school? Some are just showing off, others ...

  7. 76 FR 1136 - Electroshock Weapons Test and Measurement Workshop

    Science.gov (United States)

    2011-01-07

    ... National Institute of Standards and Technology Electroshock Weapons Test and Measurement Workshop AGENCY..., academia, military, test instrument manufacturers, etc.) of electroshock weapons that provide stand-off... requirements for electroshock weapons, the Law Enforcement Standards Office (OLES) at NIST has developed...

  8. 46 CFR 386.23 - Weapons and explosives.

    Science.gov (United States)

    2010-10-01

    ... 46 Shipping 8 2010-10-01 2010-10-01 false Weapons and explosives. 386.23 Section 386.23 Shipping... AND GROUNDS AT THE UNITED STATES MERCHANT MARINE ACADEMY § 386.23 Weapons and explosives. No person shall carry or possess firearms, other dangerous or deadly weapons or parts thereof, explosives or items...

  9. Agent-based Modeling Methodology for Analyzing Weapons Systems

    Science.gov (United States)

    2015-03-26

    43 Figure 14: Simulation Study Methodology for the Weapon System Analysis Metrics Definition and Data Collection The analysis plan calls for...AGENT-BASED MODELING METHODOLOGY FOR ANALYZING WEAPONS SYSTEMS THESIS Casey D. Connors, Major, USA...AGENT-BASED MODELING METHODOLOGY FOR ANALYZING WEAPONS SYSTEMS THESIS Presented to the Faculty Department of Operational Sciences

  10. 36 CFR 702.7 - Weapons and explosives.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Weapons and explosives. 702.7... Weapons and explosives. Except where duly authorized by law, and in the performance of law enforcement functions, no person shall carry firearms, other dangerous or deadly weapons, or explosives, either openly...

  11. 31 CFR 407.13 - Weapons and explosives.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 2 2010-07-01 2010-07-01 false Weapons and explosives. 407.13... TREASURY ANNEX § 407.13 Weapons and explosives. No person while on the property shall carry firearms, other dangerous or deadly weapons, or explosives, either openly or concealed, except for official purposes. ...

  12. 49 CFR 1544.219 - Carriage of accessible weapons.

    Science.gov (United States)

    2010-10-01

    ... 49 Transportation 9 2010-10-01 2010-10-01 false Carriage of accessible weapons. 1544.219 Section...: AIR CARRIERS AND COMMERCIAL OPERATORS Operations § 1544.219 Carriage of accessible weapons. (a... weapons, do not apply to a law enforcement officer (LEO) aboard a flight for which screening is required...

  13. 31 CFR 91.13 - Weapons and explosives.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Weapons and explosives. 91.13 Section... CONDUCT IN OR ON THE BUREAU OF THE MINT BUILDINGS AND GROUNDS § 91.13 Weapons and explosives. No person while on the property shall carry firearms, other dangerous or deadly weapons, or explosives, either...

  14. 44 CFR 15.15 - Weapons and explosives.

    Science.gov (United States)

    2010-10-01

    ... 44 Emergency Management and Assistance 1 2010-10-01 2010-10-01 false Weapons and explosives. 15.15... EMERGENCY TRAINING CENTER § 15.15 Weapons and explosives. No person entering or while at Mt. Weather or the NETC will carry or possess firearms, other dangerous or deadly weapons, explosives or items intended to...

  15. 7 CFR 502.13 - Weapons and explosives.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Weapons and explosives. 502.13 Section 502.13....13 Weapons and explosives. No person while in or on BARC property shall carry firearms, other dangerous or deadly weapons, or explosives, either openly or concealed, except as officially authorized for...

  16. 32 CFR 552.125 - Disposition of confiscated weapons.

    Science.gov (United States)

    2010-07-01

    ... 32 National Defense 3 2010-07-01 2010-07-01 true Disposition of confiscated weapons. 552.125..., Ammunition, and Explosives-Fort Lewis, Washington § 552.125 Disposition of confiscated weapons. Commanders will maintain confiscated weapons in the unit arms room pending final disposition. They will provide...

  17. 36 CFR 504.14 - Weapons and explosives.

    Science.gov (United States)

    2010-07-01

    ... 36 Parks, Forests, and Public Property 3 2010-07-01 2010-07-01 false Weapons and explosives. 504... GOVERNING SMITHSONIAN INSTITUTION BUILDINGS AND GROUNDS § 504.14 Weapons and explosives. No person while on the premises shall carry firearms, other dangerous or deadly weapons, or explosives, either openly or...

  18. 31 CFR 0.215 - Possession of weapons and explosives.

    Science.gov (United States)

    2010-07-01

    ... 31 Money and Finance: Treasury 1 2010-07-01 2010-07-01 false Possession of weapons and explosives... OF THE TREASURY EMPLOYEE RULES OF CONDUCT Rules of Conduct § 0.215 Possession of weapons and explosives. (a) Employees shall not possess firearms, explosives, or other dangerous or deadly weapons...

  19. 7 CFR 500.12 - Weapons and explosives.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Weapons and explosives. 500.12 Section 500.12... OF AGRICULTURE NATIONAL ARBORETUM Conduct on U.S. National Arboreturm Property § 500.12 Weapons and... weapons, or explosives, either openly or concealed, except for authorized official purposes. (b) No person...

  20. 7 CFR 503.13 - Weapons and explosives.

    Science.gov (United States)

    2010-01-01

    ... 7 Agriculture 6 2010-01-01 2010-01-01 false Weapons and explosives. 503.13 Section 503.13... OF AGRICULTURE CONDUCT ON PLUM ISLAND ANIMAL DISEASE CENTER § 503.13 Weapons and explosives. No person while in or on the PIADC shall carry firearms or other dangerous or deadly weapons or explosives...