The research on magnetic exploring abandoned chemical weapons by Japanese

International Nuclear Information System (INIS)

Wang Luoguo; Li Jingyue; Wang Zezhong

2007-01-01

During Word war II, a lot of chemical weapons were left by Japanese on our land. It is very difficult to explore because its complicated states underground. There is no document about the details of this. Few of the research work have been done. In order to destroy completely abandoned chemical weapons by Japanese, the paper has given a serious study on the means to explore the chemical weapons for the purpose to protect our environment and benefit our people. After plenty of research and test, we get good results. (authors)

Monte Carlo simulation of the neutron-induced prompt γ ray spectroscopy of the CW abandoned by Japan

International Nuclear Information System (INIS)

Wang Bairong; Yang Zhongping; Zhang Wenzhong

2005-01-01

This paper introduced the principle of identifying the chemical weapon by neutron-induced prompt γ ray, simulated and analyzed the neutron-induced prompt γ ray spectroscopy of chemical weapon abandoned by Japan in the different condition, using the MCNP-4C Monte Carlo program, whereby supply important datum and reference for the aftertime deeper research and disposal of Japan-abandoned chemical weapon. (authors)

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.

Nuclear weapon relevant materials and preventive arms control. Uranium-free fuels for plutonium elimination and spallation neutron sources

International Nuclear Information System (INIS)

Liebert, Wolfgang; Englert, Matthias; Pistner, Christoph

2009-01-01

Today, the most significant barrier against the access to nuclear weapons is to take hold on sufficient amounts of nuclear weapon-relevant nuclear materials. It is mainly a matter of fissionable materials (like highly enriched uranium and plutonium) but also of fusionable tritium. These can be used as reactor fuel in civil nuclear programmes but also in nuclear weapon programmes. To stop or to hinder nuclear proliferation, in consequence, there is not only a need to analyse open or covered political objectives and intentions. In the long term, it might be more decisive to analyse the intrinsic civil-military ambivalence of nuclear materials and technologies, which are suitable for sensitive material production. A farsighted strategy to avoid proliferation dangers should take much more account to technical capabilities as it is done in the political debate on nuclear non-proliferation so far. If a technical option is at a state's disposal, it is extremely difficult and lengthy to revert that again. The dangers, which one has to react to, are stemming from already existing stocks of nuclear weapon-relevant materials - in the military as well as in the civil realm - and from existing or future technologies, which are suitable for the production of such materials (cf. info 1 and 2). Therefore, the overall approach of this research project is to strive for a drastic reduction of the access to nuclear weapon-relevant material and its production capabilities. Thus, on one hand the nuclear proliferation by state actors could be answered more effectively, on the other hand by that approach a decisive barrier against the access on nuclear weapons by sub-national groups and terrorists could also be erected. For this purpose, safeguards of the International Atomic Energy Agency (IAEA) and other measures of physical accountancy will remain indispensable elements of arms control. However, one has to consider that the goal of nuclear non-proliferation could not be achieved and

The Monte Carlo simulation of the neutron-induced prompt gamma ray spectroscopy of the CW abandoned by Japan

International Nuclear Information System (INIS)

Wang Bairong; Yang Zhongping; Zhan Wenzhong

2003-01-01

This paper introduced the principle of identifying the chemical weapon abandoned by Japan by neutron-induced prompt gamma ray. Using the MCNP-4C Monte Carlo program, this paper simulated and analyzed the neutron-induced prompt gamma ray spectroscopy of chemical weapon abandoned by Japan, whereby supply important datum and reference for the aftertime deeper research and disposal of Japan-abandoned chemical weapon. (authors)

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.

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

International Nuclear Information System (INIS)

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

Nuclear weapons research in Sweden. The co-operation between civilian and military research, 1947 - 1972

International Nuclear Information System (INIS)

Jonter, Thomas

2002-05-01

The Swedish nuclear weapons research began as early as 1945, shortly after the first atomic bombs fell over Japan. The assignment to look into the new weapon of mass destruction went to the Swedish National Defence Research Establishment (FOA). Admittedly, the main aim of the research initiated at that time was to find out how Sweden could best protect itself against a nuclear weapon attack. However, from the outset FOA was interested in investigating the possibilities of manufacturing what was then called an atomic bomb. A co-operation between FOA and AB Atomenergi (AE), which was created in 1947 in order to be responsible for the industrial development of civilian nuclear energy, was initiated. AE made several technical investigations within this co-operation regarding choice of reactors and preconditions for a production of weapons-grade plutonium. The first purpose of this report is therefore to investigate how this co-operation emerged and what consequences it had for the project to produce basic information for the Swedish manufacture of nuclear weapons. In general terms, the finding of this report is that FOA was responsible for the overall nuclear weapons research. For this reason, FOA was in charge of the construction of the nuclear device and the studies of its effects. Additionally, AE should deliver basic information of a possible production of weapons-grade plutonium and investigate the possibilities of a production or a procurement of inspection-free heavy water (i.e. without inspections by the supplying country). AE should also build a reprocessing plant and manufacture fuel elements to be used in the reactors for a production of weapons-grade plutonium. Furthermore, it is important to emphasise that both FOA and AE conducted plutonium research. The reason why FOA conducted this research was that the plutonium had to be in metallic form in order to be used in a nuclear weapons device. Therefore, FOA carried out research with the purpose of producing

Nuclear weapons research in Sweden. The co-operation between civilian and military research, 1947 - 1972

Energy Technology Data Exchange (ETDEWEB)

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

2002-05-01

The Swedish nuclear weapons research began as early as 1945, shortly after the first atomic bombs fell over Japan. The assignment to look into the new weapon of mass destruction went to the Swedish National Defence Research Establishment (FOA). Admittedly, the main aim of the research initiated at that time was to find out how Sweden could best protect itself against a nuclear weapon attack. However, from the outset FOA was interested in investigating the possibilities of manufacturing what was then called an atomic bomb. A co-operation between FOA and AB Atomenergi (AE), which was created in 1947 in order to be responsible for the industrial development of civilian nuclear energy, was initiated. AE made several technical investigations within this co-operation regarding choice of reactors and preconditions for a production of weapons-grade plutonium. The first purpose of this report is therefore to investigate how this co-operation emerged and what consequences it had for the project to produce basic information for the Swedish manufacture of nuclear weapons. In general terms, the finding of this report is that FOA was responsible for the overall nuclear weapons research. For this reason, FOA was in charge of the construction of the nuclear device and the studies of its effects. Additionally, AE should deliver basic information of a possible production of weapons-grade plutonium and investigate the possibilities of a production or a procurement of inspection-free heavy water (i.e. without inspections by the supplying country). AE should also build a reprocessing plant and manufacture fuel elements to be used in the reactors for a production of weapons-grade plutonium. Furthermore, it is important to emphasise that both FOA and AE conducted plutonium research. The reason why FOA conducted this research was that the plutonium had to be in metallic form in order to be used in a nuclear weapons device. Therefore, FOA carried out research with the purpose of producing

Neutron Research in HANARO

International Nuclear Information System (INIS)

Kim, Hark Rho

2005-01-01

HANARO (High-flux Advanced Neutron Application Reactor), which was designed and constructed by indigenous technology, is a world-class multi-purpose research reactor with a design thermal power of 30 MW, providing high neutron flux for various applications in Korea. HANARO has been operated since its first criticality in February 1995, and is now successfully utilized in such areas as neutron beam research, fuel and materials tests, radioisotopes and radiopharmaceuticals production, neutron activation analysis, and neutron transmutation doping, etc. A number of experimental facilities have been developed and installed since the beginning of reactor operation, and R and D activities for installing more facilities are actively under progress. Three flux traps in the core (CT, IR1, IR2), providing a high fast neutron flux, can be used for materials and fuel irradiation tests. They are also proper for production of high specific activity radioisotopes. Four vertical holes in the outer core region, abundant in epithermal neutrons, are used for fuel or material tests and radioisotope production. In the heavy water reflector region, 25 vertical holes with high quality thermal neutrons are located for radioisotope production, neutron activation analysis, neutron transmutation doping and cold neutron source installation. The two largest holes named NTD1 and NTD2 are for neutron transmutation doping, CNS for the cold neutron source installation, and LH for the irradiation of large targets. The high resolution powder diffractometer (HRPD) became operational in 1998, followed by the four circle diffractometer (FCD) in 1999, the residual stress instrument (RSI) in 2000, and the small angle neutron spectrometer (SANS) in 2001, respectively. HRPD and SANS became the most popular instruments these days, attracting wide range of users from academia, institutes and industries. We have made a lot of efforts during the last 10 years to develop some key components such as

Materials research and development for nuclear weapons applications

International Nuclear Information System (INIS)

Anon.

1977-01-01

Highlights of a comprehensive summary of materials research and development being conducted at Sandia in support of the nuclear weapons development programs are presented. The developments include foams, encapsulants, metals with memories, material equations-of-state, composites, glass-to-metal bonds, and design processes

Neutronics benchmark of a MOX assembly with near-weapons-grade plutonium

International Nuclear Information System (INIS)

Difilippo, F.C.; Fisher, S.E.

1998-01-01

One of the proposed ways to dispose of surplus weapons-grade plutonium (Pu) is to irradiate the high-fissile material in light-water reactors in order to reduce the Pu enrichment to the level of spent fuels from commercial reactors. Considerable experience has been accumulated about the behavior of mixed-oxide (MOX) uranium and plutonium fuels for plutonium recycling in commercial reactors, but the experience is related to Pu enrichments typical of spent fuels quite below the values of weapons-grade plutonium. Important decisions related to the kind of reactors to be used for the disposition of the plutonium are going to be based on calculations, so the validation of computational algorithms related to all aspects of the fuel cycle (power distributions, isotopics as function of the burnup, etc.), for weapons-grade isotopics is very important. Analysis of public domain data reveals that the cycle-2 irradiation in the Quad cities boiling-water reactor (BWR) is the most recent US destructive examination. This effort involved the irradiation of five MOX assemblies using 80 and 90% fissile plutonium. These benchmark data were gathered by General Electric under the sponsorship of the Electric Power Research Institute. It is emphasized, however, that global parameters are not the focus of this benchmark, since the five bundles containing MOX fuels did not significantly affect the overall core performance. However, since the primary objective of this work is to compare against measured post-irradiation assembly data, the term benchmark is applied here. One important reason for performing the benchmark on Quad Cities irradiation is that the fissile blends (up to 90%) are higher than reactor-grade and, quite close to, weapons-grade isotopics

AWRE: Atomic Weapons Research Establishment

International Nuclear Information System (INIS)

1983-01-01

This reviews the work of AWRE at Aldermaston and Foulness. The main programme is nuclear and is concerned with the design and development of warheads for strategic and tactical nuclear weapons for the British nuclear deterrent, including those for the Royal Navy's missile carrying submarine fleet. The work is described grouped as design physics, development and materials. Services to these groups and to the whole establishment are provided by Engineering, Safety and Administration. The work ranges from long-term fundamental research, the development of technology, design, prototype development to the environmental testing of engineered products. In materials research the emphasis is on plutonium, uranium and beryllium, on high explosives and a wide range of inorganic and organic materials. The physics of the earth's crust is studied to aid detection of underground nuclear explosions. Reactor research facilities include the two reactors, Herald and Viper. (U.K.)

The Swedish National Defence Research Establishment and the plans for Swedish nuclear weapons

International Nuclear Information System (INIS)

Jonter, Thomas

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. During this period

Materials research with neutron beams from a research reactor

Energy Technology Data Exchange (ETDEWEB)

Root, J.; Banks, D. [Canadian Neutron Beam Centre, Chalk River Laboratories, Chalk River, Ontario (Canada)

2015-03-15

Because of the unique ways that neutrons interact with matter, neutron beams from a research reactor can reveal knowledge about materials that cannot be obtained as easily with other scientific methods. Neutron beams are suitable for imaging methods (radiography or tomography), for scattering methods (diffraction, spectroscopy, and reflectometry) and for other possibilities. Neutron-beam methods are applied by students and researchers from academia, industry and government to support their materials research programs in several disciplines: physics, chemistry, materials science and life science. The arising knowledge about materials has been applied to advance technologies that appear in everyday life: transportation, communication, energy, environment and health. This paper illustrates the broad spectrum of materials research with neutron beams, by presenting examples from the Canadian Neutron Beam Centre at the NRU research reactor in Chalk River. (author)

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.

The weapons effect.

Science.gov (United States)

Benjamin, Arlin James; Bushman, Brad J

2018-02-01

In some societies, weapons are plentiful and highly visible. This review examines recent trends in research on the weapons effect, which is the finding that the mere presence of weapons can prime people to behave aggressively. The General Aggression Model provides a theoretical framework to explain why the weapons effect occurs. This model postulates that exposure to weapons increases aggressive thoughts and hostile appraisals, thus explaining why weapons facilitate aggressive behavior. Data from meta-analytic reviews are consistent with the General Aggression Model. These findings have important practical as well as theoretical implications. They suggest that the link between weapons and aggression is very strong in semantic memory, and that merely seeing a weapon can make people more aggressive. Copyright © 2017 Elsevier Ltd. All rights reserved.

Perceived popularity of adolescents who use weapons in violence and adolescents who only carry weapons.

Science.gov (United States)

Wallace, Lacey N

2017-01-01

Prior research has found that persistently delinquent youth or more violent youth were less popular than their less delinquent peers (Young, 2013). However, recent research has also found that weapon carrying is associated with being more popular in adolescence (Dijkstra et al., 2010). The present paper examines the perceived popularity of adolescents who carry weapons in comparison to those who both carry and use weapons in acts of violence or threatened violence. Data consist of two waves from the National Longitudinal Study of Adolescent to Adult Health. Analyses use OLS regression with lagged predictors. This paper found no differences in number of friends between weapon carriers and weapon users. However, among both male and female gang members, those who did not use or carry weapons (abstainers) named significantly fewer friends than weapon users. Among females, weapon abstainers both named and were named by significantly more people than weapon users. These differences were not observed for males. Implications of these results and directions for future research are discussed.

Materials irradiation research in neutron science

Energy Technology Data Exchange (ETDEWEB)

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

1997-11-01

Materials irradiation researches are planned in Neutron Science Research Program. A materials irradiation facility has been conceived as one of facilities in the concept of Neutron Science Research Center at JAERI. The neutron irradiation field of the facility is characterized by high flux of spallation neutrons with very wide energy range up to several hundred MeV, good accessibility to the irradiation field, good controllability of irradiation conditions, etc. Extensive use of such a materials irradiation facility is expected for fundamental materials irradiation researches and R and D of nuclear energy systems such as accelerator-driven incineration plant for long-lifetime nuclear waste. In this paper, outline concept of the materials irradiation facility, characteristics of the irradiation field, preliminary technical evaluation of target to generate spallation neutrons, and materials researches expected for Neutron Science Research program are described. (author)

The weapons effect

NARCIS (Netherlands)

Benjamin, Arlin James; Bushman, Brad J.

In some societies, weapons are plentiful and highly visible. This review examines recent trends in research on the weapons effect, which is the finding that the mere presence of weapons can prime people to behave aggressively. The General Aggression Model provides a theoretical framework to explain

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.

Polarized neutrons for Australian scientific research

International Nuclear Information System (INIS)

Kennedy, Shane J.

2005-01-01

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

Neutron bomb and European defense

International Nuclear Information System (INIS)

Sweet, W.

1980-01-01

France's development of the controversial neutron bomb is in line with the US goal of flexible response to a Soviet threat in Europe. US neutron bomb production is on a standby basis pending agreement among the North Atlantic Treaty Organization (NATO) members for deployment. Controversy over the bomb centers on its anti-personnel nature, which many see as immoral in comparison with weapons that primarily damage property. Opponents also see it as lowering the nuclear threshold and increasing the chance of nuclear war. Supporters view the bomb as a tactical weapon to be used on a limited scale as a last resort. If Germany's Chancellor Schmidt fails to negotiate a limit to European nuclear arms deployment with the Soviet Union, neutron-bomb production in the US and France will most likely proceed. The prospects for including European nuclear weapons in the Strategic Arms Limitation Talks (SALT) III are jeopardized by the Soviet invasion of Afghanistan and the failure of an early SALT II ratification. 17 references

Basic research of neutron radiography using cold neutron beam

International Nuclear Information System (INIS)

Oda, Masahiro; Tamaki, Masayoshi; Tasaka, Kanji

1995-01-01

As the result of demanding high quality images, now the nuclear reactors which can supply stably intense neutron beam have become the most general neutron source for radiography. For the purpose, mostly thermal neutrons have been used, but it is indispensable to use other neutrons than thermal neutrons for advancing neutron radiography technology and expanding the application fields. The radiography using cold neutrons is most behind in the development because the suitable neutron source was not available in Japan. The neutron sources for exclusively obtaining intense cold neutron beam were installed in the Kyoto University reactor in 1986 and in the JRR-3M of Japan Atomic Energy Research Institute in 1991. Basically as neutron energy lowers, the cross section of substances increases. In certain crystalline substances, the Bragg cutoff arises. The removal of scattered neutrons, the measurement of parallelism of beam and the relation of the thickness of objects with the transmissivity of cold neutrons are described. The imaging by TV method and the cold neutron CT in the CNRF and the simplified neutron CT by film method are reported. (K.I.)

The immediate need for US universities to promote research related to a nuclear-weapon-free world

International Nuclear Information System (INIS)

Ionno, S.

1999-01-01

If disarmament is a goal, then the requisite skills must be fostered in academic research. Too many students today view nuclear weapons as a non-issue. It is crucial that those people in positions of influence encourage more young people to explore in-depth the political, scientific, and social changes that a nuclear-weapon-free world will require. The data presented are based on a search of nuclear-weapons-related keywords in the UMI Dissertation Abstracts Database which includes work from over 1000 North American graduate schools and European Universities. The search was focused on US Phd dissertations between 1987 and 1996. There was no PhDs focused on issues such as: zero-level nuclear-weapons-free world; nuclear-weapons-free zones; decreasing nuclear alert status; a nuclear weapons convention; no-first-use or-no use against non-nuclear-weapons-states; START; French nuclear weapons; a possible 'Eurobomb'; peace groups outside the USA, UK, and Germany; nuclear-weapons secrecy; funding disarmament; the role od UN in a nuclear-weapons-free world; an so on

Radiation transport and shielding information, computer codes, and nuclear data for use in CTR neutronics research and development

International Nuclear Information System (INIS)

Santoro, R.T.; Maskewitz, B.F.; Roussin, R.W.; Trubey, D.K.

1976-01-01

The activities of the Radiation Shielding Information Center (RSIC) of the Oak Ridge National Laboratory are being utilized in support of fusion reactor technology. The major activities of RSIC include the operation of a computer-based information storage and retrieval system, the collection, packaging, and distribution of large computer codes, and the compilation and dissemination of processed and evaluated data libraries, with particular emphasis on neutron and gamma-ray cross-section data. The Center has acquired thirteen years of experience in serving fission reactor, weapons, and accelerator shielding research communities, and the extension of its technical base to fusion reactor research represents a logical progression. RSIC is currently working with fusion reactor researchers and contractors in computer code development to provide tested radiation transport and shielding codes and data library packages. Of significant interest to the CTR community are the 100 energy group neutron and 21 energy group gamma-ray coupled cross-section data package (DLC-37) for neutronics studies, a comprehensive 171 energy group neutron and 36 energy group gamma-ray coupled cross-section data base with retrieval programs, including resonance self-shielding, that are tailored to CTR application, and a data base for the generation of energy-dependent atomic displacement and gas production cross sections and heavy-particle-recoil spectra for estimating radiation damage to CTR structural components

Research trends in neutron physics

International Nuclear Information System (INIS)

Lynn, J.E.

1976-01-01

The trends in neutron research are discussed from the viewpoints of development of pulsed neutron sources, the ingenuity of specialization of instrumentation and experimental techniques, and research programs. The latter comprise the large and still expanding requirements of nuclear data for nuclear power technology, the requirements of other fundamental sciences, and the experimental and theoretical developments required for a more fundamental understanding of the subject of neutron and related nuclear reactions itself. The general conclusion is that high energy resolution coupled with high intensity for detecting weak reactions provides the key to further progress, and that (provided financial limitations do not stifle the further development of experimental facilities, particularly neutron sources) the subject of neutron physics still has a long and fruitful future

Verifying the transition from low levels of nuclear weapons to a nuclear weapon-free world. VERTIC research report no. 2

International Nuclear Information System (INIS)

Milne, T.; Wilson, H.

1999-01-01

The process of verifying the complete elimination of nuclear warheads in national stockpiles can be divided, conceptually, into four stages: first, comprehensive declarations of warhead and material inventories, as a base-line from which verified disarmament can proceed; second, the transfer of all nuclear weapons and weapons-grade fissile material into bonded store; third, demilitarisation measures, such as to render warheads unusable without disassembly and refabrication; fourth, dismantlement of warheads and disposition of fissile material. Many of the technologies and technologies and techniques needed for verifying the elimination of nuclear warheads have been worked out at a general level, largely in US studies. While it is essential that these techniques are refined and improved, what is most important now, if disarmament is to proceed expeditiously, is for each of the nuclear weapon states (NWS) themselves to study the central verification problems and requirements in order to identify particular techniques and approaches that meet their needs. As yet there is no system of integrated data exchange and verification that any of the NWS is willing to endorse. Each of the NWS should give detailed consideration to the logistics of dismantling the warheads in their respective stockpiles, including, for example, the practicalities of accommodating international verification at their potential dismantlement facilities. Each of the NWS might usefully review exactly which details of warhead design and construction have to remain secret in the course of the disarmament process, in the first place from one another, and second from the IAEA or any other international body that might be involved in international disarmament arrangements. Introducing transparency and verification into national nuclear weapons programmes might have a significant financial cost. Research and ingenuity might reduce this cost, however, and early investments in these fields, with sharing of

The Los Alamos Neutron Science Center Spallation Neutron Sources

International Nuclear Information System (INIS)

Nowicki, Suzanne F.; Wender, Stephen A.; Mocko, Michael

2017-01-01

The Los Alamos Neutron Science Center (LANSCE) provides the scientific community with intense sources of neutrons, which can be used to perform experiments supporting civilian and national security research. These measurements include nuclear physics experiments for the defense program, basic science, and the radiation effect programs. This paper focuses on the radiation effects program, which involves mostly accelerated testing of semiconductor parts. When cosmic rays strike the earth's atmosphere, they cause nuclear reactions with elements in the air and produce a wide range of energetic particles. Because neutrons are uncharged, they can reach aircraft altitudes and sea level. These neutrons are thought to be the most important threat to semiconductor devices and integrated circuits. The best way to determine the failure rate due to these neutrons is to measure the failure rate in a neutron source that has the same spectrum as those produced by cosmic rays. Los Alamos has a high-energy and a low-energy neutron source for semiconductor testing. Both are driven by the 800-MeV proton beam from the LANSCE accelerator. The high-energy neutron source at the Weapons Neutron Research (WNR) facility uses a bare target that is designed to produce fast neutrons with energies from 100 keV to almost 800 MeV. The measured neutron energy distribution from WNR is very similar to that of the cosmic-ray-induced neutrons in the atmosphere. However, the flux provided at the WNR facility is typically 5×107 times more intense than the flux of the cosmic-ray-induced neutrons. This intense neutron flux allows testing at greatly accelerated rates. An irradiation test of less than an hour is equivalent to many years of neutron exposure due to cosmic-ray neutrons. The low-energy neutron source is located at the Lujan Neutron Scattering Center. It is based on a moderated source that provides useful neutrons from subthermal energies to ~100 keV. The characteristics of these sources

The Los Alamos Neutron Science Center Spallation Neutron Sources

Science.gov (United States)

Nowicki, Suzanne F.; Wender, Stephen A.; Mocko, Michael

The Los Alamos Neutron Science Center (LANSCE) provides the scientific community with intense sources of neutrons, which can be used to perform experiments supporting civilian and national security research. These measurements include nuclear physics experiments for the defense program, basic science, and the radiation effect programs. This paper focuses on the radiation effects program, which involves mostly accelerated testing of semiconductor parts. When cosmic rays strike the earth's atmosphere, they cause nuclear reactions with elements in the air and produce a wide range of energetic particles. Because neutrons are uncharged, they can reach aircraft altitudes and sea level. These neutrons are thought to be the most important threat to semiconductor devices and integrated circuits. The best way to determine the failure rate due to these neutrons is to measure the failure rate in a neutron source that has the same spectrum as those produced by cosmic rays. Los Alamos has a high-energy and a low-energy neutron source for semiconductor testing. Both are driven by the 800-MeV proton beam from the LANSCE accelerator. The high-energy neutron source at the Weapons Neutron Research (WNR) facility uses a bare target that is designed to produce fast neutrons with energies from 100 keV to almost 800 MeV. The measured neutron energy distribution from WNR is very similar to that of the cosmic-ray-induced neutrons in the atmosphere. However, the flux provided at the WNR facility is typically 5×107 times more intense than the flux of the cosmic-ray-induced neutrons. This intense neutron flux allows testing at greatly accelerated rates. An irradiation test of less than an hour is equivalent to many years of neutron exposure due to cosmic-ray neutrons. The low-energy neutron source is located at the Lujan Neutron Scattering Center. It is based on a moderated source that provides useful neutrons from subthermal energies to ∼100 keV. The characteristics of these sources, and

Characteristics of the WNR: a pulsed spallation neutron source

International Nuclear Information System (INIS)

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

Neutron bomb and European defense

Energy Technology Data Exchange (ETDEWEB)

Sweet, W.

1980-08-15

France's development of the controversial neutron bomb is in line with the US goal of flexible response to a Soviet threat in Europe. US neutron bomb production is on a standby basis pending agreement among the North Atlantic Treaty Organization (NATO) members for deployment. Controversy over the bomb centers on its anti-personnel nature, which many see as immoral in comparison with weapons that primarily damage property. Opponents also see it as lowering the nuclear threshold and increasing the chance of nuclear war. Supporters view the bomb as a tactical weapon to be used on a limited scale as a last resort. If Germany's Chancellor Schmidt fails to negotiate a limit to European nuclear arms deployment with the Soviet Union, neutron-bomb production in the US and France will most likely proceed. The prospects for including European nuclear weapons in the Strategic Arms Limitation Talks (SALT) III are jeopardized by the Soviet invasion of Afghanistan and the failure of an early SALT II ratification. 17 references. (DCK)

Semiconductor research with reactor neutrons

International Nuclear Information System (INIS)

Kimura, Itsuro

1992-01-01

Reactor neutrons play an important role for characterization of semiconductor materials as same as other advanced materials. On the other hand reactor neutrons bring about not only malignant irradiation effects called radiation damage, but also useful effects such as neutron transmutation doping and defect formation for opto-electronics. Research works on semiconductor materials with the reactor neutrons of the Kyoto University Reactor (KUR) are briefly reviewed. In this review, a stress is laid on the present author's works. (author)

Biomedical neutron research at the Californium User Facility for neutron science

International Nuclear Information System (INIS)

Martin, R.C.; Byrne, T.E.; Miller, L.F.

1997-01-01

The Californium User Facility for Neutron Science has been established at Oak Ridge National Laboratory (ORNL). The Californium User Facility (CUF) is a part of the larger Californium Facility, which fabricates and stores compact 252 Cf neutron sources for worldwide distribution. The CUF can provide a cost-effective option for research with 252 Cf sources. Three projects at the CUF that demonstrate the versatility of 252 Cf for biological and biomedical neutron-based research are described: future establishment of a 252 Cf-based neutron activation analysis system, ongoing work to produce miniature high-intensity, remotely afterloaded 252 Cf sources for tumor therapy, and a recent experiment that irradiated living human lung cancer cells impregnated with experimental boron compounds to test their effectiveness for boron neutron capture therapy

Characteristics of a Portable Neutron Generator

International Nuclear Information System (INIS)

Jin, Jeong-Tae; Oh, Byung-Hoon; Chang, Dae-Sik; In, Sang-Yeol; Huh, Sung-Ryul; Hong, Kwang-Pyo

2015-01-01

Neutron generators can be excellent tools for materials analysis, explosive material detection, nuclear weapon detection, and high quality radiography. D + D : 3He + n (2.5 MeV) D + T : 4He + n (14 MeV) Recent commercial neutron generators, fast neutron yield from 10 7 to 10 11 n/s, are produced by several companies and research groups around the world. But limited life time, high price, and frequent troubles make it difficult to develop related application systems by domestic companies or research groups. To remove such problems, it is necessary to develop our own domestic neutron generators. In this presentation, the design and experimental results on the developed small neutron generator are summarized. Experiments on deuterium beam extraction and fast neutron measurement by injecting deuterium beams on a drive-in target are executed. The stable deuterium beam of the energy higher than 100 keV was achieved by introducing metal cover which reduces the effect of metal-vacuum-insulator triple junction. The neutron flux of 5 n/s is measured by RadEye GN gamma Neutron (Thermo scientific) detector with about 200 mm distance and insertion of 40 mm PE plate between neutron source and the detector. The precise detector calibration is not carried out yet, so more detailed experimental results will be summarized at the presentation

Characteristics of a Portable Neutron Generator

Energy Technology Data Exchange (ETDEWEB)

Jin, Jeong-Tae; Oh, Byung-Hoon; Chang, Dae-Sik; In, Sang-Yeol; Huh, Sung-Ryul; Hong, Kwang-Pyo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2015-10-15

Neutron generators can be excellent tools for materials analysis, explosive material detection, nuclear weapon detection, and high quality radiography. D + D : 3He + n (2.5 MeV) D + T : 4He + n (14 MeV) Recent commercial neutron generators, fast neutron yield from 10{sup 7} to 10{sup 11} n/s, are produced by several companies and research groups around the world. But limited life time, high price, and frequent troubles make it difficult to develop related application systems by domestic companies or research groups. To remove such problems, it is necessary to develop our own domestic neutron generators. In this presentation, the design and experimental results on the developed small neutron generator are summarized. Experiments on deuterium beam extraction and fast neutron measurement by injecting deuterium beams on a drive-in target are executed. The stable deuterium beam of the energy higher than 100 keV was achieved by introducing metal cover which reduces the effect of metal-vacuum-insulator triple junction. The neutron flux of 5 n/s is measured by RadEye GN gamma Neutron (Thermo scientific) detector with about 200 mm distance and insertion of 40 mm PE plate between neutron source and the detector. The precise detector calibration is not carried out yet, so more detailed experimental results will be summarized at the presentation.

New opportunities in neutron capture research using advanced pulsed neutron sources

International Nuclear Information System (INIS)

Bowman, C.D.

1987-08-01

The extraordinary neutron intensities available from the new spallation pulsed neutron sources open up exciting opportunities for basic and applied research in neutron nuclear physics. Prospective experiments are reviewed with particular attention to those with a strong connection to capture gamma-ray spectroscopy

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.)

Physics studies of weapons plutonium disposition in the IFR closed fuel cycle

International Nuclear Information System (INIS)

Hill, R.N.; Wade, D.C.; Liaw, J.R.; Fujita, E.K.

1994-01-01

The core performance impact of weapons plutonium introduction into the IFR closed fuel cycle is investigated by comparing three disposition scenarios: a power production mode, a moderate destruction mode, and a maximum destruction mode all at a constant heat rating of 840 MWt. For each scenario, two fuel cycle models are evaluated: cores using weapons material as the sole source of transuranics in a once-through mode, and recycle corns using weapons material only as required for a make-up feed. Calculated results include mass flows, detailed isotopic distributions, neutronic performance characteristics, and reactivity feedback coefficients. In general, it is shown that weapons plutonium feed does not have an adverse impact on IFR core performance characteristics

Neutrons and sustainable energy research

International Nuclear Information System (INIS)

Peterson, V.

2009-01-01

Full text: Neutron scattering is essential for the study of sustainable energy materials, including the areas of hydrogen research (such as its separation, storage, and use in fuel-cells) and energy transport (such as fuel-cell and battery materials). Researchers at the Bragg Institute address critical questions in sustainable energy research, with researchers providing a source of expertise for external collaborators, specialist analysis equipment, and acting as a point of contact for the study of sustainable energy materials using neutron scattering. Some recent examples of sustainable energy materials research using neutron scattering will be presented. These examples include the storage of energy, in the form of hydrogen through a study of its location in and interaction with new porous hydrogen storage materials [1-3] and in battery materials through in-situ studies of structure during charge-discharge cycling, and use of energy in fuel cells by studying proton diffusion through fuel cell membranes.

Biomedical neutron research at the Californium User Facility for Neutron Science

International Nuclear Information System (INIS)

Martin, R.C.; Byrne, T.E.; Miller, L.F.

1998-01-01

The Californium User Facility for Neutron Science has been established at Oak Ridge National Laboratory (ORNL). The Californium User Facility (CUF) is a part of the larger Californium Facility, which fabricates and stores compact 252 Cf neutron sources for worldwide distribution. The CUF can provide a cost-effective option for research with 252 Cf sources. Three projects at the CUF that demonstrate the versatility of 252 Cf for biological and biomedical neutron-based research are described: future establishment of a 252 Cf-based neutron activation analysis system, ongoing work to produce miniature high-intensity, remotely afterloaded 252 Cf sources for tumor therapy, and a recent experiment that irradiated living human lung cancer cells impregnated with experimental boron compounds to test their effectiveness for boron neutron capture therapy. (author)

Narrow beam neutron dosimetry.

Science.gov (United States)

Ferenci, M Sutton

2004-01-01

Organ and effective doses have been estimated for male and female anthropomorphic mathematical models exposed to monoenergetic narrow beams of neutrons with energies from 10(-11) to 1000 MeV. Calculations were performed for anterior-posterior, posterior-anterior, left-lateral and right-lateral irradiation geometries. The beam diameter used in the calculations was 7.62 cm and the phantoms were irradiated at a height of 1 m above the ground. This geometry was chosen to simulate an accidental scenario (a worker walking through the beam) at Flight Path 30 Left (FP30L) of the Weapons Neutron Research (WNR) Facility at Los Alamos National Laboratory. The calculations were carried out using the Monte Carlo transport code MCNPX 2.5c.

Neutron spectrum at 900 from 800 MeV (p,n) reactions on a Ta target

International Nuclear Information System (INIS)

Howe, S.D.; Lisowski, P.W.; King, N.S.P.; Russell, G.J.; Donnert, H.J.

1979-01-01

The neutron time-of-flight spectrum produced by a thick tantalum target bombarded by 800-MeV protons was measured at an angle of 90 0 . The data were taken at the Weapons Neutron Research facility by use of a cylindrical Ta target with a radius of 1.27 cm and a length of 15 cm. An NE-213 liquid scintillator was used to detect the neutrons over an energy range of 0.5 to 350 MeV. The neutron yield is presented and compared to a intranuclear-cascade/evaporation model prediction. 3 figures

Crocodile years: the traditional image of science and physical scientists' participation in weapons research

Energy Technology Data Exchange (ETDEWEB)

Crews, R.J.

1985-01-01

This thesis examines one dimension of the relationship between science and the arms race. More specifically, it develops and empirically examines a theoretical model of the relationship between the social demand for defense-related and weapons research, traditional scientific values related to the worldview of classical physics, and differential participation by physical scientists in such research. The theoretical model suggests that an antiquated traditional image of science exists, and that it may explain, in part, participation by physical scientists in defense-related or weapons research. Two major hypotheses are suggested by the model: first, that a constellation of values representing a traditional image of science obtains today among young physical scientists; and second, that those who currently engage (or are willing to engage) in defense-related or weapons research are more likely to agree with the values implicit in the traditional image of science than those who do not (or would not) engage in such research. The theoretical model is located within the sociologies of knowledge and science. This study includes chapters that provide an overview of the literature of these subdisciplines. This investigation concludes with an empirical examination of the model and hypotheses.

Intense neutron sources for cancer treatment

International Nuclear Information System (INIS)

Anon.

1977-01-01

Significant progress has been made in the development of small, solid-target, pulsed neutron sources for nuclear weapons applications. The feasibility of using this type of neutron source for cancer treatment is discussed. Plans for fabrication and testing of such a source is briefly described

Stellarator fusion neutronics research in Australia

International Nuclear Information System (INIS)

Zimin, S.; Cross, R.C.

1997-01-01

The new status of the H-INF Heliac Stellaralor as a National Facility and the signed international Implementing Agreement on 'Collaboration in the Development of the Stellarator Concept' represents a significant encouragement for further fusion research in Australia. In this report the future of fusion research in Australia is discussed with special attention being paid to the importance of Stellarator power plant studies and in particular stellarator fusion neutronics. The main differences between tokamak and stellarator neutronics analyses are identified, namely the neutron wall loading, geometrical modelling and total heating in in-vessel reactor components including toroidal field (TF) coils. Due to the more complicated nature of stellarator neutronics analyses, simplified approaches to fusion neutronics already developed for tokamaks are expected to be even more important and widely used for designing a Conceptual Stellarator Power Plant

Radiation transport and shielding information, computer codes, and nuclear data for use in CTR neutronics research and development

International Nuclear Information System (INIS)

Santoro, R.T.; Maskewitz, B.F.; Roussin, R.W.; Trubey, D.K.

1976-01-01

The activities of the Radiation Shielding Information Center (RSIC) of the Oak Ridge National Laboratory are being utilized in support of fusion reactor technology. The major activities of RSIC include the operation of a computer-based information storage and retrieval system, the collection, packaging, and distribution of large computer codes, and the compilation and dissemination of processed and evaluated data libraries, with particular emphasis on neutron and gamma-ray cross-section data. The Center has acquired thirteen years of experience in serving fission reactor, weapons, and accelerator shielding research communities, and the extension of its technical base to fusion reactor research represents a logical progression. RSIC is currently working with fusion reactor researchers and contractors in computer code development to provide tested radiation transport and shielding codes and data library packages. Of significant interest to the CTR community are the 100 energy group neutron and 21 energy group gamma-ray coupled cross-section data package (DLC-37) for neutronics studies, a comprehensive 171 energy group neutron and 36 energy group gamma-ray coupled cross-section data base with retrieval programs, including resonance self-shielding, that are tailored to CTR application, and a data base for the generation of energy-dependent atomic displacement and gas production cross sections and heavy-particle-recoil spectra for estimating radiation damage to CTR structural components. Since 1964, the Center has been involved in the international exchange of information, encouraged and supported by both government and interagency agreements; and to achieve an equally viable and successful program in fusion research, the reciprocal exchange of CTR data and computing technology is encouraged and welcomed

Instruments and accessories for neutron scattering research

International Nuclear Information System (INIS)

Ishii, Yoshinobu; Morii, Yukio

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)

Physical effects of thermonuclear weapons

International Nuclear Information System (INIS)

Rotblat, J.

1984-01-01

The detonation of nuclear weapons gives rise to the following: blast wave; thermal wave; initial radiation (neutrons and gamma-rays); local radioactive fallout; global radioactive fallout; electromagnetic pulse; atmospheric disturbances. Some of these phenomena became known only as a result of the use or testing of bombs and are not as yet fully understood. They produce physical or biological effects or both, almost all of which are directly detrimental to human health. Some are likely to damage the environment

Fruits of neutron research

International Nuclear Information System (INIS)

Krause, C.

1994-01-01

Car windshields that don't break during accidents and jets that fly longer without making a refueling stop. Compact discs, credit cards, and pocket calculators. Refrigerator magnets and automatic car window openers. Beach shoes, food packaging, and bulletproof vests made of tough plastics. The quality and range of consumer products have improved steadily since the 1970s. One of the reasons: neutron research. Industries, employing neutron scattering techniques, to study materials properties, to act as diagnostics in tracing system performance, or as sources for radioactive isotopes used in medical fields for diagnostics or treatment, have all benefited from the fruits of advanced work with neutron sources

Neutron beam facilities at the Australian Replacement Research Reactor

International Nuclear Information System (INIS)

Kennedy, Shane; Robinson, Robert; Hunter, Brett

2001-01-01

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 14 n/cm 2 /sec and a liquid D 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)

Achievement and development of neutron beam utilization in research reactors

International Nuclear Information System (INIS)

Isshiki, Masahiko

1996-01-01

Especially regarding the neutron beam experiment in Japan, the basic research has been developed by utilizing the JRR-2 of Japan Atomic Energy Research Institute and the KUR of Kyoto University over long years. Now, the JRR-3M of JAERI was revived as a high performance, general purpose reactor, and bears important roles as the neutron beam experiment center in Japan. Thanks to one of the most powerful reactor neutron sources in the world and the cold neutron source, the environment of research was greatly improved, and the excellent results of researches began to be reported. The discovery of neutrons by Chadwick and the history of the related researches are described. As neutron sources, radioisotopes, accelerators and nuclear reactors are properly used corresponding to purposes. As the utilization of research reactors for neutron sources, the utilization for irradiation and neutron beam experiment are carried out. The outline of the research reactor JRR-3M is explained. The state of utilization in neutron scattering experiment, neutron radiography, prompt γ-ray analysis and the medical irradiation of neutrons is reported. (K.I.)

Neutron diagnostic investigations with a research reactor

International Nuclear Information System (INIS)

Harms, A.A.

1977-01-01

Some aspects of the use of neutron transmission analysis in applied research, as pursued at McMaster University (Canada), are examined. Examples considered are void measurements in two-phase flow, neutron conversion enhancement in neutron radiography, reconstruction of interior bulk heterogenities in solids and temperature sensing with neutrons. (author)

Research on neutron radiography in Research Reactor Institute, Kyoto University and activities related to it

International Nuclear Information System (INIS)

Fujine, Shigenori; Yoneda, Kenji

1994-01-01

The research on neutron radiography in Research Reactor Institute, Kyoto University was begun in 1974 using the E-2 experimental hole which was designed for neutron irradiation. It was reconstructed for the excellent performance as neutron radiography facility by fixing aluminum plugs, a collimator and so on. The research activities thereafter are briefly described. In 1989, the cold neutron facility was installed in the graphite thermal neutron facility, and the experiment on cold neutron radiography became feasible. The reactor in Kyoto University is of the thermal output of 5 MW, and is put to the joint utilization by universities and research institutes in whole Japan. The experimental items carried out so far are enumerated. At present, the main subjects of research are the development of the standard for establishing image evaluation method, the analysis of gas-liquid two-phase flow, the construction of the data base for the literatures and images of neutron radiography, the application of cold neutron radiography, the development of the imaging method using fast neutrons and so on. The thermal neutron radiography and the cold neutron radiography facilities of Kyoto University research reactor are described. The research and activities at Kyoto University research reactor and the investigation of problems are reported. (K.I.) 56 refs

New experimental research stand SVICKA neutron field analysis using neutron activation detector technique

Science.gov (United States)

Varmuza, Jan; Katovsky, Karel; Zeman, Miroslav; Stastny, Ondrej; Haysak, Ivan; Holomb, Robert

2018-04-01

Knowledge of neutron energy spectra is very important because neutrons with various energies have a different material impact or a biological tissue impact. This paper presents basic results of the neutron flux distribution inside the new experimental research stand SVICKA which is located at Brno University of Technology in Brno, Czech Republic. The experiment also focused on the investigation of the sandwich biological shielding quality that protects staff against radiation effects. The set of indium activation detectors was used to the investigation of neutron flux distribution. The results of the measurement provide basic information about the neutron flux distribution inside all irradiation channels and no damage or cracks are present in the experimental research stand biological shielding.

Weapons grade plutonium disposition in PWR, CANDU and FR

International Nuclear Information System (INIS)

Deplech, M.; Tommasi, J.; Zaetta, A.

2000-01-01

In the frame work of the AIDA/MOX phase I/I/ program (1994-1997) between France and Russia, the disposition of plutonium in reactors was studied. The LWR (Light Water Reactor), FR (Fast reactors), CANDU (Heavy Water Reactors), HTR (High Temperature Reactors) options for using excess dismantled weapons plutonium for peaceful commercial nuclear power generating purposes offer some advantages over the remaining options (storage). The AIDA/MOX phase 1 program covers different topics, among which are the neutronic aspects of loading reactors with weapons-grade plutonium. The conclusions are that the weapon plutonium consumption is similar in the different type of reactors. However, the use of inert matrices allows to increase the mass balance for a same denaturing level. The use of Thorium as a matrix or special isotopes to increase the proliferation resistance prove to be insufficient. (author)

Neutrons for research and training

International Nuclear Information System (INIS)

Villa, M.; Bichler, M.; Hameed, F.; Jericha, E.; Steinhauser, G.; Sterba, J.H.; Boeck, H.

2008-01-01

The 250 kW TRIGA Mark-II reactor operates since March 1962 at the Atomic Institute in Vienna, Austria. Its main tasks are nuclear education and training in the fields of neutron- and solid state physics, nuclear technology, reactor safety, radiochemistry, radiation protection and dosimetry, and low temperature physics and fusion research. Academic research is carried out by students in the above mentioned fields co-ordinated and supervised by about 80 staff members with the aim of a master- or PhD degree in one of the above mentioned areas. During the past 15 years about 600 students graduated through the Atomic Institute. The paper focuses on the results in neutron- and solid state physics and the co-operation between the low power TRIGA reactor with high flux neutron sources in Europe. The use of the TRIGA reactor at the Atomic Institute in Vienna as an irradiation facility in neutron activation analysis has a remarkable history. Present research work includes the recent determination of the precise half-life of 182 Hf and the participation in an archaeological long-term research programme. The TRIGA reactor operated by the Atomic Institute is now the only nuclear facility in Austria. Although Austria follows a dedicated anti-nuclear policy, the Atomic Institute enjoys a relatively undisturbed nuclear freedom in its nuclear activities. This allows us to use the research reactor not only for academic training but also for international training courses especially in nuclear technology. The presentation will outline typical training programmes and summarizes the experience with international training courses. (authors)

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

International Nuclear Information System (INIS)

Mizumoto, Motoharu

1997-01-01

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)

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)

Neutron and gamma-ray transport experiments in liquid air

International Nuclear Information System (INIS)

Farley, W.E.

1976-01-01

Accurate estimates of neutron and gamma radiations from a nuclear explosion and their subsequent transport through the atmosphere are vital to nuclear-weapon employment studies: i.e., for determining safety radii for aircraft crews, casualty and collateral-damage risk radii for tactical weapons, and the kill range from a high-yield defensive burst for a maneuvering reentry vehicle. Radiation transport codes, such as the Laboratory's TARTNP, are used to calculate neutron and gamma fluences. Experiments have been performed to check and update these codes. Recently, a 1.3-m-radius liquid-air (21 percent oxygen) sphere, with a pulsed source of 14-MeV neutrons at its center, was used to measure the fluence and spectra of emerging neutrons and secondary gamma rays. Comparison of measured radiation dose with TARTNP showed agreement within 10 percent

On the research activities in reactor and neutron physics using the first egyptian research reactor

International Nuclear Information System (INIS)

Hassan, A.M.

2000-01-01

A review on the most important research activities in reactor and neutron physics using the first Egyptian Research Reactor (ET-RR-1) is given. An out look on: neutron cross-sections, neutron flux, neutron capture gamma-ray spectroscopy, neutron activation analysis, neutron diffraction and radiation shielding experiments, is presented

Neutron capture prompt gamma-ray activation analysis at the NIST cold neutron research facility

Energy Technology Data Exchange (ETDEWEB)

Lindstrom, R M; Zeisler, R; Vincent, D H; Greenberg, R R; Stone, C A; Mackey, E A [National Inst. of Standards and Technology, Gaithersburg, MD (United States); Anderson, D L [Food and Drug Administration, Washington, DC (United States); Clark, D D [Cornell Univ., Ithaca, NY (United States)

1993-01-01

An instrument for neutron capture prompt gamma-ray activation analysis (PGAA) has been constructed as part of the Cold Neutron Research Facility at the 20 MW National Institute of Standards and Technology Research Reactor. The neutron fluence rate (thermal equivalent) is 1.5*10[sup 8] n*cm[sup -2]*s[sup -] [sup 1], with negligible fast neutrons and gamma-rays. With compact geometry and hydrogen-free construction, the sensitivity is sevenfold better than an existing thermal instrument. Hydrogen background is thirtyfold lower. (author) 17 refs.; 2 figs.

Requirements of data acquisition and analysis for condensed matter studies at the weapons neutron research/proton storage ring facility

International Nuclear Information System (INIS)

Johnson, M.W.; Goldstone, J.A.; Taylor, A.D.

1982-11-01

With the completion of the proton storage ring (PSR) in 1985, the subsquent increase in neutron flux, and the continuing improvement in neutron scattering instruments, a significant improvement in data acquisition and data analysis capabilities will be required. A brief account of the neutron source is given together with the associated neutron scattering instruments. Based on current technology and operating instruments, a projection for 1985 to 1990 of the neutron scattering instruments and their main parameters are given. From the expected data rates and the projected instruments, the size of data storage is estimated and the user requirements are developed. General requirements are outlined with specific requirements in user hardware and software stated. A project time scale to complete the data acquisition and analysis system by 1985 is given

A proposal of neutron science research program

International Nuclear Information System (INIS)

Suzuki, Y.; Yasuda, H.; Tone, T.; Mizumoto, M.

1996-01-01

A conception of Neutron Science Research Program (NSRP) has been proposed in Japan Atomic Energy Research Institute (JAERI) since 1994 as a future big project. The NSRP aims at exploring new basic science and nuclear energy science by a high-intensity proton accelerator. It is a complex composed of a proton linac and seven research facilities with each different target system. The proton linac is required to supply the high-intensity proton beam with energy up to 1.5 GeV and current 10 mA on average. The scientific research facilities proposed, are as follows: Thermal/Cold Neutron Facility for the neutron scattering experiments, Neutron Irradiation Facility for materials science, Neutron Physics Facility for nuclear data measurement, OMEGA/Nuclear Energy Facility for nuclear waste transmutation and fuel breeding, Spallation RI Beam Facility for nuclear physics, Meson/Muon Facility for meson and muon physics and their applications and Medium Energy Beam Facility for accelerator technology development, medical use, etc. Research and development have been carried out for the components of the injector system of the proton linac; an ion source, an RFQ linac and a part of DTL linac. The conceptual design work and research and development activities for NSRP have been started in the fiscal year, 1996. Construction term will be divided into two phases; the completion of the first phase is expected in 2003, when the proton linac will produce 1.5 GeV, 1 mA beam by reflecting the successful technology developments. (author)

Neutron scattering in applied research: possibilities for medium-flux research reactors

International Nuclear Information System (INIS)

Reijonen, H.

1977-01-01

The possibilities for neutron scattering techniques in applied research are reviewed. The areas covered are magnetism, determination of hydrogen self-diffusion constants and ionic mobility in superionic conductors, liquid crystals, molecular solids, polymers, surface chemistry and catalysts, colloids biology, physical metallurgy and neutron diagnostics. Established applications and new proposals for research projects are presented in various degrees of detail. Small angle scattering techniques, physical metallurgy and biology were identified as having particular potential. Prospective users should be realistically informed of the possibilities of neutron scattering techniques. (author)

Condensed matter and materials research using neutron diffraction and spectroscopy: reactor and pulsed neutron sources

International Nuclear Information System (INIS)

Bisanti, Paola; Lovesey, S.W.

1987-05-01

The paper provides a short, and partial view of the neutron scattering technique applied to condensed matter and materials research. Reactor and accelerator-based neutron spectrometers are discussed, together with examples of research projects that illustrate the puissance and modern applications of neutron scattering. Some examples are chosen to show the range of facilities available at the medium flux reactor operated by Casaccia ENEA, Roma and the advanced, pulsed spallation neutron source at the Rutherford Appleton Laboratory, Oxfordshire. (author)

Kartini Research Reactor prospective studies for neutron scattering application

International Nuclear Information System (INIS)

Widarto

1999-01-01

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 7 n/cm 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 9 n/cm 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)

Research of accelerator-based neutron source for boron neutron capture therapy

International Nuclear Information System (INIS)

Li Changkai; Ma Yingjie; Tang Xiaobin; Xie Qin; Geng Changran; Chen Da

2013-01-01

Background: 7 Li (p, n) reaction of high neutron yield and low threshold energy has become one of the most important neutron generating reactions for Accelerator-based Boron Neutron Capture Therapy (BNCT). Purpose Focuses on neutron yield and spectrum characteristics of this kind of neutron generating reaction which serves as an accelerator-based neutron source and moderates the high energy neutron beams to meet BNCT requirements. Methods: The yield and energy spectrum of neutrons generated by accelerator-based 7 Li(p, n) reaction with incident proton energy from 1.9 MeV to 3.0 MeV are researched using the Monte Carlo code-MCNPX2.5.0. And the energy and angular distribution of differential neutron yield by 2.5-MeV incident proton are also given in this part. In the following part, the character of epithermal neutron beam generated by 2.5-MeV incident protons is moderated by a new-designed moderator. Results: Energy spectra of neutrons generated by accelerator-based 7 Li(p, n) reaction with incident proton energy from 1.9 MeV to 3.0 MeV are got through the simulation and calculation. The best moderator thickness is got through comparison. Conclusions: Neutron beam produced by accelerator-based 7 Li(p, n) reaction, with the bombarding beam of 10 mA and the energy of 2.5 MeV, can meet the requirement of BNCT well after being moderated. (authors)

Neutron diffraction and oxide research

International Nuclear Information System (INIS)

Hunter, B.; Howard, C.J.; Kennedy, B.J.

1999-01-01

Oxide compounds form a large class of interesting materials that have a diverse range of mechanical and electronic properties. This diversity and its commercial implications has had a significant impact on physics research. This is particularly evident in the fields of superconductivity magnetoresistivity and ferroelectricity, where discoveries in the last 15 years have given rise to significant shifts in research activities. Historically, oxides have been studied for many years, but it is only recently that significant effort has been diverted to the study of oxide materials for their application to mechanical and electronic devices. An important property of such materials is the atomic structure, for the determination of which diffraction techniques are ideally suited. Recent examples of structure determinations using neutron diffraction in oxide based systems are high temperature superconductors, where oxygen defects are a key factor. Here, neutron diffraction played a major role in determining the effect of oxygen on the superconducting properties. Similarly, neutron diffraction has enjoyed much success in the determination of the structures of the manganate based colossal magnetoresistive (CMR) materials. In both these cases the structure plays a pivotal role in determining theoretical models of the electronic properties. The neutron scattering group at ANSTO has investigated several oxide systems using neutron powder diffraction. Two such systems are presented in this paper; the zirconia-based materials that are used as engineering materials, and the perovskite-based oxides that include the well known cuprate superconductors and the manganate CMR materials

Canadian Neutron Source (CNS): a research reactor solution for medical isotopes and neutrons for science

International Nuclear Information System (INIS)

Chapman, D.

2009-01-01

This presentation describes a dual purpose research facility at the University of Saskatchewan for Canada for the production of medical isotopes and neutrons for scientific research. The proposed research reactor is intended to supply most of Canada's medical isotope requirements and provide a neutron source for Canada's research community. Scientific research would include materials research, biomedical research and imaging.

Prompt fission neutron spectra from fission induced by 1 to 8 MeV neutrons on 235U and 239Pu using the double time-of-flight technique

International Nuclear Information System (INIS)

Noda, S.; Haight, R. C.; Nelson, R. O.; Devlin, M.; O'Donnell, J. M.; Chatillon, A.; Granier, T.; Belier, G.; Taieb, J.; Kawano, T.; Talou, P.

2011-01-01

Prompt fission neutron spectra from 235 U and 239 Pu were measured for incident neutron energies from 1 to 200 MeV at the Weapons Neutron Research facility (WNR) of the Los Alamos Neutron Science Center, and the experimental data were analyzed with the Los Alamos model for the incident neutron energies of 1-8 MeV. A CEA multiple-foil fission chamber containing deposits of 100 mg 235 U and 90 mg 239 Pu detected fission events. Outgoing neutrons were detected by the Fast Neutron-Induced γ-Ray Observer array of 20 liquid organic scintillators. A double time-of-flight technique was used to deduce the neutron incident energies from the spallation target and the outgoing energies from the fission chamber. These data were used for testing the Los Alamos model, and the total kinetic energy parameters were optimized to obtain a best fit to the data. The prompt fission neutron spectra were also compared with the Evaluated Nuclear Data File (ENDF/B-VII.0). We calculate average energies from both experimental and calculated fission neutron spectra.

A new neutron counter for fission research

Energy Technology Data Exchange (ETDEWEB)

Laurent, B., E-mail: benoit.laurent@cea.fr [CEA, DAM, DIF, F-91297 Arpajon (France); Granier, T.; Bélier, G.; Chatillon, A.; Martin, J.-F.; Taieb, J. [CEA, DAM, DIF, F-91297 Arpajon (France); Hambsch, F.-J. [EC-JRC Institute for Reference Materials and Measurements (IRMM), Retieseweg, 2440 Geel (Belgium); Tovesson, F.; Laptev, A.B.; Haight, R.C.; Nelson, R.O.; O' Donnell, J.M. [Los Alamos Neutron Science Center, Los Alamos National Laboratory, Los Alamos, NM 87545 (United States)

2014-05-01

A new neutron counter for research experiments on nuclear fission has been developed. This instrument is designed for the detection of prompt fission neutrons within relatively high levels of gamma and neutron background. It is composed of a set of {sup 3}He proportional counters arranged within a block of polyethylene which serves as moderator. The detection properties have been studied by means of Monte Carlo simulations and experiments with radioactive sources. These properties are confirmed by an experiment on neutron-induced fission of {sup 238}U at the WNR facility of the Los Alamos Neutron Science Center during which the mean prompt fission neutron multiplicity, or ν{sup ¯} has been measured from 1 to 20 MeV of incident neutron energy.

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.

Progress report from the Studsvik Neutron Research Laboratory 1987-89

International Nuclear Information System (INIS)

Dahlborg, U.; Ebbsjoe, I.; Holmqvist, B.

1993-01-01

The present publication contains information from activities at the Studsvik Neutron Research Laboratory (NFL) and the Department of Neutron Research. NFL is the base for the research activities at the Studvik reactors. It is administrated by the University of Uppsala and is established to facilitate reactor based research. The laboratory is intended to, in co-operation with institutes and departments at universities in Sweden, develop, construct and maintain experimental equipment for this kind of research and to make it available for scientists at Swedish universitites and, if possible, also to scientists outside the universities. The research at the Studsvik facilities has during 1989 been performed by groups from Uppsala University, Royal Institute of Technology in Stockholm, Chalmers Technical University, Gothenburg, and by scientists at NFL. The research program of the groups is divided into three main areas, scattering of thermal neutrons, nuclear chemistry and nuclear physics, and neutron capture radiography. The program for subatomic physics, especially neutron physics, at the Department for Neutron Research, Uppsala University has also staff permanently placed at NFL but they are in their research using the facilities at the The Svedberg Laboratory, Uppsala. In addition to supporting research NFL has also put substantial efforts on creating facilities for training of undergraduate students. Thus a facility for practical exercises in neutron physics, activation analysis and radiography has recently been installed at the R2-0 reactor as a collaboration between NFL, Dept. of Neutron Research, Upppsala and Department for Reactor Physics, KTH

Overview on neutron beam industry-focused strategic research in Malaysia

International Nuclear Information System (INIS)

Abdul Aziz Mohamed; Razali Kassim; Abdul Jalil Abdul Hamid; Azali Muhammad; Muhammad Rawi Mohd Zain; Azhar Azmi

2002-01-01

The TRIGA MARK II research reactor (RTP) at the Malaysian Institute for Nuclear Technology Research (MINT) was commissioned in July 1982. RTP is a 1 MW steady state reactor which being used for reactor training and research related to neutron. Since then various works have been performed to utilise the neutrons produced from this steady state reactor. Projects undertaken are the development and utilization of the neutron radiography (myNR) and small angle neutron scattering (mySANS) facilities. This poster highlights the recent status the above neutron beam facilities and their application in materials science and technology research and education. (Author)

Prerequisites for a nuclear weapons convention

International Nuclear Information System (INIS)

Liebert, W.

1999-01-01

A Nuclear Weapons Convention (NWC) would prohibit the research, development, production, testing, stockpiling, transfer, use and threat of use of nuclear weapons and would serve their total elimination.' In this fashion it follows the model laid out by the biological and chemical weapons conventions. The NWC would encompass a few other treaties and while replacing them should learn from their experiences. The Nuclear Weapons Convention should at some given point in the future replace the Non-Proliferation Treaty (NPT) and so resolve its contradictions and shortcomings. The main objectives of an NWC Would be: reduction of the nuclear arsenals of the 'five' nuclear weapons powers down to zero within a set of fixed periods of time; elimination of stockpiles of weapons-usable materials and, where existent, nuclear warheads in de-facto nuclear weapon and threshold states; providing assurance that all states will retain their non-nuclear status forever

FRM-II research neutron source commissioned

International Nuclear Information System (INIS)

Anon.

2004-01-01

On March 2, 2004, the Heinz Maier-Leibnitz research neutron source (FRM-II) generated neutrons for the first time. This marked the most important step on the way to using FRM-II for scientific purposes. On this occasion, this unique research facility in the world was dedicated in a ceremony attended by approximately 1000 representatives of politics, industry, and science. The keynote speaker, Federal Minister of the Interior Otto Schily; Bavarian Minister President Edmund Stoiber; Professor Claus Weyrich (Member of the Executive Board of Siemens AG); Dr. Thomas Goppel (Bavarian State Minister for Science, Research, and Arts); Professor Wolfgang A. Herman (President of the Technical University of Munich); Hannelore Gabor (2nd Mayor of the host municipality of Garching); and Professor Winfried Petry (Scientific Director of FRM-II) underlined the great importance of FRM-II for science, research, medicine, and technology. FRM-II will not only fill the 'neutron gap', but create extremely brilliant working conditions thanks to its considerably higher neutron flux compared to that of its predecessor, the legendary Atomic Egg. After the first conceptual design studies starting in 1980, the ground breaking ceremony in August 1996, and the third partial permit issued at Easter of 2003, a unique tool is now available for modern science and for medical and technical applications. (orig.) [de

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.

The Los Alamos Neutron Science Center

International Nuclear Information System (INIS)

Lisowski, Paul W.; Schoenberg, Kurt F.

2006-01-01

The Los Alamos Neutron Science Center, or LANSCE, uses the first truly high-current medium-energy proton linear accelerator, which operated originally at a beam power of 1 MW for medium-energy nuclear physics. Today LANSCE continues operation as one of the most versatile accelerator-based user facilities in the world. During eight months of annual operation, scientists from around the world work at LANSCE to execute an extraordinarily broad program of defense and civilian research. Several areas operate simultaneously. The Lujan Neutron Scattering Center (Lujan Center) is a moderated spallation source (meV to keV), the Weapons Neutron Research Facility (WNR) is a bare spallation neutron source (keV to 800 MeV), and a new ultra-cold neutron source will be operational in 2005. These sources give LANSCE the ability to produce and use neutrons with energies that range over 14 orders of magnitude. LANSCE also supplies beam to WNR and two other areas for applications requiring protons. In a proton radiography (pRad) area, a sequence of narrow proton pulses is transmitted through shocked materials and imaged to study dynamic properties. In 2005, LANSCE began operating a facility that uses 100-MeV protons to produce medical radioisotopes. To sustain a vigorous program beyond this decade, LANSCE has embarked on a project to refurbish key elements of the facility and to plan capabilities beyond those that presently exist

The advanced neutron source research and development plan

International Nuclear Information System (INIS)

Selby, D.L.

1995-08-01

The Advanced Neutron Source (ANS) is being designed as a user-oriented neutron research laboratory centered around the most intense continuous beams of thermal and subthermal neutrons in the world (an order of magnitude more intense than beams available from the most advanced existing reactors). The ANS will be built around a new research reactor of 330-MW fission power, producing an unprecedented peak thermal flux of >7 · 10 19 · m -2 · s -1 . Primarily a research facility, the ANS will accommodate more than 1000 academic, industrial, and government researchers each year. They will conduct basic research in all branches of science as well as applied research leading to better understanding of new materials, including high temperature super conductors, plastics, and thin films. Some 48 neutron beam stations will be set up in the ANS beam rooms and the neutron guide hall for neutron scattering and for fundamental and nuclear physics research. There also will be extensive facilities for materials irradiation, isotope production, and analytical chemistry. The top level work breakdown structure (WBS) for the project. As noted in this figure, one component of the project is a research and development (R ampersand D) program (WBS 1.1). This program interfaces with all of the other project level two WBS activities. Because one of the project guidelines is to meet minimum performance goals without relying on new inventions, this R ampersand D activity is not intended to produce new concepts to allow the project to meet minimum performance goals. Instead, the R ampersand D program will focus on the four objectives described

Polarized neutron scattering research: the beginning

International Nuclear Information System (INIS)

Mezei, F.

2005-01-01

The visionary idea of using neutron scattering for the study of magnetic phenomena in condensed matter was proposed by Bloch in 1936, mere 4 years after the neutron was discovered. It was based on one of the surprises the neutron presented the scientific community with: it is neutral, yet it has a magnetic moment, which latter was then not yet directly observed though. Although the first results proved to be mathematically wrong, due to a non-trivial ambiguity of classical electromagnetism theory, which could only be settled by neutron beam experiments 15 years later, the recognition lead to the advent of a most productive area of modern research, which culminated in the development of the powerful and sophisticated techniques of polarized neutron scattering. This recollection traces the early milestones of the development of the field in strong interaction between theory and experiment

The Advanced Neutron Source research and development plan

International Nuclear Information System (INIS)

Selby, D.L.

1992-01-01

The Advanced Neutron Source (ANS) is being designed as a user-oriented neutron research laboratory centered around the most intense continuous beams of thermal and subthermal neutrons in the world. The ANS will be built around a new research reactor of ∼ 330 MW fission power, producing an unprecedented peak thermal flux of > 7 x 10 19 M -2 · S -1 . Primarily a research facility, the ANS will accommodate more than 1000 academic, industrial, and government researchers each year. They will conduct basic research in all branches of science-as well as applied research-leading to better understanding of new materials, including high temperature super conductors, plastics, and thin films. Some 48 neutron beam stations will be set up in the ANS beam rooms and the neutron guide hall for neutron scattering and for fundamental and nuclear physics research. There also will be extensive facilities for materials irradiation, isotope production, and analytical chemistry. The R ampersand D program will focus on the four objectives: Address feasibility issues; provide analysis support; evaluate options for improvement in performance beyond minimum requirements; and provide prototype demonstrations for unique facilities. The remainder of this report presents (1) the process by which the R ampersand D activities are controlled and (2) a discussion of the individual tasks that have been identified for the R ampersand D program, including their justification, schedule and costs. The activities discussed in this report will be performed by Martin Marietta Energy Systems, Inc. (MMES) through the Oak Ridge National Laboratory (ORNL) and through subcontracts with industry, universities, and other national laboratories. It should be noted that in general a success path has been assumed for all tasks

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

Preliminary studies of microchannel plate photomultiplier tube neutron detectors for flight test applications

International Nuclear Information System (INIS)

Dolan, K.W.

1978-10-01

Electrical, mechanical, thermal, and neutron response data indicate that microchannel plate photomultiplier tubes are viable candidates as miniature, ruggedized neutron detectors for flight test applications in future weapon systems

Application of Neutron Tomography in Culture Heritage Research

International Nuclear Information System (INIS)

Mongy, T.

2014-01-01

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. - Highlights: • Neutron Tomography is an efficient tool in the field of Cultural Heritage research. • The full description of the ETRR-2 and state-of-the-art Neutron Tomography system. • Implementation of using computer software package in image reconstruction and imaging processing. • Precise measurements that was impossible by traditional methods. • The manuscript opens the door to investigate ancient Egyptian treasures

Effective delayed neutron fraction and prompt neutron lifetime of Tehran research reactor mixed-core

International Nuclear Information System (INIS)

Lashkari, A.; Khalafi, H.; Kazeminejad, H.

2013-01-01

Highlights: ► Kinetic parameters of Tehran research reactor mixed-core have been calculated. ► Burn-up effect on TRR kinetics parameters has been studied. ► Replacement of LEU-CFE with HEU-CFE in the TRR core has been investigated. ► Results of each mixed core were compared to the reference core. ► Calculation of kinetic parameters are necessary for reactivity and power excursion transient analysis. - Abstract: In this work, kinetic parameters of Tehran research reactor (TRR) mixed cores have been calculated. The mixed core configurations are made by replacement of the low enriched uranium control fuel elements with highly enriched uranium control fuel elements in the reference core. The MTR P C package, a nuclear reactor analysis tool, is used to perform the analysis. Simulations were carried out to compute effective delayed neutron fraction and prompt neutron lifetime. Calculation of kinetic parameters is necessary for reactivity and power excursion transient analysis. The results of this research show that effective delayed neutron fraction decreases and prompt neutron lifetime increases with the fuels burn-up. Also, by increasing the number of highly enriched uranium control fuel elements in the reference core, the prompt neutron lifetime increases, but effective delayed neutron fraction does not show any considerable change

New Organic Scintillators for Neutron Detection

Science.gov (United States)

2016-03-01

gamma rays. For heterogeneous or dense materials such as samples of metals , oxides , and nuclear waste, gamma ray attenuation can be too high to...highly enriched uranium and weapons grade plutonium. Neutrons and gamma rays are two signatures of these materials. Gamma ray detection techniques are... uranium ). Thus, neutron detection is an important component of the overall detection techniques used in identifying SNMs. Important requirements for

The advanced neutron source - A world-class research reactor facility

International Nuclear Information System (INIS)

Thompson, P.B.; Meek, W.E.

1993-01-01

The advanced neutron source (ANS) is a new facility being designed at the Oak Ridge National Laboratory that is based on a heavy-water-moderated reactor and extensive experiment and user-support facilities. The primary purpose of the ANS is to provide world-class facilities for neutron scattering research, isotope production, and materials irradiation in the United States. The neutrons provided by the reactor will be thermalized to produce sources of hot, thermal, cold, very cold, and ultracold neutrons usable at the experiment stations. Beams of cold neutrons will be directed into a large guide hall using neutron guide technology, greatly enhancing the number of research stations possible in the project. Fundamental and nuclear physics, materials analysis, and other research pro- grams will share the neutron beam facilities. Sufficient laboratory and office space will be provided to create an effective user-oriented environment

Terror weapons. Ridding the world of nuclear, biological and chemical weapons - Commission on mass destruction weapons

International Nuclear Information System (INIS)

Blix, H.; Journe, V.

2010-01-01

This book approaches in 8 chapters the ambitious challenge of ridding the world of all mass destruction weapons: 1 - re-launching disarmament; 2 - terror weapons: nature of threats and answers (weakness of traditional answers, counter-proliferation); 3 - nuclear weapons: preventing proliferation and terrorism, reducing threat and nuclear weapons number, from regulation to banning); 4 - biological or toxin weapons; 5 - chemical weapons; 6 - vectors, anti-missile defenses and space weapons; 7 - exports control, international assistance and non-governmental actors; 8 - respect, verification, enforcement and role of the United Nations. The recommendations and works of the Commission are presented in appendix together with the declaration adopted on April 30, 2009. (J.S.)

Neutronic simulation calculations to assess the proliferation resistance of nuclear technologies

International Nuclear Information System (INIS)

Englert, Matthias

2009-01-01

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.)

Research reactor of the future: The advanced neutron source

International Nuclear Information System (INIS)

Appleton, B.; West, C.

1994-01-01

Agents for cancer detection and treatment, stronger materials, better electronic gadgets, and other consumer and industrial products - these are assured benefits of a research reactor project proposed for Oak Ridge. Just as American companies have again assumed world leadership in producing semiconductor chips as well as cars and trucks, the United States is poised to retake the lead in neutron science by building and operating the $2.9 billion Advanced Neutron Source (ANS) research reactor by the start of the next century. In 1985, the neutron community, led by ORNL researchers, proposed a pioneering project, later called the ANS. Scheduled to begin operation in 2003, the ANS is seen not only as a replacement for the aging HFIR and HFBR but also as the best laboratory in the world for conducting neutron-based research

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

The neutron beam facility at the Australian replacement research reactor

International Nuclear Information System (INIS)

Hunter, B.; Kennedy, S.

1999-01-01

Full text: The Australian federal government gave ANSTO final approval to build a research reactor to replace HIFAR on August 25th 1999. The replacement reactor is to be a multipurpose reactor with a thermal neutron flux of 3 x 10 14 n.cm -2 .s -1 and having improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The replacement reactor will commence operation in 2005 and will cater for Australian scientific, industrial and medical needs well into the 21st century. The scientific capabilities of the neutron beams at the replacement reactor are being developed in consultation with representatives from academia, industry and government research laboratories to provide a facility for condensed matter research in physics, chemistry, materials science, life sciences, engineering and earth sciences. Cold, thermal and hot neutron sources are to be installed, and neutron guides will be used to position most of the neutron beam instruments in a neutron guide hall outside the reactor confinement building. Eight instruments are planned for 2005, with a further three to be developed by 2010. A conceptual layout for the neutron beam facility is presented including the location of the planned suite of neutron beam instruments. The reactor and all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by an accredited reactor builder in a turnkey contract. Tenders have been called for December 1999, with selection of contractor planned by June 2000. The neutron beam instruments will be developed by ANSTO and other contracted organisations in consultation with the user community and interested overseas scientists. The facility will be based, as far as possible, around a neutron guide hall that is be served by three thermal and three cold neutron guides. Efficient transportation of thermal and cold neutrons to the guide hall requires the use of modern super

Polonium-210 as Weapon for Mass Destruction

International Nuclear Information System (INIS)

Koteng, A.O.

2010-01-01

Properties of Po-210 make it possible for its use as weapon of mass destruction. Po-210 occurs naturally in minute quantities in the human body, in Uranium ore (< 0.1 mg Po-210 / ton ) and as a product of Radon-222 gas decay chain. Po-210 also occurs as deposition on vegetation (tobacco leaves). Po-210 is produced by bombardment of Bi-209 with neutrons in a nuclear reactor. Russia produces 8 grams per year for export to USA market

Steel research using neutron beam techniques. In-situ neutron diffraction, small-angle neutron scattering and residual stress analysis

International Nuclear Information System (INIS)

Sueyoshi, Hitoshi; Ishikawa, Nobuyuki; Yamada, Katsumi; Sato, Kaoru; Nakagaito, Tatsuya; Matsuda, Hiroshi; Arakaki, Yu; Tomota, Yo

2014-01-01

Recently, the neutron beam techniques have been applied for steel researches and industrial applications. In particular, the neutron diffraction is a powerful non-destructive method that can analyze phase transformation and residual stress inside the steel. The small-angle neutron scattering is also an effective method for the quantitative evaluation of microstructures inside the steel. In this study, in-situ neutron diffraction measurements during tensile test and heat treatment were conducted in order to investigate the deformation and transformation behaviors of TRIP steels. The small-angle neutron scattering measurements of TRIP steels were also conducted. Then, the neutron diffraction analysis was conducted on the high strength steel weld joint in order to investigate the effect of the residual stress distribution on the weld cracking. (author)

Neutrons in basic and applied nuclear research - a review

International Nuclear Information System (INIS)

Bhattacharya, Sailajananda

2013-01-01

Energetic neutron sources, both white and mono-energetic, are widely used In basic nuclear physics as well as various multidisciplinary research. Precise measurement of various neutron induced reaction cross-sections are crucial for the design and development of new generation of reactors, like accelerator driven subcritical systems, nuclear incinerators, etc. A review of some recent trends in neutron induced basic and applied nuclear research will be presented in this talk. (author)

On the utilization of neutron beams of research reactors in research and applications

International Nuclear Information System (INIS)

FAYEK, M.K.

2000-01-01

Nuclear research reactors are the most widely available neutron sources, and they are capable of producing very high fluxes of neutrons having a considerable range of energies, from a few MeV to 10 MeV. Therefore, these neutrons can be used in many fields of basic research and for applications in physics, chemistry, medicine, biology, etc. Experiments with research reactors over the last 50 years have laid the foundations of today's nuclear technology. In addition, research reactors continue to be utilized as facilities for testing materials and in training manpower for nuclear programs, because basic training on a research reactor provides an essential understanding of the nuclear process, and personnel become accustomed to work under the special conditions resulting from irradiation and contamination risks

Neutron beam facilities at the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Kim, S.

2003-01-01

The exciting development for Australia is the construction of a modern state-of-the-art 20-MW Replacement Research Reactor which is currently under construction to replace the aging reactor (HIFAR) at ANSTO in 2006. To cater for advanced scientific applications, the replacement reactor will provide not only thermal neutron beams but also a modern cold-neutron source moderated by liquid deuterium at approximately -250 deg C, complete with provision for installation of a hot-neutron source at a later stage. The latest 'supermirror' guides will be used to transport the neutrons to the Reactor Hall and its adjoining Neutron Guide Hall where a suite of neutron beam instruments will be installed. These new facilities will expand and enhance ANSTO's capabilities and performance in neutron beam science compared with what is possible with the existing HIFAR facilities, and will make ANSTO/Australia competitive with the best neutron facilities in the world. Eight 'leading-edge' neutron beam instruments are planned for the Replacement Research Reactor when it goes critical in 2006, followed by more instruments by 2010 and beyond. Up to 18 neutron beam instruments can be accommodated at the Replacement Research Reactor, however, it has the capacity for further expansion, including potential for a second Neutron Guide Hall. The first batch of eight instruments has been carefully selected in conjunction with a user group representing various scientific interests in Australia. A team of scientists, engineers, drafting officers and technicians has been assembled to carry out the Neutron Beam Instrument Project to successful completion. Today, most of the planned instruments have conceptual designs and are now being engineered in detail prior to construction and procurement. A suite of ancillary equipment will also be provided to enable scientific experiments at different temperatures, pressures and magnetic fields. This paper describes the Neutron Beam Instrument Project and gives

Frontier research at ANSTO with neutrons

International Nuclear Information System (INIS)

Gadd, G.E.

1999-01-01

In the last decade there has been considerable interest in the new form of carbon called fullerenes. Instead of hexagonal rings of carbon atoms arranged in planar sheets in graphite or a 3-D tetrahedral structure in diamond, this new form of carbon consists of closed cages of carbon atoms. The fullerene which has gained the most notoriety has been C 60, 'buckminsterfullerene' or 'buckyballs'. This has the geometry of a soccer ball where the carbon atoms correspond to the vertices of the seams. As well as these cages, long hollow tubes of carbon have also been formed called carbon nanotubes. These new carbon materials are poised to create new technologies in the fields of new materials, superconductors, electronic components, medical drugs, radioisotopes and radiotracers. At ANSTO the strategy of combining frontier research with the use of neutrons has been taken, to try and produce a useful end product related to our core activities. The research has focussed on trying to trap atoms (molecules) inside the centre of fullerene cages and in particular C 60 or in the solid fullerene lattice in the spaces between the closely packed cages. Neutrons from our research nuclear reactor serve a two-fold purpose. Neutron diffraction has been used to elucidate the crystal structure of the new materials followed by neutron irradiation to activate the trapped species for possible uses in radiopharmaceutical and industrial radiotracer applications. (author)

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

International Nuclear Information System (INIS)

Nigg, D.W.; Venhuizen, J.R.; Wheeler, F.J.; Wemple, C.A.; Tripard, G.E.; Gavin, P.R.

2000-01-01

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)

Development of Neutron Imaging System for Neutron Tomography at Thai Research Reactor TRR-1/M1

Science.gov (United States)

Wonglee, S.; Khaweerat, S.; Channuie, J.; Picha, R.; Liamsuwan, T.; Ratanatongchai, W.

2017-09-01

The neutron imaging is a powerful non-destructive technique to investigate the internal structure and provides the information which is different from the conventional X-ray/Gamma radiography. By reconstruction of the obtained 2-dimentional (2D) images from the taken different angle around the specimen, the tomographic image can be obtained and it can provide the information in more detail. The neutron imaging system at Thai Research Reactor TRR-1/M1 of Thailand Institute of Nuclear Technology (Public Organization) has been developed to conduct the neutron tomography since 2014. The primary goal of this work is to serve the investigation of archeological samples, however, this technique can also be applied to various fields, such as investigation of industrial specimen and others. This research paper presents the performance study of a compact neutron camera manufactured by Neutron Optics such as speed and sensitivity. Furthermore, the 3-dimentional (3D) neutron image was successfully reconstructed at the developed neutron imaging system of TRR-1/M1.

Nondestructive testing: Neutron radiography and neutron activation. (Latest citations from the INSPEC: Information services for the physics and engineering communities database). Published Search

International Nuclear Information System (INIS)

1993-08-01

The bibliography contains citations concerning the technology of neutron radiography and neutron activation for nondestructive testing of materials. The development and evaluation of neutron activation analysis and neutron diffraction examination of liquids and solids are presented. Citations also discuss nondestructive assay, verification, evaluation, and multielement analysis of biomedical, environmental, industrial, and geological materials. Nondestructive identification of chemical agents, explosives, weapons, and drugs in sealed containers are explored. (Contains a minimum of 83 citations and includes a subject term index and title list.)

Performance Test for Neutron Detector and Associated System using Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Yang, Seongwoo; Park, Sung Jae; Cho, Man Soon [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of); Oh, Se Hyun [USERS, Daejeon (Korea, Republic of); Shin, Ho Cheol [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

SPND (Self-Powered Neutron Detector) has been developed to extend its lifespan. ENFMS (Ex-Core Flux Monitoring System) of pressurized water reactor has been also improved. After the development and improvement, their performance must be verified under the neutron irradiation environment. We used a research reactor for the performance verification of neutron detector and associated system because the research reactor can meet the neutron flux level of commercial nuclear reactor. In this paper, we report the performance verification method and result for the SPND and ENFMS using the research reactor. The performance tests for the SPND and ENFMS were conducted using UCI TRIGA reactor. The test environment of commercial reactor’s neutron flux level must be required. However, it is difficult to perform the test in the commercial rector due to the constraint of time and space. The research reactor can be good alternative neutron source for the test of neutron detectors and associated system.

Screening of Maritime Containers to Intercept Weapons of Mass Destruction

International Nuclear Information System (INIS)

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

2004-01-01

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 γ-radiation in the range 3-6 MeV is distinct from normal background radioactivity that does not extend above 2.6 MeV. It's short

Comparison study on in-core neutron detector for online neutron flux mapping of research and power reactor

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Mohd Idris Taib; Izhar Abu Husin; Nurfarhana Ayuni

2010-01-01

This paper presents the comparison study on In-Core neutron detector using for online flux mapping of Research and Power reactor. Technical description of in-core neutron also taken into consideration to identify the different characterization of neutron detector and describe on Self Power neutron detector (SPND) for online neutron flux mapping. Able to provide information on the neutron flux distribution and understand how in-core neutron detector are being used in nuclear power plant including to enable to state the principles of neutron detector. (author)

Neutronics analysis of Dalat Research Reactor

International Nuclear Information System (INIS)

Pham Van Lam; Luong Ba Vien; Le Vinh Vinh; Huynh Ton Nghiem; Nguyen Kien Cuong; Nguyen Manh Hung; Pham Hong Son; Tran Quoc Duong

2006-01-01

Many neutronics codes have been used to calculate for Dalat Research Reactor (DRR) from 1983 (the first critical of DRR in December, 1983). The purposes of all calculations are to know exactly many important parameters related to Reactor Physics and Neutron Physics in reactor core. The results from calculation play important role in core and fuel management for DRR. Especially basing on the results we can predict about fuel cycle, fuel burn up distribution and plan for using optimize remain fresh fuel assemblies of DRR. By using system neutronics code including transport codes, diffusion codes and Mote Carlo code, many characteristics of fuel assemblies and other parameters of whole core were received such as main features of VVR-M2 fuel assembly type, multiplication factor, neutron flux distribution, power distribution, burn up distribution, excess reactivity, control rods worth, neutron spectrum, temperature reactivity coefficient ect. In the paper, brief description all computer codes to being used in DRR and the calculation results from the codes above are presented. (author)

Condensed matter research using pulsed neutron sources: a bibliography

International Nuclear Information System (INIS)

Mildner, D.F.R.; Stirling, G.C.

1976-05-01

This report is an updated revision of RL-75-095 'Condensed Matter Research Using Pulsed Neutron Sources: A Bibliography'. As before, the survey lists published papers concerning (a) the production of high intensity neutron pulses suitable for thermal neutron scattering research, (b) moderating systems for neutron thermalization and pulse shaping, (c) techniques and instrumentation for diffraction and inelastic scattering at pulsed sources, and (d) their application to research problems concerning the structural and dynamical properties of condensed matter. Papers which deal with the white beam time-of-flight technique at steady state reactors have also been included. A number of scientists have brought to the author's attention papers which have been published since the previous edition. They are thanked and encouraged to continue the cooperation so that the bibliography may be updated periodically. (author)

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.

Neutron-proton bremsstrahlung experiments

Energy Technology Data Exchange (ETDEWEB)

Koster, J.E. (Los Alamos National Lab., NM (United States)); Nelson, R.O. (Los Alamos National Lab., NM (United States)); Schillaci, M.E. (Los Alamos National Lab., NM (United States)); Wender, S.A. (Los Alamos National Lab., NM (United States)); Mayo, D. (Univ. of California at Davis, CA (United States)); Brady, F.P. (Univ. of California at Davis, CA (United States)); Romero, J. (Univ. of California at Davis, CA (United States)); Krofcheck, D. (Lawrence Livermore National Lab., CA (United States)); Blann, M. (Lawrence Livermore National Lab., CA (United States)); Anthony, P. (Lawrence Livermore National Lab., CA (United States)); Brown, V.R. (Lawrence Livermore National Lab., CA (United States)); Hansen, L. (Lawrence Livermore National Lab., CA (United States)); Pohl, B. (Lawrence Livermore National Lab., CA (United States)); Sangster, T.C. (Lawrence Livermore National Lab., CA (United States)); Nifenecker, H. (Inst. des Sciences Nucleaires, Grenoble (France)); Pinston,

1993-06-01

It is well known that charged particles emit bremsstrahlung radiation when they are accelerated. Classical electron bremsstrahlung occurs when a proton is emitted by an electron accelerated in the field of a nucleus. The bremsstrahlung process also occurs in the scattering of nucleons, for which it is the lowest energy inelastic process that can occur. Like electron bremsstrahlung, nucleon-nucleon bremsstrahlung also requires the exchange of a virtual particle to conserve energy and momentum. In electron bremsstrahlung a virtual photon is exchanged but with two nucleons a meson can be exchanged. Unlike electron bremsstrahlung, in nucleon-nucleon bremsstrahlung the photon can originate from the exchanged meson. This exchange contribution has been shown in calculations to be a significant fraction of bremsstrahlung events. Thus bremsstrahlung serves as a probe of exchange currents in the nucleon-nucleon interaction. Because of a lack of a free neutron target or an intense neutron beam, few measurements of neutron-proton bremsstrahlung exist, each having poor statistical accuracy and poor energy resolution. The white neutron source at the Weapons Neutron Research (WNR) target area at the Los Alamos Meson Physics Facility (LAMPF) produces neutrons with energies from below 50 to above 400 MeV. Using time-of-flight techniques and a liquid hydrogen target, we are measuring the outgoing photons of energies up to 250 MeV at gamma ray angles of around 90 relative to the incident beam. Protons scattered at very forward angles are also detected in coincidence with the gamma rays. (orig.)

Activity report on neutron scattering research. V. 1, 1994

International Nuclear Information System (INIS)

Fujii, Y.; Oohara, Y.

1994-09-01

In April, 1993, the Neutron Scattering Laboratory attached to the Institute for Solid State Physics, University of Tokyo, was newly established in Tokai, Ibaraki Prefecture, to promote nationwide users' programs for utilizing the university-owned neutron instruments installed at the JRR-3M reactor of Japan Atomic Energy Research Institute. This upgraded reactor (20 MW, the cold source is installed) has drastically expanded the number of users and research areas since 1990 when it became operational. Currently 8 and 3 out of 18 new spectrometers in total at the JRR-3M are owned by ISSP and Tohoku University, respectively, while the remaining 7 spectrometers belong to JAERI. In addition, 3 conventional spectrometers in the 30 years old JRR-2 reactor (10 MW) have also supported research activities. This is the first issue of 'Activity report on neutron scattering research', and it is to be published annually. In this report, the brief history of neutron scattering research, the users' programs, the committees, the neutron scattering instruments available at the JRR-3M and the JRR-2M, the activity reports on structures and excitation, magnetism, superconductors, liquid and glass, material science, polymers, biology and instrumentation, and publication list are reported. (K.I.)

Neutron beam facilities at the replacement research reactor

International Nuclear Information System (INIS)

Kennedy, S.

1999-01-01

Full text: On September 3rd 1997 the Australian Federal Government announced their decision to replace the HIFAR research reactor by 2005. The proposed reactor will be a multipurpose reactor with improved capabilities for neutron beam research and for the production of radioisotopes for pharmaceutical, scientific and industrial use. The neutron beam facilities are intended to cater for Australian scientific needs well into the 21st century. In the first stage of planning the neutron Beam Facilities at the replacement reactor, a Consultative Group was formed (BFCG) to determine the scientific capabilities of the new facility. Members of the group were drawn from academia, industry and government research laboratories. The BFCG submitted their report in April 1998, outlining the scientific priorities to be addressed. Cold and hot neutron sources are to be included, and cold and thermal neutron guides will be used to position most of the instruments in a neutron guide hall outside the reactor confinement building. In 2005 it is planned to have eight instruments installed with a further three to be developed by 2010, and seven spare instrument positions for development of new instruments over the life of the reactor. A beam facilities technical group (BFTG) was then formed to prepare the engineering specifications for the tendering process. The group consisted of some members of the BFCG, several scientists and engineers from ANSTO, and scientists from leading neutron scattering centres in Europe, USA and Japan. The BFTG looked in detail at the key components of the facility such as the thermal, cold and hot neutron sources, neutron collimators, neutron beam guides and overall requirements for the neutron guide hall. The report of the BFTG, completed in August 1998, was incorporated into the draft specifications for the reactor project, which were distributed to potential reactor vendors. An assessment of the first stage of reactor vendor submissions was completed in

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. © 2013 Elsevier Ltd. All rights reserved.

Future of neutron-physical research at WWR-K reactor

International Nuclear Information System (INIS)

Akhmetov, E. Z.; Ibraev, B.M.

1999-01-01

Very cold neutrons (E nm) mostly indicate wave properties in the course of going through substance. The properties are determined by the value of the relation of neutron wave length to structure dimensions of the object studied. Very cold neutrons usage in nuclear-physical and neutron-optical research, in studying of structure and phase transformation of substances in different aggregative states continues to increase and very cold neutrons scattering method can be applied in those situation when other methods don't help to obtain the result (for example identification of light nuclei by roentgen rays etc.). Currently, we suppose that very cold neutrons can be applied in the course of studying superconductors, biological objects, different polymer systems and liquid crystals. Also it can be applied in radioecology - in determination of trans-uranium and trans-plutonium elements content in soil of territories where underground nuclear explosions were performed. These researches can be implemented at the WWR-K reactor. Its parameters and structure allow creating of 'Time-of-flight spectrometer very cold neutrons and cold neutrons', that functionally consists of the following basic blocks: - neutron conductor of stainless steel gage 50 mm, 8 m length; - switch block; - measurement cryostat chamber; - Vacuum shutters; - Measurement calculation complex. Earlier at the WWR-K the authors obtained maximum fluxes of ultra-cold neutrons (E=10 -7 eV) from vapor-hydrogen moderator at the temperature of 80 K and determined interaction cross-sections of ultra-cold neutrons with gas medium

Design of neutron 'fluse-trop' in Tehran Research Reactor

International Nuclear Information System (INIS)

Khalafi, H.

1999-01-01

In this project, a Neutron Flux-Trap intended for 5MW Tehran Research Reactor was designed. Fuel conversion from HEU to LEU in research reactors usually deprives the core from the high neutron flux. Therefore one has to look for a remedy in such situations otherwise radioisotope production, especially for those neutron demanding ones, falls down dramatically. The initiations of Neutron Flux-Trap idea comes true to face up this problem and provide an appropriate place inside or outside the core with sufficient neutron flux higher than the normal average level. To implement such a design, a number of codes and calculational tools have been used. At preliminary stage, WIMSD and EXTERMINATOR-II were used and then at later stages CITATION and MCNP codes were used for final design. Furthermore, SAND-II and ORIGEN were also employed for spectral analysis and radioisotope production calculations. Good agreements resulted with experiments and especially the case that Neutron Flux-Trap filled with ordinary water

Physics studies of weapons plutonium disposition in the Integral Fast Reactor closed fuel cycle

International Nuclear Information System (INIS)

Hill, R.N.; Wade, D.C.; Liaw, J.R.; Fujita, E.K.

1995-01-01

The core performance impact of weapons plutonium introduction into the Integral Fast Reactor (IFR) closed fuel cycle is investigated by comparing three disposition scenarios: a power production mode, a moderate destruction mode, and a maximum destruction mode, all at a constant heat rating of 840 MW(thermal). For each scenario, two fuel cycle models are evaluated: cores using weapons material as the sole source of transuranics in a once-through mode and recycle cores using weapons material only as required for a makeup feed. In addition, the impact of alternative feeds (recycled light water reactor or liquid-metal reactor transuranics) on burner core performance is assessed. Calculated results include mass flows, detailed isotopic distributions, neutronic performance characteristics, and reactivity feedback coefficients. In general, it is shown that weapons plutonium does not have an adverse effect on IFR core performance characteristics; also, favorable performance can be maintained for a wide variety of feed materials and fuel cycle strategies

National facility for neutron beam research

Indian Academy of Sciences (India)

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 ...

Fundamental research with polarized slow neutrons

International Nuclear Information System (INIS)

Krupchitsky, P.A.

1987-01-01

In the last twenty years polarized beams of slow neutrons have been used effectively in fundamental research in nuclear physics. This book gives a thorough introduction to these experimental methods including the most recent techniques of generating and analyzing polarized neutron beams. It clearly shows the close relationship between elementary particle physics and nuclear physics. The book not only addresses specialists but also those interested in the foundations of elementary particle and nuclear physics. With 42 figs

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

Energy Technology Data Exchange (ETDEWEB)

Simpson, R., E-mail: raspberry@lanl.gov; 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. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States)

2016-11-15

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.

Recent research on nuclear reaction using high-energy proton and neutron

Energy Technology Data Exchange (ETDEWEB)

Shibata, Tokushi [Tokyo Univ., Tanashi (Japan). Inst. for Nuclear Study

1997-11-01

The presently available high-energy neutron beam facilities are introduced. Then some interesting research on nuclear reaction using high-energy protons are reported such as the intermediate mass fragments emission and neutron spectrum measurements on various targets. As the important research using high-energy neutron, the (p,n) reactions on Mn, Fe, and Ni, the elastic scattering of neutrons, and the shielding experiments are discussed. (author)

Status of neutron beam utilization at the Dalat nuclear research reactor

International Nuclear Information System (INIS)

Dien, Nguyen Nhi; Hai, Nguyen Canh

2003-01-01

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

Research within the coordinated programme on neutron scattering techniques in applied research

International Nuclear Information System (INIS)

Satya Murthy, N.S.

1982-02-01

This paper reviews developments of neutron scattering studies at Bhabha Atomic Research Centre (BARC) over the past two decades through utilisation of Apsara and Circus reactor facilities. Salient results in neutron crystallography, magnetic diffraction and inelastic neutron scattering will be presented highlighting progressive involvement in more and more complex studies. The growth of non-neutronic activities as a natural outcome of overall necessity and interest of investigators will be indicated. A description of facilities planned at R5 and the nature of studies that are likely to be taken up at R5 will be briefly discussed. (author)

The WNR facility - a pulsed spallation neutron source at the Los Alamos Scientific Laboratory

International Nuclear Information System (INIS)

Russell, G.J.; Lisowski, P.W.; King, N.S.P.

1978-01-01

The Weapons Neutron Research facility (WNR) at the Los Alamos Scientific Laboratory is the first operating example of a new class of pulsed neutron sources using the X(p,n)Y spallation reaction. At present, up to 10 microamperes of 800-MeV protons from the Clinton P. Anderson Meson Physics Facility (LAMPF) linear accelerator bombard a Ta target to produce an intense white-neutron spectrum from about 800 MeV to 100 keV. The Ta target can be coupled with CH 2 and H 2 O moderators to produce neutrons of lower energy. The time structure of the WNR proton beam may be varied to optimize neutron time-of-flight (TOF) measurements covering the energy range from several hundred MeV to a few meV. The neutronics of the WNR target and target/moderator configurations have been calculated from 800 MeV to 0.5 eV. About 11 neutrons per proton are predicted for the existing Ta target. Some initial neutron TOF data are presented and compared with calculations

Basic research for developing the quantitative neutron radiography

International Nuclear Information System (INIS)

Tamaki, Masayoshi; Ikeda, Yasushi; Ohkubo, Kohei; Tasaka, Kanji; Yoneda, Kenji; Fujine, Shigenori.

1992-01-01

This investigation concerns the basic research and development on quantitative neutron radiography by using a honeycomb collimator which reduces the effect due to scattered neutrons in objective matter. On the observation of the hydrogenate materials such as metal hydrides, water and hydrocarbons by neutron radiography, scattered neutrons from these objectives make the quantitativeness of the neutron radiographic image lower grade. In order to improve the quantitativeness of the image, a honeycomb collimator, which is a honeycomb structure of neutron absorbing material, was introduced to the conventional neutron radiography system. By setting the neutron-absorbing honeycomb collimator between objective and imaging system, neutrons scattered in the objective were absorbed by the honeycomb material and attenuated before coming to the imaging system, but neutrons which were transmitted the objective sample without any interaction reached the imaging system and formed the image of the sample. As the image by purely transmitted neutrons is intrinsic due to the neutronic character of the sample, the image data give the quantitative information. In the present experiment, aluminum honeycomb which was coated with boron nitride was prepared and used in order to image the standard stepwise samples for the evaluation of the quantitative grade of the newly proposed neutron radiography method. From the comparison between macroscopic total cross section and the attenuation coefficient of the thermal neutron for aluminum, copper and hydrocarbons, it was confirmed that they were fairly consistent each other. It can be concluded that the newly proposed neutron radiography method using the neutron-absorbing honeycomb collimator for the elimination of the scattered neutrons improves remarkably the quantitativeness of the neutron radiography technique. (author)

Neutron polarizing set-up of the Sofia IRT research reactor

International Nuclear Information System (INIS)

Krezhov, K.; Mikhajlova, V.; Okorokov, A.

1990-01-01

Neutron polarizing set-up of one of the horizontal beam tubes of the IRT-200 research reactor of the Bulgarian Institute of Nuclear Research and Nuclear Energy is presented. Neutron mirrors are extensively used in an effort to compensate the moderate reactor beam intensity by the high reflected intensity and wide-band transmittance of the mirror neutron guides. Time-to-flight technique using a slotted neutron absorbing chopper with a horizontal rotation axis has been applied to obtain the exit neutron spectra. Beam polarization and flipping ratios have been determined. Cadmium ratio in the polarized beam has been found almost 10 4 and the average polarization has been measured to be higher than 96%. 3 figs, 3 refs

Accelerator-driven neutron sources for materials research

International Nuclear Information System (INIS)

Jameson, R.A.

1990-01-01

Particle accelerators are important tools for materials research and production. Advances in high-intensity linear accelerator technology make it possible to consider enhanced neutron sources for fusion material studies or as a source of spallation neutrons. Energy variability, uniformity of target dose distribution, target bombardment from multiple directions, time-scheduled dose patterns, and other features can be provided, opening new experimental opportunities. New designs have also been used to ensure hands-on maintenance on the accelerator in these factory-type facilities. Designs suitable for proposals such as the Japanese Energy-Selective Intense Neutron Source, and the international Fusion Materials Irradiation Facility are discussed

Utilization of a sealed-tube neutron generator for training and research

International Nuclear Information System (INIS)

Jonah, S.A.

2000-01-01

The development of a program in nuclear science and technology in Nigeria began in 1976 with the establishment of two research centers, namely, the Centre for Energy Research and Training, (CERT), Zaria and the Centre for Energy Research and Development (CERD), Ile-Ife. The choice of Neutron Activation Analysis (NAA) technique as a very effective method of training scientists in basic and applied nuclear research led to the purchase of two KAMAN A-711 Neutron Generators for the two research centers. At CERT, the neutron generator (code named ZARABUNG-1) was successfully installed and the first 14 MeV neutrons were produced through the technical assistance of the International Atomic Energy Agency (IAEA) in 1988. In 1991, a new tube-head was purchased and installed due to the expiration of the old tube. Following the completion of its permanent site, the neutron generator was re-located from the old site and re-installed at the permanent site of CERT in 1995. (author)

The reactor and cold neutron research facility at NIST

Energy Technology Data Exchange (ETDEWEB)

Prask, H J; Rowe, J M [Reactor Radiation Division, National Institute of Standards and Technology, Gaithersburg, MD (United States)

1992-07-01

The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D{sub 2}O/H{sub 2}O ice cold source. (author)

The reactor and cold neutron research facility at NIST

International Nuclear Information System (INIS)

Prask, H.J.; Rowe, J.M.

1992-01-01

The NIST Reactor (NBSR) is a 20 MW research reactor located at the Gaithersburg, MD site, and has been in operation since 1969. It services 26 thermal neutron facilities which are used for materials science, chemical analysis, nondestructive evaluation, neutron standards work, and irradiations. In 1987 the Department of Commerce and NIST began development of the CNRF - a $30M National Facility for cold neutron research -which will provide fifteen new experimental stations with capabilities currently unavailable in this country. As of May 1992, four of the planned seven guides and a cold port were installed, eight cold neutron experimental stations were operational, and the Call for Proposals for the second cycle of formally-reviewed guest-researcher experiments had been sent out. Some details of the performance of instrumentation are described, along with the proposed design of the new hydrogen cold source which will replace the present D 2 O/H 2 O ice cold source. (author)

Utilizations of filtered neutron beams at Dalat nuclear research reactor

International Nuclear Information System (INIS)

Hien, P.D.; Chau, L.N.; Tan, V.H.; Hiep, N.T.; Phuong, L.B.

1992-01-01

Neutron beam utilizations in basic and applied researches have been important activities at the Dalat nuclear reactor. The neutron filters with single crystal of silicon are used to produce thermal neutrons at the tangential horizontal channel and quasi-monoenergetic 144 KeV and 54 KeV neutrons at the piercing beam tube. The paper presents some relevant characteristics of the filtered neutron beams at the two horizontal channels. Applications of neutron beams in prompt gamma-ray activation analysis and in nuclear data measurements are briefly described. (author)

Opportunities for research using neutron beams at Australia's replacement research reactor

International Nuclear Information System (INIS)

Robinson, R.A.

2000-01-01

Full text: On July 13th 2000, a contract was signed for construction of Australia's Replacement Research Reactor at Lucas Heights just outside Sydney. This may represent Australia's largest single investment in scientific infrastructure, and it provides researchers in condensed matter physics, chemistry, materials science, and some aspects of engineering, the earth sciences and biology with the 'opportunity of a generation' The replacement reactor, which will commence operation in 2005, will be comparable with the national neutron sources of Japan, France and the U.S.A. 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 all the associated infrastructure, with the exception of the neutron beam instruments, is to be built by the Argentinian company INVAP S.E., in collaboration with two Australian firms, in a turnkey contract. The instruments will be developed by ANSTO and other contracted organisations, in consultation with the Australian user community and interested overseas parties. This presentation reviews the planned scientific capabilities and opportunities, gives a description of the facility and a status report on the activities so far

Cold neutron source conceptual designing for Tehran Research Reactor

International Nuclear Information System (INIS)

Khajvand, N.; Mirvakili, S.M.; Faghihi, F.

2016-01-01

Highlights: • Cold neutron source conceptual designing for Tehran research reactor is carried out. • Type and geometry of moderator and dimensions of cold neutron source are analyzed. • Liquid hydrogen with more ortho-concentration can be better option as moderator. - Abstract: A cold neutron source (CNS) conceptual designing for the Tehran Research Reactor (TRR) were carried out using MCNPX code. In this study, a horizontal beam tube of the core which has appropriate the highest thermal flux is selected and parametric analysis to choose the type and geometry of the moderator, and the required CNS dimensions for maximizing the cold neutron production was performed. In this design the moderator cell has a spherical annulus structure, and the cold neutron flux and its brightness are calculated together with the nuclear heat load of the CNS for a variety of materials including liquid hydrogen, liquid deuterium, and solid methane. Based on our study, liquid hydrogen with more ortho-concentration than para and solid methane are the best options.

Flexible weapons architecture design

Science.gov (United States)

Pyant, William C., III

Present day air-delivered weapons are of a closed architecture, with little to no ability to tailor the weapon for the individual engagement. The closed architectures require weaponeers to make the target fit the weapon instead of fitting the individual weapons to a target. The concept of a flexible weapons aims to modularize weapons design using an open architecture shell into which different modules are inserted to achieve the desired target fractional damage while reducing cost and civilian casualties. This thesis shows that the architecture design factors of damage mechanism, fusing, weapons weight, guidance, and propulsion are significant in enhancing weapon performance objectives, and would benefit from modularization. Additionally, this thesis constructs an algorithm that can be used to design a weapon set for a particular target class based on these modular components.

Personal neutron dosimetry at a research reactor facility

International Nuclear Information System (INIS)

Kamenopoulou, V.; Carinou, E.; Stamatelatos, I.E.

2001-01-01

Individual neutron monitoring presents several difficulties due to the differences in energy response of the dosemeters. In the present study, an individual dosemeter (TLD) calibration approach is attempted for the personnel of a research reactor facility. The neutron energy response function of the dosemeter was derived using the MCNP code. The results were verified by measurements to three different neutron spectra and were found to be in good agreement. Three different calibration curves were defined for thermal, intermediate and fast neutrons. At the different working positions around the reactor, neutron spectra were defined using the Monte Carlo technique and ambient dose rate measurements were performed. An estimation of the neutrons energy is provided by the ratio of the different TLD pellets of each dosemeter in combination with the information concerning the worker's position; then the dose equivalent is deduced according to the appropriate calibration curve. (author)

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.

Neutron flux characterization of californium-252 Neutron Research Facility at the University of Texas - Pan American by nuclear analytical technique

Science.gov (United States)

Wahid, Kareem; Sanchez, Patrick; Hannan, Mohammad

2014-03-01

In the field of nuclear science, neutron flux is an intrinsic property of nuclear reaction facilities that is the basis for experimental irradiation calculations and analysis. In the Rio Grande Valley (Texas), the UTPA Neutron Research Facility (NRF) is currently the only neutron facility available for experimental research purposes. The facility is comprised of a 20-microgram californium-252 neutron source surrounded by a shielding cascade containing different irradiation cavities. Thermal and fast neutron flux values for the UTPA NRF have yet to be fully investigated and may be of particular interest to biomedical studies in low neutron dose applications. Though a variety of techniques exist for the characterization of neutron flux, neutron activation analysis (NAA) of metal and nonmetal foils is a commonly utilized experimental method because of its detection sensitivity and availability. The aim of our current investigation is to employ foil activation in the determination of neutron flux values for the UTPA NSRF for further research purposes. Neutron spectrum unfolding of the acquired experimental data via specialized software and subsequent comparison for consistency with computational models lends confidence to the results.

IMPROVED COMPUTATIONAL CHARACTERIZATION OF THE THERMAL NEUTRON SOURCE FOR NEUTRON CAPTURE THERAPY RESEARCH AT THE UNIVERSITY OF MISSOURI

Energy Technology Data Exchange (ETDEWEB)

Stuart R. Slattery; David W. Nigg; John D. Brockman; M. Frederick Hawthorne

2010-05-01

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 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. This is essential for detailed dosimetric studies required for the anticipated research program.

Flexible weapons architecture design

OpenAIRE

Pyant, William C.

2015-01-01

Present day air-delivered weapons are of a closed architecture, with little to no ability to tailor the weapon for the individual engagement. The closed architectures require weaponeers to make the target fit the weapon instead of fitting the individual weapons to a target. The concept of a flexible weapons aims to modularize weapons design using an open architecture shell into which different modules are inserted to achieve the desired target fractional damage while reducing cost and civilia...

Results of neutron dose measurements at the Rossendorf research reactors taking the actual neutron spectra into account

International Nuclear Information System (INIS)

Rimpler, A.; Kneschke, H.

1985-01-01

Based on a systematic evaluation of area dose studies at the beginning of the seventies, no individual routine neutron monitoring has been performed at the Rossendorf research reactors. To check this decision, a limited number of persons has been monitored with solid-state nuclear track detectors for several years. The dosemeters were calibrated on the basis of neutron spectra determined at the working places by means of the Bonner sphere method. Intermediate neutrons with a 1/E/sup α/ Fermi distribution were dominating. The fraction of fast neutrons was practically negligible. The obtained spectra, radiation, field quantities and results of individual dose measurements are presented. The dosemeter most appropriate for such neutron fields would be a 12-inch Bonner sphere rem counter. As the mean annual neutron exposure of research workers at the reactor amounted to only 2% of the maximum permissible dose, individual routine monitoring will, also in the future, not be neccessary. (author)

Neutron scattering investigation on low-dimensional, quantum and frustrated magnetism and utilization of neutron polarization analysis. My first encounter with neutron research

International Nuclear Information System (INIS)

Kakurai, Kazuhisa

2013-01-01

My first encounter with neutron scattering research on low-dimensional magnetism at the Hahn-Meitner Institut under the supervision of Prof. H. Dachs and Prof. M. Steiner, were it all began, is accounted for. The polarized neutron analysis research on low-dimensional magnetism at the Institut Laue Langevin under the supervision of Dr. R. Pynn is also reported. I would like to dedicate this article to late Prof. H. Dachs expressing may deepest gratitude for his warm guidance during the early period of my neutron science carrier. (author)

Progress report from the Studsvik Neutron Research Laboratory 1990-91

International Nuclear Information System (INIS)

Dahlborg, U.; Ebbsjoe, I.; Holmqvist, B.

1992-01-01

The Studsvik Neutron Research Laboratory (NFL) is the base for the research activities at the Studsvik reactors. It is administrated by the University of Uppsala and is established to facilitate reactor based research. The laboratory is intended to, in co-operation with institutes and department at universities in Sweden, develop, construct and maintain experimental equipment for this kind of research and to make it available for scientists at Swedish universities and, if possible, also to scientists outside the universities. The research at the Studsvik facilities has during 1990 and 1991 been performed by groups form Uppsala University, Royal Institute of Technology, Stockholm, Chalmers Technical University, Gothenburg, and by scientists at NFL. The research programme of the groups is divided into three main areas, scattering of thermal neutrons, nuclear chemistry/nuclear physics, and neutron capture radiography

Research on neutron source multiplication method in nuclear critical safety

International Nuclear Information System (INIS)

Zhu Qingfu; Shi Yongqian; Hu Dingsheng

2005-01-01

The paper concerns in the neutron source multiplication method research in nuclear critical safety. Based on the neutron diffusion equation with external neutron source the effective sub-critical multiplication factor k s is deduced, and k s is different to the effective neutron multiplication factor k eff in the case of sub-critical system with external neutron source. The verification experiment on the sub-critical system indicates that the parameter measured with neutron source multiplication method is k s , and k s is related to the external neutron source position in sub-critical system and external neutron source spectrum. The relation between k s and k eff and the effect of them on nuclear critical safety is discussed. (author)

Neutron Imaging at LANSCE—From Cold to Ultrafast

Directory of Open Access Journals (Sweden)

Ronald O. Nelson

2018-02-01

Full Text Available In recent years, neutron radiography and tomography have been applied at different beam lines at Los Alamos Neutron Science Center (LANSCE, covering a very wide neutron energy range. The field of energy-resolved neutron imaging with epi-thermal neutrons, utilizing neutron absorption resonances for contrast as well as quantitative density measurements, was pioneered at the Target 1 (Lujan center, Flight Path 5 beam line and continues to be refined. Applications include: imaging of metallic and ceramic nuclear fuels, fission gas measurements, tomography of fossils and studies of dopants in scintillators. The technique provides the ability to characterize materials opaque to thermal neutrons and to utilize neutron resonance analysis codes to quantify isotopes to within 0.1 atom %. The latter also allows measuring fuel enrichment levels or the pressure of fission gas remotely. More recently, the cold neutron spectrum at the ASTERIX beam line, also located at Target 1, was used to demonstrate phase contrast imaging with pulsed neutrons. This extends the capabilities for imaging of thin and transparent materials at LANSCE. In contrast, high-energy neutron imaging at LANSCE, using unmoderated fast spallation neutrons from Target 4 [Weapons Neutron Research (WNR facility] has been developed for applications in imaging of dense, thick objects. Using fast (ns, time-of-flight imaging, enables testing and developing imaging at specific, selected MeV neutron energies. The 4FP-60R beam line has been reconfigured with increased shielding and new, larger collimation dedicated to fast neutron imaging. The exploration of ways in which pulsed neutron beams and the time-of-flight method can provide additional benefits is continuing. We will describe the facilities and instruments, present application examples and recent results of all these efforts at LANSCE.

Neutron scattering research at JAERI reactors - past, present and future -

International Nuclear Information System (INIS)

Funahashi, Satoru; Morii, Yukio; Minakawa, Nobuaki

1992-01-01

It was in 1961 that the first neutron scattering experiment was performed in Japan at JRR-2. The start of JRR-3 in 1964 accelerated the neutron scattering activities in Japan. The research in this field in Japan grew up by using these two research reactors. Among them JRR-2 has played an important role because its neutron flux was about seven times higher than that of the old JRR-3. The completion of the new JRR-3M in 1990 made an epoch to the neutron scattering activities in Japan. The long-waited JRR-3M came up to the expectations of the scientists of Japan. It is a realization of the ideal reactor with tangential beam holes, cold source and neutron guides in a large guide hall. The flux at the neutron scattering instruments is about five times higher than that of JRR-2. Utilization of JRR-3M has just started. Twelve neutron scattering machines are running there. The number will increase up to close twenty in a couple of years. (author)

Basic Design of the Cold Neutron Research Facility in HANARO

International Nuclear Information System (INIS)

Kim, Hark Rho; Lee, K. H.; Kim, Y. K.

2005-09-01

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

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.

Research on neutron capture therapy in the USSR

International Nuclear Information System (INIS)

Ryabukhin, Y.

1988-01-01

Research on neutron capture therapy in the USSR began in 1964. Towards 1975 prime knowledge in physics, pharmacology and radiobiology had been accumulated. It was realized that inherent to NCT is a variety of modalities as to the type and location of the tumor, the energy and source of neutrons, the nature and transportation of the nuclide-carrying agent (NCA), etc. Thus, it became likely that some modalities would turn out to be clinically feasible. At the end of the 70s, studies of boron derivatives began at the All-Union Oncological Research Center, Moscow. These studies were stimulated by the clinical trials in Japan. Still, neutron capturing nuclides (NCN) other than 10 b are regarded as promising. Research was aimed at clinical trials that could ensure sufficient safety, convenience and conclusiveness. Hence, new requirements emerged, such as the pre-clinical modeling of NCT in big animals and the monitoring of tumor response to each fraction of NCT. Usual requirements are also to be met, that is: tailoring neutron beams with an adequate intensity and energy, choosing NCNs and finding suitable NCAs, physical and radiobiological planning including adoption of tentative RBEs and time-fractionation regimen, selecting tumors as candidates for NCT, and developing techniques for monitoring NCNs in vivo

New era of neutron scattering research on advanced materials

International Nuclear Information System (INIS)

Ikeda, Susumu

2001-01-01

The projects of the next generation of pulsed spallation neutron source are planed in USA, Europe and Japan. They are one order of magnitude more powerful than the most powerful existing neutron source, ISIS in UK. They offer the exciting prospects for the future, and will open the new era of neutron scattering research on advanced materials. The Japanese project is named as the 'Joint project' between JAERI and KEK on high-intensity proton accelerators. The details of the neutron science facility in the 'Joint project' and the sciences to be developed are summarized. (author)

Research Reactors Types and Utilization

International Nuclear Information System (INIS)

Abdelrazek, I.D.

2008-01-01

A nuclear reactor, in gross terms, is a device in which nuclear chain reactions are initiated, controlled, and sustained at a steady rate. The nuclei of fuel heavy atoms (mostly 235 U or 239 Pu), when struck by a slow neutron, may split into two or more smaller nuclei as fission products,releasing energy and neutrons in a process called nuclear fission. These newly-born fast neutrons then undergo several successive collisions with relatively low atomic mass material, the moderator, to become thermalized or slow. Normal water, heavy water, graphite and beryllium are typical moderators. These neutrons then trigger further fissions, and so on. When this nuclear chain reaction is controlled, the energy released can be used to heat water, produce steam and drive a turbine that generates electricity. The fission process, and hence the energy release, are controlled by the insertion (or extraction) of control rods through the reactor. These rods are strongly neutron absorbents, and thus only enough neutrons to sustain the chain reaction are left in the core. The energy released, mostly in the form of heat, should be continuously removed, to protect the core from damage. The most significant use of nuclear reactors is as an energy source for the generation of electrical power and for power in some military ships. This is usually accomplished by methods that involve using heat from the nuclear reaction to power steam turbines. Research reactors are used for radioisotope production and for beam experiments with free neutrons. Historically, the first use of nuclear reactors was the production of weapons grade plutonium for nuclear weapons. Currently all commercial nuclear reactors are based on nuclear fission. Fusion power is an experimental technology based on nuclear fusion instead of fission.

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.

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.

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.

Current status of neutron scattering research and accelerator technology in Indonesia

International Nuclear Information System (INIS)

Ridwan; Ikram, Abarul; Wuryanto

2001-01-01

The neutron beam generated from steady state reactor 30 MW RSG-GAS are used mainly for neutron scattering studies and isotope production. There are seven neutron scattering facilities under responsible and operated by Research and Development Center for Materials Science and Technology of National Nuclear Energy Agency (Batan) of Indonesia. In this report, current conditions of the facilities namely, DN1-M, HRPD, FCD/TD, SANS, HRSANS, TAS and NRF and research activities will be described. Also, a part of research activities by using accelerator technology at Batan-Yogyakarta will be reviewed. (author)

Democracy, public opinion, and nuclear weapons

International Nuclear Information System (INIS)

Russett, B.

1989-01-01

To the degree that people's fears of nuclear war are deep and pervasive, they become subject to manipulation by cynical or politically utopian promises, whether those promises be to abolish nuclear weapons from the earth or to create a leakproof peace shield (SDI). But the basic yearning for protection could also be mobilized to support serious arms reduction and arms control agreements. Nuclear weapons provide the basis for a vivid form of symbolic politics, perhaps equivalent in foreign policy considerations to the Korean and Vietnam wars during their durations, and in similar ways (although not necessarily as severe) as unemployment does among domestic policy issues. This paper presents survey research directed specifically at the role of public opinion on nuclear imagery (difference between expectation of nuclear war versus any kind of weapon war; willingness to spend on nuclear weapons versus conventional ones or general defense spending) can help in understanding these phenomena

Introduction of neutron research facilities in Indonesia Nuclear Agency

International Nuclear Information System (INIS)

Nishida, Masayuki; Muslih, M. Refai; Minakawa, Nobuaki

2004-01-01

In this report, some facilities for neutron diffraction installed in Indonesia nuclear Agency (BATAN) are introduced. Rough sketch of BATAN, and facility arrangement in the reactor hall and the guide hall are schematically shown. The four facilities (powder diffractometer, four-circle goniometer, three-axis goniometer and neutron radiography system) are installed in the reactor hall and the three (small angle neutron scattering (SANS), high resolution SANS and high resolution powder diffractometer) in the guide hall. Neutron wavelengths determined from four hk1 planes of standard Si powder by the BATAN's neutron diffraction facility are compared with those measured by the similar facility in Japan Atomic Energy Research Institute (JAERI). The neutron diffraction profile of W-fiber reinforced Cu composite is measured by the BATAN's facility. The experimental results show the strong 110 preferred orientation to the fiber direction. (author)

Creative scientific research international session of 2nd meeting on advanced pulsed-neutron research on quantum functions in nano-scale materials

International Nuclear Information System (INIS)

Itoh, Shinichi

2005-06-01

1 MW-class pulsed-neutron sources will be constructed in Japan, United State and United Kingdom in a few years. Now is the time for a challenge to innovate on neutron science and extend new science fields. Toward the new era, we develop new pulsed-neutron technologies as well as new neutron devices under the international collaborations with existing pulsed-neutron facilities, such as the UK-Japan collaboration program on neutron scattering. At the same time, the new era will bring international competitions to neutron researchers. We aim to create new neutron science toward the new pulsed-neutron era by introducing the new technologies developed here. For this purpose, we have started the research project, 'Advanced pulsed-neutron research on quantum functions in nano-scale materials,' in the duration between JFY2004 and JFY2008. The 2nd meeting of this project was held on 22-24 February 2005 to summarize activities in FY2004 and to propose research projects in the coming new fiscal year. In this international session as a part of this meeting, the scientific results and research plans on the UK-Japan collaboration program, the research plans on the collaboration between IPNS (Intense Pulsed Neutron Source, Argonne National Laboratory) and KENS (Neutron Science Laboratory, KEK), also the recent scientific results arisen form this project were presented. (author)

Disposition of excess weapon grade plutonium: Status of the Russian program

Energy Technology Data Exchange (ETDEWEB)

Diyakov, Anatoly [Center for Arms Control, Energy and Environmental Studies, Moscow (Russian Federation)

2015-07-01

During the Cold War, the Soviet Union and United States produced huge quantities of plutonium for weapons. Substantial cuts in their nuclear arsenals released of huge amounts of weapon grade nuclear materials. This put into the agenda the problem what to do with the excess weapon materials. In 2000 Russia and the United States concluded a Plutonium Management and Disposition Agreement (PMDA), committing each to eliminate 34 tons of excess weapon plutonium. It was expected that the implementation of the PMDA Agreement will start in the second half of the year 2009 and the disposition programs finalized in 2025. But from the very beginning the practical implementation of the PMDA agreement met with substantial difficulties. After the consultations held in 2006-2007 the PMDA Agreement was modified. In compliance with the modified Agreement each side pledged to start the disposition of 34 tons of excess plutonium (25 tons in the form of metal and 9 tons in dioxide) in 2018 and to finalize the process in 15 years. Both sides were supposed to use the same disposition method through use in the MOX fuel and its subsequent irradiation in civil nuclear reactors: in light reactors for the USA and in fast neutron reactors for Russia. The presentation is going to provide the current status of the disposition program.

Biological effectiveness of neutrons: Research needs

International Nuclear Information System (INIS)

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

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.

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.

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

APSTNG: Neutron interrogation for detection of nuclear and CW weapons, explosives, and drugs

International Nuclear Information System (INIS)

Rhodes, E.; Dickerman, C.E.; De Volpi, A.; Peters, C.W.

1992-01-01

A recently developed neutron diagnostic probe system has the potential to satisfy a significant number of van-mobile and fixed- portal requirements for nondestructive verification of sealed munitions and detection of contraband explosives and drugs. The probe is based on a unique associated-particle sealed-tube neutron generator (APSTNG) that interrogates the object of interest with a low-intensity beam of 14-MeV neutrons generated from the deuterium-tritium reaction and that detects the alpha-particle associated with each neutron. Gamma-ray spectra of resulting neutron inelastic scattering and fission reactions identify nuclides associated with all major chemicals in chemical warfare agents, explosives, and drugs, as well as many pollutants and fissile and fertile special nuclear material. Flight times determined from determined from detection times of the gamma-rays and alpha-particles yield a separate tomographic image of each identified nuclide. The APSTNG also forms the basis for a compact fast-neutron transmission imaging system that can be used along with or instead of the emission imaging system; a collimator is not required since scattered neutrons are removed by ''electronic collimation'' (detected neutrons not having the proper flight time to be uncollided are discarded). The small and relatively inexpensive APSTNG exhibits high reliability and can be quickly replaced. Proof-of-concept experiments have been performed under laboratory conditions for simulated nuclear and chemical warfare munitions and for explosives and drugs

The neutron utilization and promotion program of TRR-II research reactor project in Taiwan

International Nuclear Information System (INIS)

Gone, J.K.; Huang, Y.H.

2001-01-01

The objective of the Taiwan research reactor system improvement and utilization promotion project is to reconstruct the old Taiwan research reactor (TRR), which was operated by the Institute of Nuclear Energy Research (INER) between 1973 and 1988, into a multi-purpose medium flux research reactor (TRR-II). The project started in 1998, and the new reactor is scheduled to have its first critical in June of 2006. The estimated maximum unperturbed thermal neutron flux (E 14 n/cm 2 sec, and it is about one order of magnitude higher than other operating research reactors in Taiwan. The new reactor will equip with secondary neutron sources to provide neutrons with different energies, which will be an essential tool for advanced material researches in Taiwan. One of the major tasks of TRR-II project is to promote domestic utilization of neutrons generated at TRR-II. The traditional uses of neutrons in fuel/material research, trace element analysis, and isotope production has been carried out at INER for many years. On the other hand, it is obvious that promotions of neutron spectrometric technique will be a major challenge for the project team. The limited neutron flux from operating research reactors had discouraged domestic users in developing neutron spectrometric technique for many years, and only few researchers in Taiwan are experienced in using spectrometers. It is important for the project team to encourage domestic researchers to use neutron spectrometers provided by TRR-II as a tool for their future researches in various fields. This paper describes the current status of TRR-II neutron utilization and promotion program. The current status and future plans for important issues such as staff recruiting, personnel training, international collaboration, and promotion strategy will be described. (orig.)

Progress report on JAERI-ORNL cooperative neutron scattering research

International Nuclear Information System (INIS)

Iizumi, Masashi

1985-08-01

One year activities done under the JAERI-DOE(ORNL) cooperative neutron scattering program are summarized. This period just followed the completion of the wide-angle neutron diffractometer dedicated to the cooperative research. The report contains results of the performance test of the instrument and early research activities. The latter part includes the time-resolved measurements of the transition kinetics in tin and Ni-Mn alloy as well as the single-crystal diffraction by the flat-cone method. (author)

Combating the terrorist use of mass destruction weapons, particularly nuclear weapons

International Nuclear Information System (INIS)

Barakat, M.

2008-01-01

The risks of mass destruction weapons vary and also forms of damages resulting therefrom. While the effects of nuclear weapons are focused, sudden and comprehensive, the chemical weapons have limited impacts relatively unless used intensively severe prejudice to the element of surprise, and thus impaired the efficacy of their influences,especially that they affect exceptionally the individuals in the area of injury and biological weapons do not announce themselves except through their effect that appears later than the time of use as they affect exceptionally the organisms in the area of injury.The mass destruction weapons have turned from being a purely military means in the early twentieth century and have now become the means of violence against governments and countries that they should prepare themselves for and respond in ways of successful and effective countermeasures. Despite the fact that the acquisition of mass destruction weapons can be considered as a priority objective, which terrorist groups and organizations steadily seek but their accessibility is flanked by a lot of difficulties. Addressing the risk of further spread of nuclear weapons, and especially after doubling the power of those high-risk weapons, the international community has an approach to take a number of arrangements that complement each other to control and resist nuclear proliferation, either for the states or for terrorist groups.

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.)

Preliminary study on weapon grade uranium utilization in molten salt reactor miniFUJI

International Nuclear Information System (INIS)

Aji, Indarta Kuncoro; Waris, A.

2014-01-01

Preliminary study on weapon grade uranium utilization in 25MWth and 50MWth of miniFUJI MSR (molten salt reactor) has been carried out. In this study, a very high enriched uranium that we called weapon grade uranium has been employed in UF 4 composition. The 235 U enrichment is 90 - 95 %. The results show that the 25MWth miniFUJI MSR can get its criticality condition for 1.56 %, 1.76%, and 1.96% of UF 4 with 235 U enrichment of at least 93%, 90%, and 90%, respectively. In contrast, the 50 MWth miniFUJI reactor can be critical for 1.96% of UF 4 with 235 U enrichment of at smallest amount 95%. The neutron spectra are almost similar for each power output

Neutron generators and their uses in research and applied fields. Vol. 1

Energy Technology Data Exchange (ETDEWEB)

Asfour, F I [Division of Basic Nuclear Sciences, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

1996-03-01

The development of the low voltage neutron generators (NGS) has contributed considerably to the scope of nuclear research and the economical application of nuclear methods. Such simple instruments are used to produce 14 MeV and 3 MeV neutrons via the 3{sup H}(d,n)4{sup H}e and 2{sup H}(d,n)3{sup H}e reactions,respectively. The neutrons are very widely used and are inexpensive, easy to install and operate, therefore, in addition to nuclear physicists, there are a number of groups of scientists who use low voltage accelerators as tools for pure and applied research, service and education. The aim of this work is to review shortly those problems and methods of science and technology where the neutrons produced in the D-T and D-D reactions play the main role. A wide range of experiments with the detection of neutrons and charged particles is available including the study of shielding and the generator technology itself. N.G. are recently widely used for the determination of neutron data needed for fast reactor and thermonuclear devices. The principles and techniques of the possible uses of neutron generators in technology and research are summarized. The review is devoted to:- Give a short review of the most important operational characteristics of the neutron generators and the necessary instruments needed for application. Outline the main applications of the neutron generators in neutron activation and prompt radiation analysis in various fields(metallurgy, chemistry, biology, meteoritic and lunar studies, geology and mining, etc...) fast neutron therapy, and radiation effects. 2 figs.

Laboratory directed research and development on disposal of plutonium recovered from weapons. FY1994 final report

International Nuclear Information System (INIS)

Pitts, J.H.; Choi, J.S.

1994-01-01

This research project was conceived as a multi-year plan to study the use of mixed plutonium oxide-uranium oxide (MOX) fuel in existing nuclear reactors. Four areas of investigation were originally proposed: (1) study reactor physics including evaluation of control rod worth and power distribution during normal operation and transients; (2) evaluate accidents focusing upon the reduced control rod worth and reduced physical properties of PuO 2 ; (3) assess the safeguards required during fabrication and use of plutonium bearing fuel assemblies; and (4) study public acceptance issues associated with using material recovered from weapons to fuel a nuclear reactor. First year accomplishments are described. Appendices contain 2 reports entitled: development and validation of advanced computational capability for MOX fueled ALWR assembly designs; and long-term criticality safety concerns associated with weapons plutonium disposition

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

Energy Technology Data Exchange (ETDEWEB)

Choopan Dastjerdi, M.H., E-mail: mdastjerdi@aeoi.org.ir [Reactor Research School, Nuclear Science and Technology Research Institute, Atomic Energy Organization of Iran, Tehran (Iran, Islamic Republic of); Department of Energy Engineering and Physics, Amirkabir University of Technology, Tehran (Iran, Islamic Republic of); Khalafi, H.; Kasesaz, Y.; Mirvakili, S.M.; Emami, J.; Ghods, H.; Ezzati, A. [Reactor Research School, Nuclear Science and Technology Research Institute, Atomic Energy Organization of Iran, Tehran (Iran, Islamic Republic of)

2016-05-11

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 2.26×10{sup 6} to 6.5×10{sup 6} n cm{sup −2} s{sup −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.

High Brightness Neutron Source for Radiography. Final report

International Nuclear Information System (INIS)

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

2008-01-01

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.

US develops neutron to sniff out nuclear material

CERN Document Server

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).

A new neutron reflectometer at Australia's HIFAR research reactor

International Nuclear Information System (INIS)

James, M.; Nelson, A.; Schulz, J.C.; Jones, M.J.; Studer, A.J.; Hathaway, P.

2005-01-01

A new neutron reflectometer has been built at Australia's 10MW HIFAR research reactor. The X172 reflectometer operates in a monochromatic, angular dispersive mode collecting reflectivity data as a function of angle. The incident neutron beam is monochromated by a pair of pyrolytic graphite crystals (λ=2.43A) before being collimated using a pair of motorised sintered B 4 C slits. Detection of the reflected neutron beam is via a 10-atmosphere, helium-3, linear position sensitive detector. Examples of data collected using the X172 reflectometer at air-solid and solid-liquid interfaces are given. Neutron reflectivity values as low as 10 -5 have been measured on this instrument

Neutron physics and nuclear data measurements with accelerators and research reactors

International Nuclear Information System (INIS)

1985-08-01

The report contains a collection of lectures devoted to the latest theoretical and experimental developments in the field of fast neutron measurements and in the studies of neutron interactions with nuclei. The possibilities offered by particle accelerators and research reactors for research and technological applications in these fields are pointed out

Structural adaptations to diverse fighting styles in sexually selected weapons.

Science.gov (United States)

McCullough, Erin L; Tobalske, Bret W; Emlen, Douglas J

2014-10-07

The shapes of sexually selected weapons differ widely among species, but the drivers of this diversity remain poorly understood. Existing explanations suggest weapon shapes reflect structural adaptations to different fighting styles, yet explicit tests of this hypothesis are lacking. We constructed finite element models of the horns of different rhinoceros beetle species to test whether functional specializations for increased performance under species-specific fighting styles could have contributed to the diversification of weapon form. We find that horns are both stronger and stiffer in response to species-typical fighting loads and that they perform more poorly under atypical fighting loads, which suggests weapons are structurally adapted to meet the functional demands of fighting. Our research establishes a critical link between weapon form and function, revealing one way male-male competition can drive the diversification of animal weapons.

Construction of the neutron beam facility at Australia's OPAL research reactor

International Nuclear Information System (INIS)

Kennedy, Shane J.

2006-01-01

Australia's new research reactor, OPAL, has been designed principally for neutron beam science and radioisotope production. It has a capacity for 18 neutron beam instruments, located at the reactor face and in a neutron guide hall. The neutron beam facility features a 20 l liquid deuterium cold neutron source and cold and thermal supermirror neutron guides. Nine neutron beam instruments are under development, of which seven are scheduled for completion in early 2007. The project is approaching the hot-commissioning stage, when criticality will be demonstrated. Installation of the neutron beam transport system and neutron beam instruments in the neutron guide hall and at the reactor face is underway, and the path to completion of this project is relatively clear. This paper will outline the key features of the OPAL reactor, and will describe the neutron beam facility in particular. The status of the construction and a forecast of the program to completion, including commissioning and commencement of routine operation in 2007 will also be discussed

Filtered epithermal quasi-monoenergetic neutron beams at research reactor facilities

International Nuclear Information System (INIS)

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

2015-01-01

Filtered neutron techniques were applied to produce quasi-monoenergetic neutron beams in the energy range of 1.5–133 keV 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. - Highlights: • Quasi-monoenergetic neutron beams in energy range from (1.5–133) keV. • Interference between the resonance and potential scattering amplitudes. • Epithermal neutron beams used in BNCT

4th meeting on advanced pulsed-neutron research on quantum functions in nano-scale materials

International Nuclear Information System (INIS)

2006-07-01

Toward the worldwide realization of high-intensity pulsed neutron source, KEK (High Energy Accelerator Research Organization) proceeds the research by composing 6 research groups as neutron science initiation base to initiate new neutron science. The papers generalizing the researches for 2 years were presented at this meeting. KENS (Neutron Science Laboratory, KEK) shut down on March 22nd in 2006, and KEK will continue the research utilizing the pulsed neutron by using foreign facilities until the completion of J-PARC from now on. At international session in this meeting, the accomplishments and future prospects about the Japan-United Kingdom science and technology collaboration project, and about the research collaboration projects with IPNS (Intense Pulsed Neutron Source, ANL) and LANSCE (Los Alamos Neutron Science Center) were presented. Especially in the latter projects, the first accomplishment was reported under the present agreement. In addition, Meeting on structural study of proteins in aqueous solutions' and 'Meeting on hydrogen quantum atomics study' were held as satellite meetings. (J.P.N)

Cold neutron PGAA facility developments at university research reactors in the USA

International Nuclear Information System (INIS)

Uenlue, K.; Rios-Martinez, C.

2005-01-01

The PGAA applications can be enhanced by using subthermal neutrons, cold neutrons at university research reactors. Only two cold neutron beam facilities were developed at the U.S. university research reactors, namely at Cornell University and the University of Texas at Austin. Both facilities used mesitylene moderator. The mesitylene moderator in the Cornell Cold Neutron Beam Facility (CNBF) was cooled by a helium cryorefrigerator via copper cold fingers to maintain the moderator below 30 K at full power reactor operation. Texas Cold Neutron Source (TCNS) also uses mesitylene moderator that is cooled by a cryorefrigerator via a neon thermosiphon. The operation of the TCNS is based on a helium cryorefrigerator, which liquefies neon gas in a 3-m long thermosiphon. The thermosiphon cools and maintains mesitylene moderator at about 30 K in a chamber. Neutrons streaming through the mesitylene chamber are moderated and thus reduce their energy to produce a cold neutron distribution. (author)

Research opportunities with compact accelerator-driven neutron sources

Energy Technology Data Exchange (ETDEWEB)

Anderson, I.S. [Oak Ridge National Laboratory, Oak Ridge, TN (United States); Andreani, C., E-mail: carla.andreani@uniroma2.it [Università degli Studi di Roma “Tor Vergata”, Physics Department and NAST Centre, Via della Ricerca Scientifica 1, 00133 Roma (Italy); CNR-IPCF Sezione di Messina, Messina (Italy); Museo Storico della Fisica e Centro Studi e Ricerche Enrico Fermi, Roma (Italy); Carpenter, J.M. [Argonne National Laboratory, Argonne, IL (United States); Festa, G., E-mail: giulia.festa@uniroma2.it [Università degli Studi di Roma “Tor Vergata”, Physics Department and NAST Centre, Via della Ricerca Scientifica 1, 00133 Roma (Italy); Museo Storico della Fisica e Centro Studi e Ricerche Enrico Fermi, Roma (Italy); Gorini, G. [Università degli Studi di Milano—Bicocca, Milano (Italy); Loong, C.-K. [Università degli Studi di Roma “Tor Vergata”, Centro NAST, Via della Ricerca Scientifica 1, 00133 Roma (Italy); Senesi, R. [Università degli Studi di Roma “Tor Vergata”, Physics Department and NAST Centre, Via della Ricerca Scientifica 1, 00133 Roma (Italy); CNR-IPCF Sezione di Messina, Messina (Italy); Museo Storico della Fisica e Centro Studi e Ricerche Enrico Fermi, Roma (Italy)

2016-10-13

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.

Research opportunities with compact accelerator-driven neutron sources

International Nuclear Information System (INIS)

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

2016-01-01

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.

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.

A strategy for weapons-grade plutonium disposition

International Nuclear Information System (INIS)

Sylvester, K.W.B.

1994-09-01

A political as well as technical analysis was performed to determine the feasibility of glassification (vitrification) for weapons grade plutonium (WGPu) disposition. The political analysis provided the criteria necessary to compare alternative storage forms. The technical areas of weapon useability and environmental safety were then computationally and experimentally explored and a vitrification implementation strategy postulated. The Monte Carlo Neutron Photon (MCNP) computer code was used to model the effect of blending WGPu with reactor grade Pu (RGPu). A mixture of 30% RGPu and 70% WGPu more than doubled the surface flux from a bare sphere of the mixture which assumedly correlates to a significantly increased predetonation probability. Rare earth diluents were also examined (using MCNP) for their ability to increase the compressed critical mass of the WGPu mixture. The rare earths (notably Eu) were effective in this regard. As Pu-239 has a 24,100 year half life, reactivity control in the long term is an environmental safety issue. Rare earths were investigated as criticality controllers due to their neutron absorption capabilities and insolubility in aqueous environments. Thorium (a Pu surrogate) and the rare earths Eu, Gd, and Sm were added to two standard frits (ARM-1 and SRL-165) and formed into glass. Aqueous leach tests were performed (using MCC-1P guidelines) to measure rare earth leaching and determine the added elements' effects on glass durability. Europium was much more leach resistant than boron in the glasses tested. The elements had no negative effect on the environmental durability of the glasses tested at 90 C and minimal effect at room temperature. No fission product releases were detected in the ARM-1 compositions (which contained numerous simulated fission products)

A strategy for weapons-grade plutonium disposition

Energy Technology Data Exchange (ETDEWEB)

Sylvester, K.W.B. [Iowa State Univ., Ames, IA (United States)

1994-09-01

A political as well as technical analysis was performed to determine the feasibility of glassification (vitrification) for weapons grade plutonium (WGPu) disposition. The political analysis provided the criteria necessary to compare alternative storage forms. The technical areas of weapon useability and environmental safety were then computationally and experimentally explored and a vitrification implementation strategy postulated. The Monte Carlo Neutron Photon (MCNP) computer code was used to model the effect of blending WGPu with reactor grade Pu (RGPu). A mixture of 30% RGPu and 70% WGPu more than doubled the surface flux from a bare sphere of the mixture which assumedly correlates to a significantly increased predetonation probability. Rare earth diluents were also examined (using MCNP) for their ability to increase the compressed critical mass of the WGPu mixture. The rare earths (notably Eu) were effective in this regard. As Pu-239 has a 24,100 year half life, reactivity control in the long term is an environmental safety issue. Rare earths were investigated as criticality controllers due to their neutron absorption capabilities and insolubility in aqueous environments. Thorium (a Pu surrogate) and the rare earths Eu, Gd, and Sm were added to two standard frits (ARM-1 and SRL-165) and formed into glass. Aqueous leach tests were performed (using MCC-1P guidelines) to measure rare earth leaching and determine the added elements` effects on glass durability. Europium was much more leach resistant than boron in the glasses tested. The elements had no negative effect on the environmental durability of the glasses tested at 90 C and minimal effect at room temperature. No fission product releases were detected in the ARM-1 compositions (which contained numerous simulated fission products).

Research on spatial Model and analysis algorithm for nuclear weapons' damage effects

International Nuclear Information System (INIS)

Liu Xiaohong; Meng Tao; Du Maohua; Wang Weili; Ji Wanfeng

2011-01-01

In order to realize the three dimension visualization of nuclear weapons' damage effects. Aiming at the characteristics of the damage effects data, a new model-MRPCT model is proposed, and this model can carry out the modeling of the three dimension spatial data of the nuclear weapons' damage effects. For the sake of saving on the memory, linear coding method is used to store the MRPCT model. On the basis of Morton code, spatial analysis of the damage effects is completed. (authors)

[Chemical weapons and chemical terrorism].

Science.gov (United States)

Nakamura, Katsumi

2005-10-01

Chemical Weapons are kind of Weapons of Mass Destruction (WMD). They were used large quantities in WWI. Historically, large quantities usage like WWI was not recorded, but small usage has appeared now and then. Chemical weapons are so called "Nuclear weapon for poor countrys" because it's very easy to produce/possession being possible. They are categorized (1) Nerve Agents, (2) Blister Agents, (3) Cyanide (blood) Agents, (4) Pulmonary Agents, (5) Incapacitating Agents (6) Tear Agents from the viewpoint of human body interaction. In 1997 the Chemical Weapons Convention has taken effect. It prohibits chemical weapons development/production, and Organization for the Prohibition of Chemical Weapons (OPCW) verification regime contributes to the chemical weapons disposal. But possibility of possession/use of weapons of mass destruction by terrorist group represented in one by Matsumoto and Tokyo Subway Sarin Attack, So new chemical terrorism countermeasures are necessary.

Current status of neutron activation analysis in HANARO Research Reactor

International Nuclear Information System (INIS)

Chung, Yong Sam; Moon, Jong Hwa; Sohn, Jae Min

2003-01-01

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 13 - 1 x 10 14 n/cm 2 ·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)

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)

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. Copyright © 2014 Elsevier Ltd. All rights reserved.

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 ...

Thai Research Reactor (TRR-1/M1) Neutron Beam Measurements

International Nuclear Information System (INIS)

Ratanatongchai, Wichian

2009-07-01

Full text: Neutron beam tube of neutron radiography facility at Thai Research Reactor (TRR-1/M1) Thailand Institute of Nuclear Technology (public organization) is a divergent beam. The rectangular open-end of the beam tube is 16 cm x 17 cm while the inner-end is closed to the reactor core. The neutron beam size was measured using 20 cm x 40 cm neutron imaging plate. The measurement at the position 100 cm from the end of the collimator has shown that the beam size was 18.2 cm x 19.0 cm. Gamma ray in neutron the beam was also measured by the identical position using industrial X ray film. The area of gamma ray was 27.8 cm x 31.1 cm with the highest intensity found to be along the neutron beam circumference

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…

Preliminary study on weapon grade uranium utilization in molten salt reactor miniFUJI

Energy Technology Data Exchange (ETDEWEB)

Aji, Indarta Kuncoro [Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia); Waris, A., E-mail: awaris@fi.itb.ac.id [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa No. 10 Bandung 40132 (Indonesia)

2014-09-30

Preliminary study on weapon grade uranium utilization in 25MWth and 50MWth of miniFUJI MSR (molten salt reactor) has been carried out. In this study, a very high enriched uranium that we called weapon grade uranium has been employed in UF{sub 4} composition. The {sup 235}U enrichment is 90 - 95 %. The results show that the 25MWth miniFUJI MSR can get its criticality condition for 1.56 %, 1.76%, and 1.96% of UF{sub 4} with {sup 235}U enrichment of at least 93%, 90%, and 90%, respectively. In contrast, the 50 MWth miniFUJI reactor can be critical for 1.96% of UF{sub 4} with {sup 235}U enrichment of at smallest amount 95%. The neutron spectra are almost similar for each power output.

The IAEA collaborating centre for neutron activation based methodologies of research reactors

International Nuclear Information System (INIS)

Bode, P.

2010-01-01

The Reactor Institute Delft of the Delft University of Technology houses the Netherlands' only academic nuclear research reactor, with associated instrumentation and laboratories, for scientific education and research with ionizing radiation. The Institute's swimming pool type research reactor reached first criticality in 1963 and is currently operated at 2MW thermal powers on a 100 h/week basis. The reactor is equipped with neutron mirror guides serving ultra modern neutron beam physics instruments and with a very bright positron facility. Fully automated gamma-ray spectrometry systems are used by the laboratory for neutron activation analysis, providing large scale services under an ISO/IEC 17025:2005 compliant management system, being (since 1993) the first accredited laboratory of its kind in the world. Already for several years, this laboratory is sustainable by rendering these services to both the public and the private sector. The prime user of the Institute's fac ilities is the scientific Research Department of Radiation, Radionuclide and Reactors of the Faculty of Applied Sciences, housed inside the building. All reactor facilities are also made available for use by or for services to, external clients (industry, government, private sector, other (international research institutes and universities). The Reactor Institute Delft was inaugurated in May 2009 as a new lAEA Collaborating Centre for Neutron Activation Based Methodologies of Research Reactors. The collaboration involves education, research and development in (I) Production of reactor-produced, no-carrier added radioisotopes of high specific activity via neutron activation; (II) Neutron activation analysis with emphasis on automation as well as analysis of large samples, and radiotracer techniques and as a cross-cutting activity, (IIl) Quality assurance and management in research and application of research reactor based techniques and in research reactor operations. This c ollaboration will

Defining Weapons of Mass Destruction

Science.gov (United States)

2012-01-01

Cyprus, Liberia, Malta, Marshall Islands , Mongolia, Panama, and St. Vin- cent and the Grenadines, according to a State Department summary available...1972 Biological and Toxin Weapons Convention, and the 1993 Chemical Weapons Convention. As such, NBC weapons represent a group of weapons that the...Development, Produc- tion and Stockpiling of Bacteriological (Biological) and Toxin Weapons and on Their Destruction contains two references to WMD

Nonstrategic Nuclear Weapons

Science.gov (United States)

2017-02-21

of their nonstrategic nuclear weapons and eliminate many of them. These 1991 announcements, coming after the abortive coup in Moscow in July 1991...of these weapons. The abortive coup in Moscow in August 1991 had also caused alarms about the strength of central control over nuclear weapons...assure other allies of the U.S. commitment to their security, but these assurances do not necessarily include legally binding commitments to retaliate

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.

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.

Construction of the Neutron Beam Facility at Australia's OPAL Research Reactor

International Nuclear Information System (INIS)

Kennedy, J.S.

2005-01-01

Full text: Australia's new research reactor, OPAL, has been designed for high quality neutron beam science and radioisotope production. It has a capacity for eighteen neutron beam instruments to be located at the reactor face and in a neutron guide hall. The new neutron beam facility features a 20 litre liquid deuterium cold neutron source and supermirror neutron reflecting guides for intense cold and thermal neutron beams. Nine neutron beam instruments are under development, of which seven are scheduled for completion in early 2007. The project is approaching the hot-commissioning stage, where criticality will be demonstrated. Installation of the neutron beam transport system and neutron beam instruments in the neutron guide hall and at the reactor face is underway, and the path to completion of this project is relatively clear. The lecture will outline Australia's aspirations for neutron science at the OPAL reactor, and describe the neutron beam facility under construction. The status of this project and a forecast of the program to completion, including commissioning and commencement of routine operation in 2007 will also be discussed. This project is the culmination of almost a decade of effort. We now eagerly anticipate catapulting Australia's neutron beam science capability to meet the best in the world today. (author)

Status report on the cold neutron source of the Garching neutron research facility FRM-II

International Nuclear Information System (INIS)

Gobrecht, K.; Gutsmiedl, E.; Scheuer, A.

2001-01-01

The new high flux research reactor of the Technical University of Munich (Technische Universitaet Muenchen, TUM) will be equipped with a cold neutron source (CNS). The centre of the CNS will be located in the D2O-reflector tank at 400 mm from the reactor core axis, close to the thermal neutron flux maximum. The power of 4500 W developed by the nuclear heating in the 16 litres of liquid deuterium at 25 K, and in the structures, is evacuated by a two phase thermal siphon avoiding film boiling and flooding. The thermal siphon is a single tube with counter current flow. It is inclined by 10deg from vertical, and optimised for a deuterium flow rate of 14 g/s. Optimisation of structure design and material, as well as safety aspects will be discussed. Those parts of the structure, which are exposed to high thermal neutron flux, are made from Zircaloy 4 and 6061T6 aluminium. Structure failure due to embrittlement of the structure material under high rapid neutron flux is very importable during the life time of the CNS (30 years). Double, in pile even triple, containment with inert gas liner guarantees lack of explosion risk and of tritium contamination to the environment. Adding a few percent of hydrogen (H2) to the deuterium (D2) will improve the moderating properties of our relatively small moderator volume. Nearly all of the hydrogen is bound in the form of HD molecules. The new reactor will have 13 beam tubes, 4 of which are looking at the cold neutron source (CNS), including two for very cold (VCN) and ultra-cold neutron (UCN) production. The latter will take place in the horizontal beam tube SR4, which will house an additional cryogenic moderator (e.g. solid deuterium). More than 60% of the experiments foreseen in the new neutron research facility will use cold neutrons from the CNS. The mounting of the hardware components of the CNS into the reactor has started in the spring of 2000. The CNS will go into trial operation in the end of year 2000. (J.P.N.)

Neutron energy spectra calculations in the low power research reactor

International Nuclear Information System (INIS)

Omar, H.; Khattab, K.; Ghazi, N.

2011-01-01

The neutron energy spectra have been calculated in the fuel region, inner and outer irradiation sites of the zero power research reactor using the MCNP-4C code and the combination of the WIMS-D/4 transport code for generation of group constants and the three-dimensional CITATION diffusion code for core analysis calculations. The neutron energy spectrum has been divided into three regions and compared with the proposed empirical correlations. The calculated thermal and fast neutron fluxes in the low power research reactor MNSR inner and outer irradiation sites have been compared with the measured results. Better agreements have been noticed between the calculated and measured results using the MCNP code than those obtained by the CITATION code. (author)

Weapons-grade plutonium dispositioning. Volume 1: Executive summary

International Nuclear Information System (INIS)

Parks, D.L.; Sauerbrun, T.J.

1993-06-01

The Secretary of Energy requested the National Academy of Sciences (NAS) Committee on International Security and Arms Control to evaluate dispositioning options for weapons-grade plutonium. The Idaho National Engineering Laboratory (INEL) assisted NAS in this evaluation by investigating the technical aspects of the dispositioning options and their capability for achieving plutonium annihilation levels greater than 90%. Additionally, the INEL investigated the feasibility of using plutonium fuels (without uranium) for disposal in existing light water reactors and provided a preconceptual analysis for a reactor specifically designed for destruction of weapons-grade plutonium. This four-volume report was prepared for NAS to document the findings of these studies. Volume 2 evaluates 12 plutonium dispositioning options. Volume 3 considers a concept for a low-temperature, low-pressure, low-power-density, low-coolant-flow-rate light water reactor that quickly destroys plutonium without using uranium or thorium. This reactor concept does not produce electricity and has no other mission than the destruction of plutonium. Volume 4 addresses neutronic performance, fabrication technology, and fuel performance and compatibility issues for zirconium-plutonium oxide fuels and aluminum-plutonium metallic fuels. This volumes gives summaries of Volumes 2--4

Research with Neutrons at the TRIGA Mainz

International Nuclear Information System (INIS)

Hampel, Gabriele

2008-01-01

The TRIGA Mark II reactor at the Institut fuer Kernchemie of the Johannes Gutenberg-Universitaet in Mainz became first critical on August 3, 1965 and is still intensively used for basic research, applied science and educational purposes. Considering the past and future operation schedule and the low burn-up of the fuel elements (∼4 g 235 U/a), the reactor can be operated for at least the next decade taking into account the fresh fuel elements on stock and without changing spent fuels. The operation of the TRIGA Mainz has been extended very recently until the year 2020. The TRIGA Mainz can be operated in the steady state mode with a maximum power of 100 kWth and in the pulse mode with a peak power of 250 MWth. Until now, more than 16600 pulses have been carried out without any fuel failure. For irradiations the TRIGA Mainz has a central experimental tube, three pneumatic transfer systems and a rotary specimen rack with 40 positions which allows the irradiation of 80 samples at the same time. In addition, the TRIGA Mainz includes four horizontal beam ports penetrating the concrete shielding and extending inside the pool towards the reflector. A graphite thermal column provides a source of well-thermalized neutrons suitable for physical research or biological and medical irradiations. Important projects for the future of the TRIGA Mainz are the production of ultracold neutrons (UCN) and experiments with UCN, high precision mass measurements and laser spectroscopy of short-lived fission products (TRIGA-TRAP), the production of radionuclides for fast chemical separations, medical and radiopharmaceutical applications, and the use of the neutron activation analysis for the application in archeometry, solar energy technique, criminalistics and vine analysis. Furthermore, studies are performed to judge if the Boron Neutron Capture Therapy (BNCT) can be applied at the TRIGA Mainz for cancer treatment of liver metastases. Also, the reactor facility is used for the training

The neutron radiography facility at Tehran Research Reactor (TRR)

International Nuclear Information System (INIS)

Ali Pazirandeh

2009-01-01

Full text: Non-destructive testing in many fields of industry including detection of explosives, at the airports, testing for micro-cracks on airplane wings and turbine blades cracks is badly needed. Thermal neutron beam is one of preferable method to detect the micro-cracks, reveals the internal structure of components and explosives. The purpose of this paper is to present the neutron radiography facility at Tehran Research Reactor (TRR), Science and Technology Research Institute, and in particular to emphasize the industrial applications in wood industry, automobile engine inspection, minerals composition identification, turbine blade cracks detection. (author)

Status report of the program on neutron beam utilization at the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Vuong Huu Tan

1996-08-01

The thermal reactor is an intense source not only of thermal neutron, but also intermediate as well as fast neutrons. Using the filtered neutron beam technique at steady state atomic reactor allows receiving the neutrons in the intermediate energy region with the most available intense flux at present. In the near time at the Dalat reactor the filtered neutron beam technique has been applied. Utilization of the filtered neutron beams in basic and applied researches has been a important activity of the Dalat Nuclear Research Institute (DNRI). This report presents some relevant characteristics of the filtered neutron beams and their utilization in nuclear data measurements, neutron capture gamma ray spectroscopy, neutron radiography, neutron dose calibration and other applications. (author). 3 refs, 2 figs

Classifying threats with a 14-MeV neutron interrogation system.

Science.gov (United States)

Strellis, Dan; Gozani, Tsahi

2005-01-01

SeaPODDS (Sea Portable Drug Detection System) is a non-intrusive tool for detecting concealed threats in hidden compartments of maritime vessels. This system consists of an electronic neutron generator, a gamma-ray detector, a data acquisition computer, and a laptop computer user-interface. Although initially developed to detect narcotics, recent algorithm developments have shown that the system is capable of correctly classifying a threat into one of four distinct categories: narcotic, explosive, chemical weapon, or radiological dispersion device (RDD). Detection of narcotics, explosives, and chemical weapons is based on gamma-ray signatures unique to the chemical elements. Elements are identified by their characteristic prompt gamma-rays induced by fast and thermal neutrons. Detection of RDD is accomplished by detecting gamma-rays emitted by common radioisotopes and nuclear reactor fission products. The algorithm phenomenology for classifying threats into the proper categories is presented here.

Security with nuclear weapons

International Nuclear Information System (INIS)

Karp, R.C.

1991-01-01

Recent improvements in East-West relations and the process of dramatic political change in Europe may result in unprecedented opportunities to reduce the global arsenal of nuclear weapons. Despite these welcome developments, the prospects for effectively controlling the spread of nuclear capability in the Third World have remained much less encouraging. The possibility of large reductions in nuclear weapons poses fundamental questions about their purpose. Why have some states chosen to acquire nuclear weapons? How and why have these decisions been maintained over time? Why have some states elected to approach, but not cross, the nuclear threshold? This book examines the commonalities and differences in political approaches to nuclear weapons both within and between three groups of states: nuclear, non-nuclear and threshold. The chapters explore the evolution of thinking about nuclear weapons and the role these weapons play in national security planning, and question the official security rationales offered by the nuclear weapon states for the maintenance of nuclear capabilities. For the non-nuclear weapon states, the book presents an analysis of alternative ways of assuring security and foreign policy effectiveness. For the threshold states, it examines the regional contexts within which these states maintain their threshold status. This book transcends traditional East-West approaches to analysis of nuclear issues by giving equal prominence to the issues of nuclear proliferation and non-nuclearism. The book also provides a comprehensive analysis of how current approaches to nuclear weapons have evolved both within and among the groups of countries under study

Application of neutron radiography to plant research

International Nuclear Information System (INIS)

Nakanishi, Tomoko

1995-01-01

Neutron radiography was used to image plant roots in soils. Soybeans were used as experimental plants. When the length of the soybean root was 3-5 cm, the plant was transferred to an alminum foil and cultivated by adding polyvinyl alcoholic polymer (polymer A) and pulm-derived polymer (polymer B) as water absorbing polymers to soils. Plant samples were removed sequentially and irradiated with neutrons for 19 seconds at the JRR-3M neutron radiography facility. After irradiation, X-ray film images were obtained to observe water dynamics of roots and soils. Neutron images of soybean roots showed that secondary roots had grown on the side of water absorbing polymer-added soils in the case of polymer A, but on the side of non-added soils in the case of polymer B. When polymer B was added just below the soils where roots were grown, root growth was restricted only to the soil surface, and plant growth condition and dry weight were similar to those in the control plants. Thus the design of root shape may be possible by using polymer B. Similar experiment was made on 5 kinds of trees. Images of cross section of Japanese Cypress revealed that water contained in the tree is not always present along with growth ring of the tree. These findings may have an important implication for the potential application of neutron radiography in plant research. (N.K.)

Psychological markers underlying murder weapon profile: a quantitative study.

Science.gov (United States)

Kamaluddin, M R; Othman, A; Ismail, K H; Mat Saat, G A

2017-12-01

The horrific nature of murder using different types of weapons has been an important focal point of many criminological studies. Weapons that are used in murders seem to play dominant roles in murder investigations as they may provide information leading to arrest. The established factors for weapon usage include environmental context, demography and availability of weapons. However, there is insufficient research attention on the psychological functioning of murderers for particular weapon usage. In light of this, the current study seeks to narrow this gap of information by identifying the influences of psychological traits on weapon usage among a sample of male murderers. The present cross-sectional study was conducted among 71 male murderers incarcerated in 11 prisons within Peninsular Malaysia. The selection of the sample was based on predetermined selection criteria using a purposive sampling method. A guided self-administered questionnaire comprising sociodemography variables and four Malay validated psychometric instruments: Zuckerman-Kuhlman Personality Questionnaire-40-Cross-Culture, Self-control Scale, "How I Think" Questionnaire and Aggression Questionnaire; was used. Independent sample t-test was performed to establish the mean score differences of psychological traits between the murderers who used single and multiple weapons while Kruskal-Wallis tests were carried out to ascertain the differences between the specific types of weapons used among the murderers. Following this, one-way ANOVA was carried out to ascertain the psychological trait differences among the murderers according to the different sources of weapon. Results indicated specific psychological traits influenced the number(s), source(s) and type(s) of weapon used in committing murder. The findings have implications for the psychological profiling of unknown murderers within the Malaysian context.

Nuclear weapons free zones

International Nuclear Information System (INIS)

Stahl, K.

1990-01-01

The article analyses the concept and problems of the two nuclear weapons free zones in Latin America and in the South Pacific established by the Treaty of Tlatelolco and the Treaty of Rarotonga. So far the nuclear weapons states except China have refused to sign the additional protocols of the Treaties or have signed them only with considerable provisos. Therefore they don't fully recognize the nuclear weapons free status of those zones, or they don't recognize it at all. Both Treaties contain no provisions to regulate the transit of nuclear weapons through the zones. This allows de facto the stationing of nuclear weapons in the military bases of the US which are located within the nuclear weapons free zone of Latin America. The Treaty of Tlatelolco contains also the right of the states, party to the Treaty, to explode nuclear devices for peaceful purposes. Since peaceful and military nuclear explosions cannot be distinguished technically, this right could also undermine the nuclear weapons free status of the region. Important nuclear threshold countries like Argentina and Brazil have furthermore refrained from putting the Treaty into force. (orig.) [de

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.

Utilization of the research and measurement reactor Braunschweig for neutron metrology

International Nuclear Information System (INIS)

Alberts, W.G.

1982-01-01

The objectives of the Physikalisch-Technische Bundesanstalt (PTB) with regard to neutron metrology are briefly described. The use of the PTB's Research and Measuring Reactor as neutron source for metrological purposes is discussed. Reference neutron beams are described which serve as irradiation facilities for the calibration of detectors for radiation protection purposes in the frame of the legal metrology work in the PTB. (orig.) [de

Applied research and development of neutron activation analysis

International Nuclear Information System (INIS)

Chung, Yong Sam; Moon, Jong Hwa; Kim, Sun Ha; Baek, Sung Ryel; Kim, Young Gi; Jung, Hwan Sung; Park, Kwang Won; Kang, Sang Hun; Lim, Jong Myoung

2003-05-01

The aims of this project are to establish the quality control system of Neutron Activation Analysis(NAA) due to increase of industrial needs for standard analytical method and to prepare and identify the standard operation procedure of NAA through practical testing for different analytical items. R and D implementations of analytical quality system using neutron irradiation facility and gamma-ray measurement system and automation of NAA facility in HANARO research reactor are as following ; 1) Establishment of NAA quality control system for the maintenance of best measurement capability and the promotion of utilization of HANARO research reactor 2) Improvement of analytical sensitivity for industrial applied technologies and establishment of certified standard procedures 3) Standardization and development of Prompt Gamma-ray Activation Analysis (PGAA) technology

Solid polystyrene and deuterated polystyrene light output response to fast neutrons

International Nuclear Information System (INIS)

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

2016-01-01

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.

Solid polystyrene and deuterated polystyrene light output response to fast neutrons

Energy Technology Data Exchange (ETDEWEB)

Simpson, R., E-mail: raspberry@lanl.gov; Danly, C.; Merrill, F. E.; Volegov, P. L.; Wilde, C. [Los Alamos National Laboratory, Los Alamos, New Mexico 87545 (United States); Glebov, V. Yu. [Laboratory for Laser Energetics, Rochester, New York 14623 (United States); Hurlbut, C. [Eljen Technology, Sweetwater, Texas 79556 (United States)

2016-04-15

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.

Chemical Weapons Convention

National Research Council Canada - National Science Library

1997-01-01

On April 29, 1997, the Convention on the Prohibition of the Development, Production, Stockpiling, and Use of Chemical Weapons and on Their Destruction, known as the Chemical Weapons Convention (CWC...

Opportunities for research program development at LANSCE (Los Alamos Neutron Scattering Center

International Nuclear Information System (INIS)

Bowman, C.D.

1989-01-01

The availability of intense neutron beams from facilities associated with the Proton Storage Ring and LANSCE has stimulated the development of neutron research well beyond the mainstream of neutron scattering. A description of this extended program is given along with prospects for further growth. 23 refs., 11 figs., 4 tabs

High energy neutron source for materials research and development

International Nuclear Information System (INIS)

Odera, M.

1989-01-01

Requirements for neutron source for nuclear materials research are reviewed and ESNIT, Energy Selective Neutron Irradiation Test facility proposed by JAERI is discussed. Its principal aims of a wide neutron energy tunability and spectra peaking at each energy to enable characterization of material damage process are demanding but attractive goals which deserve detailed study. It is also to be noted that the requirements make a difference in facility design from those of FMIT, IFMIF and other high energy intense neutron sources built or planned to date. Areas of technologies to be addressed to realize the ESNIT facility are defined and discussed. In order to get neutron source having desired spectral characteristics keeping moderate intensity, projectile and target combinations must be examined including experimentation if necessary. It is also desired to minimize change of flux density and energy spectrum according to location inside irradiation chamber. Extended target or multiple targets configuration might be a solution as well as specimen rotation and choice of combination of projectile and target which has minimum velocity of the center of mass. Though relevant accelerator technology exists, it is to be stressed that considerable efforts must be paid, especially in the area of target and irradiation devices to get ESNIT goal. Design considerations to allow hands-on maintenance and future upgrading possibility are important either, in order to exploit the facility fully for nuclear materials research and development. (author)

Characteristics of neutron irradiation facility and dose estimation method for neutron capture therapy at Kyoto University research reactor institute

International Nuclear Information System (INIS)

Kobayashi, T.; Sakurai, Y.; Kanda, K.

2001-01-01

The neutron irradiation characteristics of the Heavy Water Neutron Irradiation Facility (HWNIF) at the Kyoto University Research Reactor Institute (KIJRRI) for boron neutron capture therapy (BNCT), is described. The present method of dose measurement and its evaluation at the KURRI, is explained. Especially, the special feature and noticeable matters were expounded for the BNCT with craniotomy, which has been applied at present only in Japan. (author)

Antisatellite weapons

International Nuclear Information System (INIS)

Garwin, R.L.; Gottfried, K.; Hafner, D.L.

1984-01-01

The authors take issue with the assessment that the advent of antisatellite weapons implies that the beneficial role of satellites in arms control, confidence building, and conflict resolution has been judged less important than their ability to support actual military operations. They argue that there is still an opportunity to negotiate a militarily significant and verifiable constraint on the growth of antisatellite technology that would be in the security interest of the US and the world as a whole. They base their opinion on an assessment of the roles of the existing military satellites and their vulnerability to antisatellite weapons and the probable impact of antisatellite weapons on various kinds of crisis and conflict. 10 figures, 1 table

Miniature neutron-alpha activation spectrometer

International Nuclear Information System (INIS)

Rhodes, Edgar; Goldsten, John; Holloway, James Paul; He, Zhong

2002-01-01

We are developing a miniature neutron-alpha activation spectrometer for in-situ analysis of chem-bio samples, including rocks, fines, ices, and drill cores, suitable for a lander or Rover platform for Mars or outer-planet missions. In the neutron-activation mode, penetrating analysis will be performed of the whole sample using a γ spectrometer and in the α-activation mode, the sample surface will be analyzed using Rutherford-backscatter and x-ray spectrometers. Novel in our approach is the development of a switchable radioactive neutron source and a small high-resolution γ detector. The detectors and electronics will benefit from remote unattended operation capabilities resulting from our NEAR XGRS heritage and recent development of a Ge γ detector for MESSENGER. Much of the technology used in this instrument can be adapted to portable or unattended terrestrial applications for detection of explosives, chemical toxins, nuclear weapons, and contraband

Simulating Neutronic Core Parameters in a Research and Test Reactor

International Nuclear Information System (INIS)

Selim, H.K.; Amin, E.A.; Koutb, M.E.

2011-01-01

The present study proposes an Artificial Neural Network (ANN) modeling technique that predicts the control rods positions in a nuclear research reactor. The neutron, flux in the core of the reactor is used as the training data for the neural network model. The data used to train and validate the network are obtained by modeling the reactor core with the neutronic calculation code: CITVAP. The type of the network used in this study is the feed forward multilayer neural network with the backpropagation algorithm. The results show that the proposed ANN has good generalization capability to estimate the control rods positions knowing neutron flux for a research and test reactor. This method can be used to predict critical control rods positions to be used for reactor operation after reload

Is the nuclear weapon taboo? The nuclear weapon is useless and expensive. Let us not leave the nuclear weapon as an inheritance

International Nuclear Information System (INIS)

Gauchet, Nathalie; Norlain, Bernard; Beach, Hugh; Beckett, Margaret; Quiles, Paul; Rocard, Michel; Ramsbotham, David

2012-03-01

Starting with the definition of the word taboo as stated in a dictionary (a topic it would be unbecoming to evoke, under social and moral proprieties), the author of the first article discusses the status of the nuclear weapon, outlining that it is expensive, useless and monstrous. She notices that conventions on chemical weapons seem to be more efficient than the NPT, that, even if the reasons for abolition are known as well as ways to reach it, it seems difficult to actually address this issue. She evokes different voices coming from different countries or international bodies calling for this abolition. She also states that the nuclear weapon is not a deterrent weapon but a weapon of domination, and calls for the mobilisation of the civil society throughout the world. A second article states that the nuclear weapon is useless and expensive, and that we have to get rid of this hazard for the sake of the planet. Former ministers, Prime ministers, and generals consider that we can and must give up nuclear weapons, notably because the strategic context has completely changed since the fall of the Berlin wall, and support the action of Global Zero

Applications of neutron powder diffraction in materials research

International Nuclear Information System (INIS)

Kennedy, S.J.

1996-01-01

The aim of this article is to provide an overview of the applications of neutron powder diffraction in materials science. The technique is introduced with particular attention to comparison with the X-ray powder diffraction technique to which it is complementary. The diffractometers and special environment ancillaries operating around the HIFAR research reactor at the Australian Nuclear Science and Technology Organisation (ANSTO) are described. Applications of the technique which the advantage of the unique properties of thermal neutrons have been selected from recent materials studies undertaken at ANSTO

Designing research of fast neutron radiation field based on the reactor

International Nuclear Information System (INIS)

Zhang Wenzhong; Zhang Xiaomin

2009-01-01

Based on the Tsinghua University experimental nuclear reactor neutron source, this research designed moderate theory technical scheme, and the thickness of materials in the scheme were selected by means of Monte Carlo simulating method. An fast neutron radiation field was gained. (authors)

Design and simulation of an optimized e-linac based neutron source for BNCT research

International Nuclear Information System (INIS)

Durisi, E.; Alikaniotis, K.; Borla, O.; Bragato, F.; Costa, M.; Giannini, G.; Monti, V.; Visca, L.; Vivaldo, G.; Zanini, A.

2015-01-01

The paper is focused on the study of a novel photo-neutron source for BNCT preclinical research based on medical electron Linacs. Previous studies by the authors already demonstrated the possibility to obtain a mixed thermal and epithermal neutron flux of the order of 10"7 cm"−"2 s"−"1. This paper investigates possible Linac’s modifications and a new photo-converter design to rise the neutron flux above 5 10"7 cm"−"2 s"−"1, also reducing the gamma contamination. - Highlights: • Proposal of a mixed thermal and epithermal (named hyperthermal) neutron source based on medical high energy electron Linac. • Photo-neutron production via Giant Dipole Resonance on high Z materials. • MCNP4B-GN simulations to design the photo-converter geometry maximizing the hyperthermal neutron flux and minimizing the fast neutron and gamma contaminations. Hyperthermal neutron field suitable for BNCT preclinical research.

Use of neutron beams for fundamental research, applications and human capacity building: From national to regional perspectives

International Nuclear Information System (INIS)

Nothnagel, S.G.

2010-01-01

The SAFARI-1 research reactor at NECSA South Africa is currently one of the best utilized research reactors in the world. Apart from being used for materials irradiation and isotope production, there is a history of innovative utilization of neutron beam line techniques, such as neutron diffraction (strain scanning, powder and single crystal), neutron radiography/tomography, prompt gamma-ray neutron activation analysis and small angle neutron scattering both for NECSA research programs and external users. Through these applications neutron beam line diagnostics have been shown to make important contributions to a number of key research areas in South Africa. As a result these techniques are now being viewed as 'standard and essential' for an increasing number of researchers who came to appreciate the extra dimension of knowledge provided by neutron techniques. In addition neutron beam line facilities provide excellent training platforms for human capacity building in nuc lear and material related science and technology. Because of these reasons neutron beam line facilities at research reactors offer unique opportunities to build productive cross-cutting research collaborations, at national and regional levels. Some information on the role that nuclear beams can play, in the capacities mentioned, will be shared by virtue of some examples and the national, international and regional net-working potential of research reactor based neutron facilities shall be discussed.

Utilization and facility of neutron activation analysis in HANARO research reactor

International Nuclear Information System (INIS)

Chung, Y.S.; Chung, Y.J.; Moon, J.H.

1998-01-01

The facilities of neutron activation analysis within a multi-purpose research reactor (HANARO) are described and the main applications of Neutron activation analysis (NAA) in Korea are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system, are installed at three irradiation holes. One irradiation hole is lined with a cadmium tube for epithermal-nal NAA. The performance of the NAA facility was examined to identify the characteristics of tube transfer system, irradiation sites and polyethylene irradiation capsule. The available thermal neutron flux with each irradiation site are in the range of 3.9x10 13 -1.6x10 14 n/cm 2 ·s and cadmium ratios are 15-250. 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. Analytical services and the latest analytical results are summarized. (author)

Burnup dependent core neutronic calculations for research and training reactors via SCALE4.4

International Nuclear Information System (INIS)

Tombakoglu, M.; Cecen, Y.

2001-01-01

In this work, the full core modelling is performed to improve neutronic analyses capability for nuclear research reactors using SCALE4.4 code system. KENOV.a module of SCALE4.4 code system is utilized for full core neutronic analysis. The ORIGEN-S module is coupled with the KENOV.a module to perform burnup dependent neutronic analyses. Results of neutronic calculations for 1 st cycle of Cekmece TR-2 research reactor are presented. In particular, coupling of KENOV.a and ORIGEN-S modules of SCALE4.4 is discussed. The preliminary results of 2-D burnup dependent neutronic calculations are also given. These results are extended to burnup dependent core calculations of TRIGA Mark-II research reactors. The code system developed here is similar to the code system that couples MCNP and ORIGEN2.(author)

Monochromatic neutron beam production at Brazilian nuclear research reactors

Science.gov (United States)

Stasiulevicius, Roberto; Rodrigues, Claudio; Parente, Carlos B. R.; Voi, Dante L.; Rogers, John D.

2000-12-01

Monochomatic beams of neutrons are obtained form a nuclear reactor polychromatic beam by the diffraction process, suing a single crystal energy selector. In Brazil, two nuclear research reactors, the swimming pool model IEA-R1 and the Argonaut type IEN-R1 have been used to carry out measurements with this technique. Neutron spectra have been measured using crystal spectrometers installed on the main beam lines of each reactor. The performance of conventional- artificial and natural selected crystals has been verified by the multipurpose neutron diffractometers installed at IEA-R1 and simple crystal spectrometer in operator at IEN- R1. A practical figure of merit formula was introduced to evaluate the performance and relative reflectivity of the selected planes of a single crystal. The total of 16 natural crystals were selected for use in the neutron monochromator, including a total of 24 families of planes. Twelve of these natural crystal types and respective best family of planes were measured directly with the multipurpose neutron diffractometers. The neutron spectrometer installed at IEN- R1 was used to confirm test results of the better specimens. The usually conventional-artificial crystal spacing distance range is limited to 3.4 angstrom. The interplane distance range has now been increased to approximately 10 angstrom by use of naturally occurring crystals. The neutron diffraction technique with conventional and natural crystals for energy selection and filtering can be utilized to obtain monochromatic sub and thermal neutrons with energies in the range of 0.001 to 10 eV. The thermal neutron is considered a good tool or probe for general applications in various fields, such as condensed matter, chemistry, biology, industrial applications and others.

Use of research reactors for neutron activation analysis. Report of an advisory group meeting

International Nuclear Information System (INIS)

2001-04-01

Neutron activation analysis (NAA) is an analytical technique based on the measurement of characteristic radiation from radionuclides formed directly or indirectly by neutron irradiation of the material of interest. In the last three decades, neutron activation analysis has been found to be extremely useful in the determination of trace and minor elements in many disciplines. These include environmental analysis applications, nutritional and health related studies, geological as well as material sciences. The most suitable source of neutrons for NAA is a research reactor. There are several application fields in which NAA has a superior position compared to other analytical methods, and there are good prospects in developing countries for long term growth. Therefore, the IAEA is making concerted efforts to promote neutron activation analysis and at the same time to assist developing Member States in better utilization of their research reactors. The purpose of the meeting was to discuss the benefits and the role of NAA in applications and research areas that may contribute towards improving utilization of research reactors. The participants focused on five specific topics: (1) Current trends in NAA; (2) The role of NAA compared to other methods of chemical analysis; (3) How to increase the number of NAA users through interaction with industries, research institutes, universities and medical institutions; (4) How to reduce costs and to maintain quality and reliability; (5) NAA using low power research reactors. Neutron activation analysis in its various forms is still active and there are good prospects in developing countries for long-term growth. This can be achieved by a more effective use of existing irradiation and counting facilities, a better end-user focus, and perhaps marginal improvements in equipment and techniques. Therefore, it is recommended that the Member States provide financial and other assistance to enhance the effectiveness of their laboratories

Types and effects of radiation coming from nuclear weapons

International Nuclear Information System (INIS)

Messerschmidt, O.

1974-01-01

The article shows which effects can be expected from an atomic explosion, such as neutron and gamma rays, pressure surge, thermal radiation and at which KT-values and at which distance from the centre influence the individual noxious substances is most pronounced. Combined effects and delayed effects are discussed. The results of the numerous studies on the effects of the A-bomb dropping on Hiroshima and Nagazaki are shown. Results of animal experiments are used for explanation. Furthermore, the effect of radioactive fallout is described. As an example, the author points out the Marshall islands on which radioactive fallout was noticed after a nuclear weapon test by the Americans. (MG) [de

Neutrons down-under: Australia's research reactor review

International Nuclear Information System (INIS)

Murray, Allan

1995-01-01

Australian research reactor review commenced in September 1992, the Review had the following Terms of Reference: Whether, on review of the benefits and costs for scientific, commercial, industrial and national interest reasons, Australia has a need for a new reactor; a review of the present reactor, HIFAR, to include: an assessment of national and commercial benefits and costs of operations, its likely remaining useful life and its eventual closure and decommissioning; if Australia has a need for a new nuclear research reactor, the Review will consider: possible locations for a new reactor, its environmental impact at alternative locations, recommend a preferred location, and evaluate matters associated with regulation of the facility and organisational arrangements for reactor-based research. From the Review findings the following recommendations were stated: keep HIFAR going; commission a PRA to ascertain HIFAR's remaining life and refurbishment possibilities; identify and establish a HLW repository; accept that neither HIFAR nor a new reactor can be completely commercial; any decision on a new neutron source must rest primarily on benefits to science and Australia's national interest; make a decision on a new neutron source in about five years' time (1998). Design Proposals for a New Reactor are specified

A Conceptual Model to Identify Intent to Use Chemical-Biological Weapons

Directory of Open Access Journals (Sweden)

Mary Zalesny

2017-10-01

Full Text Available This paper describes a conceptual model to identify and interrelate indicators of intent of non-state actors to use chemical or biological weapons. The model expands on earlier efforts to understand intent to use weapons of mass destruction by building upon well-researched theories of intent and behavior and focusing on a sub-set of weapons of mass destruction (WMD to account for the distinct challenges of employing different types of WMD in violent acts. The conceptual model is presented as a first, critical step in developing a computational model for assessing the potential for groups to use chemical or biological weapons.

Establishment of the Neutron Beam Research Facility at the OPAL Reactor

International Nuclear Information System (INIS)

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

2012-01-01

Full text: Australia's first research reactor, HIFAR, reached criticality in January 1958. At that time Australia's main agenda was establishment of a nuclear power program. HIFAR operated for nearly 50 years, providing a firm foundation for the establishment of Australia's second generation research Reactor OPAL, which reached criticality in August 006. In HIFAR's early years a neutron beam facility was established for materials characterization, partly in aid of the nuclear energy agenda and partly in response to interest from Australia's scientific community. By the time Australia's nuclear energy program ceased (in the 1970s), radioisotope production and research had also been established at Lucas Heights. Also, by this time the neutron beam facility for scientific research had evolved into a major utilization programme, warranting establishment of an independent body to facilitate scientific access (the Australian Institute for Nuclear Science and Engineering). In HIFAR's lifetime, ANSTO established a radiopharmaceuticals service for the Australian medical community and NDT silicon production was also established and grew to maturity. So when time came to determine the strategy for nuclear research in Australia into the 21st century, it was clear that the replacement for HIFAR should be multipurpose, with major emphases on scientific applications of neutron beams and medical isotope production. With this strategy in mind, ANSTO set about to design and build OPAL with a world-class neutron beam facility, capable of supporting a large and diverse scientific research community. The establishment of the neutron beam facility became the mission of the Bragg Institute management team. This journey began in 1997 with establishment of a working budget, and reached its first major objective when OPAL reached 20 MW thermal power nearly one decade later (in 2006). The first neutron beam instruments began operation soon after (in 2007), and quickly proved themselves to be

Fundamentals and applications of neutron imaging. Application part 9. Application of neutron imaging to biological research

International Nuclear Information System (INIS)

Kawabata, Yuji

2007-01-01

For radiography, the use of neutrons as a complement to X-rays is especially suitable for biological research such as plant, wood, and medical application due to the enhanced sensitivity to light elements such as hydrogen, carbon, and nitrogen. The present paper introduces applications of neutron CT to the humidity (water) distribution and its variation in the flowering plant as cut carnation, observation of water movement in refrigerated chrysanthemum leaves using very cold neutron and in cut leaves using deuterium oxide and ordinary water, measurement of water movement in sprouting cone and soy bean and growing ginseng in the soil, and other applications as to archaeological wood immersed in a restoration solution and to medical purposes. (S. Ohno)

Does Britain need nuclear weapons?

International Nuclear Information System (INIS)

Hill, C.R.; Pease, R.S.; Peierls, R.E.; Rotblat, J.

1995-01-01

This report from the British Pugwash Group follows up a detailed international study of the desirability and feasibility of a world free from nuclear weapons with an analysis of issues particular to British nuclear weapons and the associated defense policies. United Kingdom nuclear weapons are reviewed historically, as are the nuclear weapons policies of other countries. A critique of present government policy is presented, with alternative uses for nuclear weapons in the post-Cold war world. The document concludes with a summary of the text and suggests how a British government could move towards global nuclear disarmament. (UK)

Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel: Appendix B, foreign research reactor spent nuclear fuel characteristics and transportation casks. Volume 2

International Nuclear Information System (INIS)

1995-03-01

This is Appendix B of a draft Environmental Impact Statement (EIS) on a Proposed Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. It discusses relevant characterization and other information of foreign research reactor spent nuclear fuel that could be managed under the proposed action. It also discusses regulations for the transport of radioactive materials and the design of spent fuel casks

Radiation protection commissioning of neutron beam instruments at the OPAL research reactor

International Nuclear Information System (INIS)

Parkes, Alison; Saratsopoulos, John; Deura, Michael; Kenny, Pat

2008-01-01

The neutron beam facilities at the 20 MW OPAL Research Reactor were commissioned in 2007 and 2008. The initial suite of eight neutron beam instruments on two thermal neutron guides, two cold neutron guides and one thermal beam port located at the reactor face, together with their associated shielding were progressively installed and commissioned according to their individual project plans. Radiation surveys were systematically conducted as reactor power was raised in a step-wise manner to 20 MW in order to validate instrument shielding design and performance. The performance of each neutron guide was assessed by neutron energy spectrum and flux measurements. The activation of beam line components, decay times assessments and access procedures for Bragg Institute beam instrument scientists were established. The multiple configurations for each instrument and the influence of operating more than one instrument or beamline simultaneously were also tested. Areas of interest were the shielding around the secondary shutters, guide shield and bunker shield interfaces and monochromator doors. The shielding performance, safety interlock checks, improvements, radiation exposures and related radiation protection challenges are discussed. This paper discusses the health physics experience of commissioning the OPAL Research Reactor neutron beam facilities and describes health physics results, actions taken and lessons learned during commissioning. (author)

Utilization and facility of neutron activation analysis in HANARO research reactor

Energy Technology Data Exchange (ETDEWEB)

Chung, Y S; Chung, Y J; Moon, J H [Korea Atomic Energy Research Institute, P.O.Box 105 Yusong, 305-600, Taejon (Korea, Republic of)

1998-07-01

The facilities of neutron activation analysis within a multi-purpose research reactor (HANARO) are described and the main applications of Neutron activation analysis (NAA) in Korea are reviewed. The sample irradiation tube, automatic and manual pneumatic transfer system, are installed at three irradiation holes. One irradiation hole is lined with a cadmium tube for epithermal-nal NAA. The performance of the NAA facility was examined to identify the characteristics of tube transfer system, irradiation sites and polyethylene irradiation capsule. The available thermal neutron flux with each irradiation site are in the range of 3.9x10{sup 13}-1.6x10{sup 14} n/cm{sup 2}{center_dot}s and cadmium ratios are 15-250. 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. Analytical services and the latest analytical results are summarized. (author)

Neutron and gamma radiography with a research reactor

International Nuclear Information System (INIS)

Reijonen, Heikki

1973-01-01

The thesis consists of eight publications, which describe the instrumental analysis of both neutron and γ-radiography. The emphasis is on various research applications, especially solidification and segregation in Sn-Cd and Sn-In alloys. (L.M.K.)

Number distribution of leakage neutrons for single neutron emission event and one source emission event in multiplying medium for two variables - a GEANT4 study

International Nuclear Information System (INIS)

Roy, Arup Singha; Raman, Anand; Chaudhury, Probal; Thomas, Renju G.

2018-01-01

A quantitative knowledge about the neutron multiplying character of a neutron multiplying medium such as High enriched Uranium (HEU), Weapon Graded plutonium (WGPu) and similar special nuclear materials is essential for improving the probability of detection of these materials to check against illicit trafficking. The objective of this study is to gain a deeper insight in to the neutron and gamma multiplication behaviour of these materials. The leakage number distribution of neutron and gamma initiated by a source emission event (Spontaneous Fission) as well as single neutron emission event has been obtained in the course of this study. The computations for this study were carried out through GEANT4 simulation and also with the help of FREYA incorporated into it. This helped to carry out a detailed analysis of each history more realistically and obtain more reliable results

Chemical and biological weapons

International Nuclear Information System (INIS)

Harris, E.D.

1991-01-01

This paper discusses the prospects of the multilateral negotiations aimed at achieving a complete and total ban on chemical weapons the Chemical Weapons convention (CWC). The control of the proliferation of chemical weapons is no longer just on East-West issue; it is also an issue of concern in Third World Countries, and in some of the wealthier middle eastern nations, such as Kuwait

Physics Division annual progress report, January 1-December 31, 1983

International Nuclear Information System (INIS)

Trela, W.J.

1984-12-01

The Physics Division is organized into three major research areas: Weapons Physics, Inertial Fusion Physics, and Basic Research. In Weapons Physics, new strategic defensive research initiatives were developed in response to President Reagan's speech in May 1983. Significant advances have been made in high-speed diagnostics including electro-optic technique, fiber-optic systems, and imaging. In Inertial Fusion, the 40-kJ Antares CO 2 laser facility was completed, and the 1- by 1- by 2-m-long large-aperture module amplifier (LAM) was constructed and operated. In Basic Research, our main emphasis was on development of the Weapons Neutron Research (WNR) facility as a world-class pulsed neutron research facility

The US nuclear weapon infrastructure and a stable global nuclear weapon regime

Energy Technology Data Exchange (ETDEWEB)

Immele, John D [Los Alamos National Laboratory; Wagner, Richard L [Los Alamos National Laboratory

2009-01-01

US nuclear weapons capabilities -- extant force structure and nuclear weapons infrastructure as well as declared policy -- influence other nations' nuclear weapons postures, at least to some extent. This influence can be desirable or undesirable, and is, of course, a mixture of both. How strong the influence is, and its nature, are complicated, controversial, and -- in our view -- not well understood but often overstated. Divergent views about this influence and how it might shape the future global nuclear weapons regime seem to us to be the most serious impediment to reaching a national consensus on US weapons policy, force structure and supporting infrastructure. We believe that a paradigm shift to capability-based deterrence and dissuasion is not only consistent with the realities of the world and how it has changed, but also a desirable way for nuclear weapon postures and infrastructures to evolve. The US and other nuclear states could not get to zero nor even reduce nuclear arms and the nuclear profile much further without learning to manage latent capability. This paper has defined three principles for designing NW infrastructure both at the 'next plateau' and 'near zero.' The US can be a leader in reducing weapons and infrastructure and in creating an international regime in which capability gradually substitutes for weapons in being and is transparent. The current 'strategy' of not having policy or a Congressionally-approved plan for transforming the weapons complex is not leadership. If we can conform the US infrastructure to the next plateau and architect it in such a way that it is aligned with further arms reductions, it will have these benefits: The extant stockpile can be reduced in size, while the smaller stockpile still deters attack on the US and Allies. The capabilities of the infrastructure will dissuade emergence of new challenges/threats; if they emerge, nevertheless, the US will be able to deal with them in

From Russian weapons grade plutonium to MOX fuel

International Nuclear Information System (INIS)

Braehler, G.; Kudriavtsev, E.G.; Seyve, C.

1997-01-01

The April 1996, G7 Moscow Summit on nuclear matters provided a political framework for one of the most current significant challenges: ensuring a consistent answer to the weapons grade fissile material disposition issue resulting from the disarmament effort engaged by both the USA and Russia. International technical assessments have showed that the transformation of Weapons grade Plutonium in MOX fuel is a very efficient, safe, non proliferant and economically effective solution. In this regard, COGEMA and SIEMENS, have set up a consistent technical program properly addressing incineration of weapons grade plutonium in MOX fuels. The leading point of this program would be the construction of a Weapons grade Plutonium dedicated MOX fabrication plant in Russia. Such a plant would be based on the COGEMA-SIEMENS industrial capabilities and experience. This facility would be operated by MINATOM which is the partner for COGEMA-SIEMENS. MINATOM is in charge of coordination of the activity of the Russian research and construction institutes. The project take in account international standards for non-proliferation, safety and waste management. France and Germany officials reasserted this position during their last bilateral summits held in Fribourg in February and in Dijon in June 1996. MINATOM and the whole Russian nuclear community have already expressed their interest to cooperate with COGEMA-SIEMENS in the MOX field. This follows governmental-level agreements signed in 1992 by French, German and Russian officials. For years, Russia has been dealing with research and development on MOX fabrication and utilization. So, the COGEMA-SIEMENS MOX proposal gives a realistic answer to the management of weapons grade plutonium with regard to the technical, industrial, cost and schedule factors. (author)

Nuclear weapons complex

International Nuclear Information System (INIS)

Rezendes, V.S.

1992-04-01

In addition to long-standing safety and environmental problems plaguing the nuclear weapons complex, this paper reports that the Department of Energy (DOE) faces a major new challenge-how to reconfigure the weapons complex to meet the nation's defense needs in the 21st century. Key decisions still need to be made about the size of the complex; where, if necessary, to relocate various operations; what technologies to use for new tritium production; and what to do with excess weapons-grade material. The choices confronting DOE and Congress are difficult given the conflicting demands for limited resources

Nuclear research emulsion neutron spectrometry at the Little-Boy replica

International Nuclear Information System (INIS)

Gold, R.; Roberts, J.H.; Preston, C.C.

1985-10-01

Nuclear research emulsions (NRE) have been used to characterize the neutron spectrum emitted by the Little-Boy replica. NRE were irradiated at the Little-Boy surface as well as approximately 2 m from the center of the Little-Boy replica using polar angles of 0 0 , 30 0 , 60 0 and 90 0 . For the NRE exposed at 2 m, neutron background was determined using shadow shields of borated polyethylene. Emulsion scanning to date has concentrated exclusively on the 2-m, 0 0 and 2-m, 90 0 locations. Approximately 5000 proton-recoil tracks have been measured in NRE irradiated at each of these locations. Neutron spectra obtained from these NRE proton-recoil spectra are compared with both liquid scintillator neutron spectrometry and Monte Carlo calculations. NRE and liquid scintillator neutron spectra generally agree within experimental uncertainties at the 2-m, 90 0 location. However, at the 2-m, 0 0 location, the neutron spectra derived from these two independent experimental methods differ significantly. NRE spectra and Monte Carlo calculations exhibit general agreement with regard to both intensity as well as energy dependence. Better agreement is attained between theory and experiment at the 2-m, 90 0 location, where the neutron intensity is considerably higher. 14 refs., 18 figs., 11 tabs

Red China’s Capitalist Bomb: Inside the Chinese Neutron Bomb Program

Science.gov (United States)

2015-01-01

Moscow demanded, “What is the stand of the Peking leaders toward the neutron bomb and all nuclear weapons? Why have Chinese newspapers, magazines , and...for civilian and military use. Programs for laser technology, space, biotechnology , information technology, automation and manufacturing technology

The Fifth International Symposium on Advanced Nuclear Energy Research - neutrons as microscopic probes

International Nuclear Information System (INIS)

Hayter, J.B.

1994-01-01

New neutron sources being planned, such as the Advanced Neutron Source (ANS) or the European Spallation Source (ESS), will provide an order of magnitude flux increase over what is available today, but neutron scattering will still remain a signal-limited technique. At the same time, the development of new materials, such as polymer and ceramic composites or a variety of complex fluids, will increasingly require neutron-based research. This paper will discuss some of the new techniques which will allow us to make. better use of the available neutrons, either through improved instrumentation or through sample manipulation. Discussion will center primarily on unpolarized neutron techniques since polarized neutrons will be the subject of the next paper

Research of isolated resonances using the average energy shift method for filtered neutron beam

International Nuclear Information System (INIS)

Gritzay, O.O.; Grymalo, A.K.; Kolotyi, V.V.; Mityushkin, O.O.; Venediktov, V.M.

2010-01-01

This work is devoted to detailed description of one of the research directions in the Neutron Physics Department (NPD), namely, to research of resonance parameters of isolated nuclear level at the filtered neutron beam on the horizontal experimental channel HEC-8 of the WWR-M reactor. Research of resonance parameters is an actual problem nowadays. This is because there are the essential differences between the resonance parameter values in the different evaluated nuclear data library (ENDL) for many nuclei. Research of resonance parameter is possible due to the set of the neutron cross sections received at the same filter, but with the slightly shifted filter average energy. The shift of the filter average energy is possible by several processes. In this work this shift is realized by neutron energy dependence on scattering angle. This method is provided by equipment.

Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program

National Research Council Canada - National Science Library

1998-01-01

We performed the audit in response to allegations made to the Defense Hotline concerning conflicts of interest among members of the Defense Special Weapons Agency Advisory Panel on the Nuclear Weapon Effects Program...

Verifying a nuclear weapon`s response to radiation environments

Energy Technology Data Exchange (ETDEWEB)

Dean, F.F.; Barrett, W.H.

1998-05-01

The process described in the paper is being applied as part of the design verification of a replacement component designed for a nuclear weapon currently in the active stockpile. This process is an adaptation of the process successfully used in nuclear weapon development programs. The verification process concentrates on evaluating system response to radiation environments, verifying system performance during and after exposure to radiation environments, and assessing system survivability.

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)

Combined Neutron Center for European Research and Technology

International Nuclear Information System (INIS)

Lagniel, Jean-Michel

2002-01-01

High-power proton linacs are needed as driver for several applications, namely transmutation of nuclear waste using Accelerator Driven Systems (ADS), spallation neutron sources (ESS in Europe) and other fields of basic and applied research (next generation of radioactive ion beam facilities, neutrino factories, muon colliders, irradiation facilities for material testing...). The possible synergies among these projects will be pointed out and the feasibility study of high-power proton linac used as driver of a multi-user facility (CONCERT) will be presented. There was excellent scientific, technical and economic reasons to study a Combined Neutron Center for European Research and Technology (CONCERT) based on a high-power proton accelerator. Such an installation would serve condensed matter studies by spallation neutron scattering, a technological irradiation tool and R and D facility for an hybrid reactor demonstrator, a radioactive ion beam facility for nuclear physics, R and D developments for a muon/neutrino facility. The installation could therefore constitute a European center of excellence in the field of neutronics where a large number of scientific and technical executives could be trained. The CONCERT Project Team has performed the feasibility study of such a multi-user facility with: - a review of the beam needs for the different applications, - an analyze of their compatibility, - the definition of the scope of a site-independent project, - a selection of the most appropriate options regarding scientific, technical, financial, organizational and administrative aspects, - an estimation of the costs for construction, operation and the needs in manpower. The conceptual design report [17] is sufficiently detailed to minimize contingencies on those parts of the project having a large potential impact in terms of performances, costs or delays. (author)

Research activities on dosimetry for high energy neutrons

Energy Technology Data Exchange (ETDEWEB)

Yamaguchi, Yasuhiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2003-03-01

The external dosimetry research group of JAERI has been calculating dose conversion coefficients for high-energy radiations using particle transport simulation codes. The group has also been developing radiation dose measurement techniques for high-energy neutrons in collaboration with some university groups. (author)

Atomic Weapons Establishment Bill [Money

International Nuclear Information System (INIS)

Bennett, A.F.; Cryer, Bob; Carlisle, Kenneth; Dean, Paul.

1990-01-01

The debate concerns the authorisation of payment of the money required to reorganise the atomic weapons establishment in the United Kingdom provided for in the Atomic Weapons Establishment Bill in progress through Parliament. In the Bill the contractorisation of the establishment is recommended and some sort of Government owned company operated scheme set up. The debate lasted about half an hour and is reported verbatim. The issues raised concerned the actual sums likely to be incurred in the formation of a Company to carry out the designated activities of the Bill. These are connected with the research, development, production or maintenance of nuclear devices and the premises needed. The government spokesman suggested the sums required to support the Bill would not be large and the resolution was agreed to without a vote. (UK)

Nuclear weapon testing and the monkey business

International Nuclear Information System (INIS)

Murthy, M.S.S.

1978-01-01

Reasons for India's total ban on the export of rhesus monkeys to U.S. have been explained. The major reason is that some of the animals were used in nuclear weapon related radiation experiments. This was a clear violation of a stricture in the agreement about supply of monkeys. The stricture prohibited the use of animals for research concerning military operations, including nuclear weapon testing. It is pleaded that a strict enforcement of strictures rather than a total ban on the export of monkeys would be better in the interest of advancement of knowledge in human medicine and disease control. (M.G.B.)

Gamma-Free Neutron Detector Based upon Lithium Phosphate Nanoparticles

International Nuclear Information System (INIS)

Steven Wallace

2007-01-01

A gamma-free neutron-sensitive scintillator is needed to enhance radiation sensing and detection for nonproliferation applications. Such a scintillator would allow very large detectors to be placed at the perimeter of spent-fuel storage facilities at commercial nuclear power plants, so that any movement of spontaneously emitted neutrons from spent nuclear fuel or weapons grade plutonium would be noted in real-time. This task is to demonstrate that the technology for manufacturing large panels of fluor-doped plastic containing lithium-6 phosphate nanoparticles can be achieved. In order to detect neutrons, the nanoparticles must be sufficiently small so that the plastic remains transparent. In this way, the triton and alpha particles generated by the capture of the neutron will result in a photon burst that can be coupled to a wavelength shifting fiber (WLS) producing an optical signal of about ten nanoseconds duration signaling the presence of a neutron emitting source

Simulation study on the cold neutron guides in China advanced research reactor

International Nuclear Information System (INIS)

Guo Liping; Yang Tonghua; Wang Hongli; Sun Kai; Zhao Zhixiang

2003-01-01

The designs of the two cold neutron guides, CNG1 and CNG2, to be built in China advanced research reactor (CARR) are studied with Monte-Carlo simulation technique. The neutron flux density at the exit of the both guides can reach above 1 x10 9 cm -2 ·s -1 under the assumed flux spectrum of the cold neutron source. The transmission efficiency is 50% and 42%, and the maximum divergence is about 2.2 degree and 1.9 degree, respectively for CNG1 and CNG2. Neutron distribution along horizontal direction is quite uniform for both guides, with maximum fluctuation of less than 3%. Gravity can affect neutron distribution along vertical direction considerably

Underground autocatalytic-criticality potential and its implications to weapons fissile- material disposition

International Nuclear Information System (INIS)

Choi, J.-S.

1998-01-01

autocatalytic criticality and the associated consequences. Here we present our calculations of possible conditions and a mechanism for criticality in a container containing fissile material in various different chemical forms, including conditions for autocatalytic criticality. We discuss criteria for designing waste solids for the disposition of weapons fissile material so that long-term dissolution of a neutron-absorber or of fissile material would not cause criticality. These results for simplified geometries outline the conditions for a more detailed analysis of practical systems. The potential for underground criticality is also studied for other fissile waste forms, including spent fuel from commercial reactors, research reactors, and naval reactors, all of which may be destined for geologic disposal. If not carefully resolved on scientific grounds, underground criticality could potentially become the 'Achilles heel' of programmes to dispose of weapons materials and nuclear wastes. 6 refs

Neutronics analysis of the proposed 25-MW leu TRIGA Multipurpose Research Reactor

International Nuclear Information System (INIS)

Nurdin, M.; Bretscher, M.M.; Snelgrove, J.L.

1982-01-01

More than two years ago the government of Indonesia announced plans to purchase a research reactor for the Puspiptek Research Center in Serpong Indonesia to be used for isotope production, materials testing, neutron physics measurements, and reactor operator training. Reactors using low-enriched uranium (LEU) plate-type and rod-type fuel elements were considered. This paper deals with the neutronic evaluation of the rod-type 25-MW LEU TRIGA Multipurpose Research Reactor (MPRR) proposed by the General Atomic Company of the United States of America

On Line Neutron Flux Mapping in Fuel Coolant Channels of a Research Reactor

International Nuclear Information System (INIS)

Barbot, Loic; Domergue, Christophe; Villard, Jean-Francois; Destouches, Christophe; Braoudakis, George; Wassink, David; Sinclair, Bradley; Osborn, John-C.; Wu, Huayou; Blandin, C.; Thevenin, Mathieu; Corre, Gwenole; Normand, Stephane

2013-06-01

This work deals with the on-line neutron flux mapping of the OPAL research reactor. A specific irradiation device has been set up to investigate fuel coolant channels using subminiature fission chambers to get thermal neutron flux profiles. Experimental results are compared to first neutronic calculations and show good agreement (C/E ∼0.97). (authors)

Neutronic design of a 22 MW MTR type nuclear research reactor

International Nuclear Information System (INIS)

Khamis, I.; Khattab, K.; Soleman, I.; Ghazi, N.

2008-01-01

The neutronic design calculations of a 22 MW MTR type nuclear research reactor are conducted in this project. This reactor type is selected by the Arab Atomic Energy Commission in a cooperated project. The design calculations are conducted in two methods: The deterministic method, solving the neutron transport and diffusion equations using the WIMSD4 and the CITATION codes, and the probabilistic method using the MCNP code. Good agreements are noticed between the results of the multiplication factor and the neutron flux distribution which prove the accuracy of our models using the two methods. (authors)

Neutronic design of a 22 MW MTR type nuclear research reactor

International Nuclear Information System (INIS)

Khamis, I.; Khattab, K.; Soleman, I.; Ghazi, N.

2006-12-01

The neutronic design calculations of a 22 MW MTR type nuclear research reactor are conducted in this project. This reactor type is selected by the Arab Atomic Energy Commission in a cooperated project. The design calculations are conducted in two methods: The deterministic method, solving the neutron transport and diffusion equations using the WIMSD4 and the CITATION codes, and the probabilistic method using the MCNP code. Good agreements are noticed between the results of the multiplication factor and the neutron flux distribution which prove the accuracy of our models using the two methods. (author)

Use of Neutron Beams for Materials Research Relevant to the Nuclear Energy Sector

International Nuclear Information System (INIS)

2015-10-01

Nuclear technologies such as fission and fusion reactors, including associated waste storage and disposal, rely on the availability of not only nuclear fuels but also advanced structural materials. In 2010–2013, the IAEA organized and implemented the Coordinated Research Project (CRP) on Development, Characterization and Testing of Materials of Relevance to Nuclear Energy Sector Using Neutron Beams. A total of 19 institutions from 18 Member States (Argentina, Australia, Brazil, China, Czech Republic, France, Germany, Hungary, Indonesia, Italy, Japan, Netherlands, Republic of Korea, Romania, Russian Federation (two institutions), South Africa, Switzerland and United States of America) cooperated with the main objective to address the use of various neutron beam techniques for characterization, testing and qualification of materials and components produced or under development for applications in the nuclear energy sector. This CRP aimed to bring stakeholders and end users of research reactors and accelerator based neutron sources together for the enhanced use of available facilities and development of new infrastructures for applied materials research. Work envisioned under this CRP was related to the optimization and validation of neutron beam techniques, including facility and instrument modifications/optimizations as well as improved data acquisition, processing and analysis systems. Particular emphasis was placed on variable environments during material characterization and testing as required by some applications such as intensive irradiation load, high temperature and high pressure conditions, and the presence of strong magnetic fields. Targeted neutron beam techniques were neutron diffraction, small angle neutron scattering and digital neutron radiography/tomography. This publication is a compilation of the main results and findings of the CRP, and the CD-ROM accompanying this publication contains 19 reports with additional relevant technical details

Making weapons, talking peace

International Nuclear Information System (INIS)

York, H.F.

1987-01-01

The memoirs of the author traces his life from his first-year graduate studies in physics at the University of Rochester in 1942 to his present position as Director of the University of California's Institute on Global Conflict and Cooperation. The part of his life involved in making weapons extends from 1942 to 1961. During this period, he worked with E.O. Lawrence on the Manhattan Project and served as director of Livermore after it became the Atomic Energy Commission's second nuclear weapons laboratory. He also served on many government advisory boards and commissions dealing with nuclear and other weapons. In 1961, the combination of a heart attack and changes in administration in Washington led York too return to the University of California for the talking peace portion of his life. He has since become a public exponent of arms control and disarmament and the futility of seeking increased security through more and better nuclear weapons. York's explanation of his move from making weapons to talking peace leaves the reader with a puzzle

Do Weapons Facilitate Adolescent Delinquency? An Examination of Weapon Carrying and Delinquency Among Adolescents.

Science.gov (United States)

Emmert, Amanda D; Hall, Gina Penly; Lizotte, Alan J

2018-03-01

This article examines whether weapon carrying influences the frequency and variety of violent, property, and drug delinquency adolescents commit through fixed-effects analyses of data from the Rochester Youth Development Study (RYDS). We conclude that weapon carrying contributes to violent, substance, and property delinquency, and delinquent behaviors learned during weapon carrying continue to affect substance and property delinquency long after carrying has ceased.

Utilization of the Dalat Research Reactor for Radioisotope Production, Neutron Activation Analysis, Research and Training

International Nuclear Information System (INIS)

Nguyen Nhi Dien; Duong Van Dong; Cao Dong Vu; Nguyen Xuan Hai

2013-01-01

The Dalat Nuclear Research Reactor (DNRR) is a 500 kW pool type reactor loaded with a mixed core of HEU (36% enrichment) and LEU (19.75% enrichment) fuel assemblies. The reactor is used as a neutron source for the purposes of radioisotopes production, neutron activation analysis, basic and applied research and training. The reactor is operated mainly in continuous runs of 108 hours for cycles of 3–4 weeks for the above mentioned purposes. The current status of safety, operation and utilization of the reactor is given and some aspects for improvement of commercial products and services of the DNRR are also discussed in this paper. (author)

The Advanced Neutron Source (ANS) project: A world-class research reactor facility

International Nuclear Information System (INIS)

Thompson, P.B.; Meek, W.E.

1993-01-01

This paper provides an overview of the Advanced Neutron Source (ANS), a new research facility being designed at Oak Ridge National Laboratory. The facility is based on a 330 MW, heavy-water cooled and reflected reactor as the neutron source, with a thermal neutron flux of about 7.5x10 19 m -2 ·sec -1 . Within the reflector region will be one hot source which will serve 2 hot neutron beam tubes, two cryogenic cold sources serving fourteen cold neutron beam tubes, two very cold beam tubes, and seven thermal neutron beam tubes. In addition there will be ten positions for materials irradiation experiments, five of them instrumented. The paper touches on the project status, safety concerns, cost estimates and scheduling, a description of the site, the reactor, and the arrangements of the facilities

Weapons and hope

International Nuclear Information System (INIS)

Dyson, F.

1984-01-01

The British-born physicist presents a full-blown critique of US weapons policy. His careful evaluation of opposing views leads him to endorse a live-and-let-live concept of arms control, which would reject both assured destruction and first use of nuclear weapons in favor of abolishing them. Dyson's faith in the humane progress of military technology and his tolerance of dangerous conventional weapons will not please dovish readers, while his denunciation of military idolatry and his support of a nuclear freeze will disappoint some hawks. Along with moving personal memories of war and pacifism, the most original sections of the book are the author's insightful comments about the Soviet Union and the issue of verification

Feasibility studies on large sample neutron activation analysis using a low power research reactor

International Nuclear Information System (INIS)

Gyampo, O.

2008-06-01

Instrumental neutron activation analysis (INAA) using Ghana Research Reactor-1 (GHARR-1) can be directly applied to samples with masses in grams. Samples weights were in the range of 0.5g to 5g. Therefore, the representativity of the sample is improved as well as sensitivity. Irradiation of samples was done using a low power research reactor. The correction for the neutron self-shielding within the sample is determined from measurement of the neutron flux depression just outside the sample. Correction for gamma ray self-attenuation in the sample was performed via linear attenuation coefficients derived from transmission measurements. Quantitative and qualitative analysis of data were done using gamma ray spectrometry (HPGe detector). The results of this study on the possibilities of large sample NAA using a miniature neutron source reactor (MNSR) show clearly that the Ghana Research Reactor-1 (GHARR-1) at the National Nuclear Research Institute (NNRI) can be used for sample analyses up to 5 grams (5g) using the pneumatic transfer systems.

Neutron-Induced Fission Cross Section of Uranium, Americium and Curium Isotopes. Progress report - Research Contract 14485, Coordinated Research Project on Minor Actinide Neutron Reaction Data (MANREAD)

International Nuclear Information System (INIS)

Alekseev, A.A.; Bergman, A.A.; Berlev, A.I.; Koptelov, E.A.; Samylin, B.F.; Trufanov, A.M.; Fursov, B.I.; Shorin, V.S.

2009-12-01

This report contains brief description of the Lead Slowing Down Spectrometer and results of measurements of neutron-induced fission cross sections for 236 U, 242m Am, 243 Cm, 244 Cm, 245 Cm and 246 Cm done at this spectrometer. The work was partially supported through the IAEA research contract RC-14485-RD in the framework of the IAEA Coordinated Research Project 'Minor Actinide Neutron Reaction Data (MANREAD)'. The detailed description of the experimental set up, measurements procedure and data treatment can be found in the JIA-1182 (2007) and JIA-1212 (2009) reports from the Institute of Nuclear Research of the Russian Academy of Science published in Russian. Part 1 contains the first year report of the research contract and part 2 the second year report. (author)

Virtual nuclear capabilities and deterrence in a world without nuclear weapons. VERTIC research report no. 3

International Nuclear Information System (INIS)

Paloczi-Horvath, G.

1998-01-01

'Virtual nuclear capabilities' (VNC) can be defined as the ability of a state not equipped wth nuclear weapons to produce them within a matter of months or years, using fissile material and/or technological skills and materials available to it. 'Virtual nuclear deterrence' (VND) would use these capabilities to a specific end. It could be a temporary posture adopted by former nuclear weapon states as a guarantee against nuclear weapon 'break out'. VND could hence reinforce a temporary security architecture, even if in this instance 'temporary' might mean up to around ten years. In the context of getting to 'zero', VND could not be an end in itself, but rather serve as an element of the security architecture of a world free of nuclear weapons. VND would only be adopted by the acknowledged nuclear weapon states (NWS) - China, France, the Russian Federation, the United Kingdom and the United States of America - after the commit to complete nuclear disarmament, sign the appropriate treaties and perceive the temporary adoption of this form of deterrence to be in their political and security interests. As with the NWS, VND will only be accepted as an interim form of security by the de facto nuclear weapon states (DFNWS) - India, Israel and Pakistan - when they can be assured that their virtual security interests would be guaranteed by other means after they sign a nuclear disarmament treaty. There are several alternative approaches to VND. These range from various types of precise or explicit virtual deterrence to more implicit or tacit forms. An explicit VND posture might allow materials and capabilities relevant to the construction of a nuclear weapon to be retained under verified arrangements for a limited time. This report explains why explicit VND would not be a reliable tool for reinforcing a nuclear disarmament treaty, as it could undermine the treaty's whole purpose. An implicit VND posture would not permit the retention of any weapons-related fissile material or

Neutronic Design of an Accelerator Driven Sub-Critical Research Reactor

International Nuclear Information System (INIS)

Pesic, M.

2002-01-01

Conceptual design of an accelerator driven sub-critical research reactor (ADSRR), as a new project in the Vinca Institute of Nuclear Sciences, is suggested for support to the Ministry of science, technologies and development of Republic Serbia, Yugoslavia. This paper show initial results of neutronic analyses of the proposed ADSRR carried out by Monte Carlo based MCNP and SHIELD codes. According to the proposal, the ADSRR would be constructed, in a later phase, at high-energy channel H5B of the VINCY cyclotron of the TESLA Accelerator Installation, that is under completion in the Vinca Institute. The fuel elements of 80%-enriched uranium dioxide dispersed in aluminium matrix, available in the Vinca Institute, are proposed for the ADSRR core design. The HEU fuel elements are placed in aluminium tubes filled by the 'primary moderator' - light water. These 'fuel tubes' are placed in a square lattice within lead matrix in a stainless steel tank. The lead is used as a 'secondary moderator' in the core and as the axial and radial reflector. Such design of the ADSRR shows that this small low neutron flux system can be used as an experimental 'demonstration' ADS with some neutron characteristics similar to proposed well-known lead moderated and cooled power sub-critical ADS with intermediate or fast neutron spectrum. The proposed experimental ADSRR, beside usage as a valuable research machine in reactor and neutron physics, will contribute to following and developing new nuclear technologies in the country, useful for eventual nuclear power option and nuclear waste incineration in future. (author)

Status report on the cold neutron source of the Garching neutron research facility FRM-II

International Nuclear Information System (INIS)

Gobrecht, K.

1999-01-01

The new high flux research reactor of the Technical University of Munich (Technische Universitaet Muenchen, TUM) will be equipped with a cold neutron source (CNS). The centre of the CNS will be located in the D 2 O-reflector tank at 400 mm from the reactor core axis, close to the thermal neutron flux maximum. The power of 4000 W developed by the nuclear heating in the 16 litres of liquid deuterium at 25 K, and in the structures, is evacuated by a two phase thermal siphon avoiding film boiling and flooding. The thermal siphon is a single tube with counter current flow. It is inclined by 10 deg from vertical, and optimised for a deuterium flow rate of 14 g/s. Optimisation of structure design and material, as well as safety aspects will be discussed. Those parts of the structure, which are exposed to high thermal neutron flux, are made from Zircaloy 4 and 6061T6 aluminium. Structure failure due to embrittlement of the structure material under high rapid neutron flux is very improbable during the life time of the CNS (30 years). Double, in pile even triple, containment with inert gas liner guarantees lack of explosion risk and of tritium contamination to the environment. Adding a few percent of hydrogen (H 2 ) to the deuterium (D 2 ) will improve the moderating properties of our relatively small moderator volume. Nearly all of the hydrogen is bound in the form of HD molecules. A long term change of the hydrogen content in the deuterium is avoided be storing the mixture not in a gas buffer volume but as a metal hydride at low pressure. The metal hydride storage system contains two getter beds, one with 250 kg of LaCo 3 Ni 2 , the other one with 150 kg of ZrCo(0.8)Ni(0.2). Each bed can take the total gas inventory, both beds together can absorb the total gas inventory in less than 6 minutes at a pressure < 3 bar. The new reactor will have 13 beam tubes, 4 of which are looking at the cold neutron source (CNS), including two for very cold (VCN) and ultra-cold neutron (UCN

Maintaining non-nuclear weapon status

International Nuclear Information System (INIS)

Muller, H.

1991-01-01

Among the some 170 sovereign states in the world, five are legally recognized as nuclear weapon states (NWS) under the terms of the 1968 Non-Proliferation Treaty (NPT). Six countries (Argentina, Brazil, India, Israel, Pakistan, and South Africa) are counted as threshold states: they possess sizeable unsafeguarded nuclear facilities or have passed the brink of a nuclear test or of clandestine weapon production. Six other countries (Iran, Iraq, Libya, Taiwan, and North and South Korea) have been suspected periodically of either considering the nuclear weapon option or of working secretly on the development of weapons. Thus, about 150 non-nuclear weapon states (NNWS) remain which neither possess nuclear weapons nor strive to acquire them. These states are distributed throughout the globe and encompass highly industrialized as well as underdeveloped countries, liberal democracies, socialist states, sheikdoms and dictatorships. Some NNWS face acute military threats; other are far removed from the quarrels of the world, as in the case of some remote fortunate islands. Furthermore, NNWS may be members of nuclear-umbrella alliances or may have opted for a policy of neutrality or non-alignment

The return of nuclear weapons

International Nuclear Information System (INIS)

Calvez, Jean-Yves

2005-01-01

Written after the 2005 NPT review conference, this article first recalls the early stages of nuclear proliferation: acquisition of nuclear weapons by Great-Britain, USSR, France and China, and creation of the NPT in 1970. The author briefly evokes some weaknesses and violations of this treaty: emergence of new nuclear powers (India, Pakistan, Israel) and of nuclear weapon programmes (Iran, North Korea). He outlines the lack of true rules to impede countries to develop nuclear weapons, and then states that the only solution seems to be a simple abolition of these weapons. This option is notably supported by the Catholic Church as outlined and recalled here. The author discusses the situation of this abolition option, and notices that, even though NPT members committed themselves on this way, some also decided to develop new and smaller weapons. Then, it becomes always more difficult to persuade countries not to possess these weapons. The author finally discusses the issues of terrorism threat in relationship to the miniaturisation process, and regrets the lack of commitment in an abolition process

The Manuel Lujan, Jr. Neutron Scattering Center (LANSCE) experiment reports 1992 run cycle

International Nuclear Information System (INIS)

DiStravolo, M.A.

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

Does nuclear power lead to nuclear weapons

International Nuclear Information System (INIS)

Prawitz, J.

1977-01-01

It is pointed out that 'reactor grade' plutonium usually contains about 30 % Pu240 and is unsuitable for weapons. While it is possible to obtain an explosion, it is more difficult to initiate one and its effect, which will be considerably less than with bomb grade plutonium, is difficult to predict. The critical mass will be larger and more cooling required. The proliferation problem is then discussed and the four aspects, vertical, horizontal, sub-national and revolutionary, mentioned. In connection with nuclear power it is the second and third aspects which are of interest. In discussing the possibility of terrorist groups obtaining plutonium, a study by the Swedish Defence Research Institute is quoted as estimating that 10-20 qualified specialists and several years secret preparation would be necessary to make a nuclear weapon. Other authors, e.g. Ted Taylor, have maintained that it would be much easier, but examples of 'student designs' are primitive and unlikely to detonate. Even so, it is emphasised that safeguards and physical security are necessary. Horizontal proliferation is a more real problem and the NPT and IAEA safeguards are discussed in this connection. In conclusion the question of whether the proliferation of nuclear weapons via nuclear power can be prevented cannot be answered with a clear yes or no. Certain states may use nuclear weapon potential as a bargaining factor. However the decision to acquire nuclear weapons is political and while a nuclear power industry would be of help, it would not be decisively so. (JIW)

Sweden and the bomb. The Swedish plans to acquire nuclear weapons, 1945 - 1972

Energy Technology Data Exchange (ETDEWEB)

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

2001-09-01

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

Sweden and the bomb. The Swedish plans to acquire nuclear weapons, 1945 - 1972

International Nuclear Information System (INIS)

Jonter, T

2001-09-01

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. During this period

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.

Wounds and weapons

International Nuclear Information System (INIS)

Vogel, H.; Dootz, B.

2007-01-01

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

Neutron and gamma dose and spectra measurements on the Little Boy replica

International Nuclear Information System (INIS)

Hoots, S.; Wadsworth, D.

1984-01-01

The radiation-measurement team of the Weapons Engineering Division at Lawrence Livermore National Laboratory (LLNL) measured neutron and gamma dose and spectra on the Little Boy replica at Los Alamos National Laboratory (LANL) in April 1983. This assembly is a replica of the gun-type atomic bomb exploded over Hiroshima in 1945. These measurements support the National Academy of Sciences Program to reassess the radiation doses due to atomic bomb explosions in Japan. Specifically, the following types of information were important: neutron spectra as a function of geometry, gamma to neutron dose ratios out to 1.5 km, and neutron attenuation in the atmosphere. We measured neutron and gamma dose/fission from close-in to a kilometer out, and neutron and gamma spectra at 90 and 30 0 close-in. This paper describes these measurements and the results. 12 references, 13 figures, 5 tables

Some aspects of a technology of processing weapons grade plutonium to nuclear fuel

International Nuclear Information System (INIS)

Bibilashvili, Y.; Glagovsky, E.M.; Zakharkin, B.S.; Orlov, V.K.; Reshetnikov, F.G.; Rogozkin, B.G.; Soloni-N, M.I.

2000-01-01

The concept by Russia to use fissile weapons-grade materials, which are being recovered from nuclear pits in the process of disarmament, is based on an assessment of weapons-grade plutonium as an important energy source intended for use in nuclear power plants. However, in the path of involving plutonium excessive from the purposes of national safety into industrial power engineering there are a lot of problems, from which effectiveness and terms of its disposition are being dependent upon. Those problems have political, economical, financial and environmental character. This report outlines several technology problems of processing weapons-grade metallic plutonium into MOX-fuel for reactors based on thermal and fast neutrons, in particular, the issue of conversion of the metal into dioxide from the viewpoint of fabrication of pelletized MOX-fuel. The processing of metallic weapons-grade plutonium into nuclear fuel is a rather complicated and multi-stage process, every stage of which is its own production. Some of the stages are absent in production of MOX-fuel, for instance the stage of the conversion, i.e. transferring of metallic plutonium into dioxide of the ceramic quality. At this stage of plutonium utilization some tasks must be resolved as follows: I. As a result of the conversion, a material purified from ballast and radiogenic admixtures has to be obtained. This one will be applied to fabricate pelletized MOX-fuel going from morphological, physico-mechanical and technological properties. II. It is well known that metallic gallium, which is used as an alloying addition in weapons-grade plutonium, actively reacts with multiple metals. Therefore, an important issue is to study the effect of gallium on the technology of MOX-fuel production, quality of the pellets, as well as the interaction of gallium oxide with zirconium and steel shells of fuel elements depending upon the content of gallium in the fuel. The rate of the interaction of gallium oxide

Research and development activities of the Neutron Physics Division for the period January 1977-December 1978

International Nuclear Information System (INIS)

Ramanadham, M.; Joneja, O.P.

1979-01-01

The research and development programmes of the Neutron Physics Division of the Bhabha Atomic Research Centre, Bombay, for the period 1977-1978 are outlined. The fields covered include reactor (neutron) physics, fusion and plasma neutronics, biological and high precision crystallography, solid state phenomena and seismology as well as the associated workshop facilities. (K.B.)

Status report on the cold neutron source of the Garching neutron research facility FRM-II

Science.gov (United States)

Gobrecht, K.; Gutsmiedl, E.; Scheuer, A.

2002-01-01

The new high flux research reactor of the Technical University of Munich (Technische Universität München, TUM) will be equipped with a cold neutron source (CNS). The centre of the CNS will be located in the D 2O-reflector tank at 400 mm from the reactor core axis close to the thermal neutron flux maximum. The power of 4500 W developed by the nuclear heating in the 16 l of liquid deuterium at 25 K, and in the structures, is evacuated by a two-phase thermal siphon avoiding film boiling and flooding. The thermal siphon is a single tube with counter current flow. It is inclined by 10° from vertical, and optimised for a deuterium flow rate of 14 g/s. Optimisation of structure design and material, as well as safety aspects will be discussed. Those parts of the structure, which are exposed to high thermal neutron flux, are made from Zircaloy 4 and 6061T6 aluminium. Structure failure due to embrittlement of the structure material under high rapid neutron flux is very improbable during the lifetime of the CNS (30 years). Double, in pile even triple, containment with inert gas liner guarantees lack of explosion risk and of tritium contamination to the environment. Adding a few percent of hydrogen (H 2) to the deuterium (D 2) will improve the moderating properties of our relatively small moderator volume. Nearly all of the hydrogen is bound in the form of HD molecules. A long-term change of the hydrogen content in the deuterium is avoided by storing the mixture not in a gas buffer volume but as a metal hydride at low pressure. The metal hydride storage system contains two getter beds, one with 250 kg of LaCo 3Ni 2, the other one with 150 kg of ZrCo 0.8Ni 0.2. Each bed can take the total gas inventory, both beds together can absorb the total gas inventory in cold (VCN) and ultra-cold neutron (UCN) production. The latter will take place in the horizontal beam tube SR4, which will house an additional cryogenic moderator (e.g. solid deuterium). More than 60% of the experiments

Development Of A Method For Measurement Of Total Neutron Cross Sections Based On The Neutron Transmission Method Using A He-3 Counter On Filtered Neutron Beams At Dalat Research Reactor

International Nuclear Information System (INIS)

Tran Tuan Anh; Dang Lanh; Nguyen Canh Hai; Nguyen Xuan Hai; Pham Kien; Nguyen Thuy Nham; Pham Ngoc Son; Ho Huu Thang

2007-01-01

Determination of total neutron cross sections and average resonance parameters in the energy range from tens keV to hundreds keV is important for fast reactors calculations and designs because this energy range gives the most output of all neutron induced reactions in the spectrum of fast reactors. Besides, the total neutron cross section measurement is also one of the methods for determination of s, p and d-wave neutron strength functions. The purpose of this project is to develop a method for measurement of total neutron cross sections based on the neutron transmission technique using a He-3 counter. The average total neutron cross sections of 238 U were obtained from neutron transmission measurements on filtered neutron beams of 55 keV and 144 keV at the horizontal channel No.4 of the Dalat research reactor. The present results have been compared with the previous measurements, and the evaluated data from ENDF/B-6.8 library. (author)

Optimization study for an epithermal neutron beam for boron neutron capture therapy at the University of Virginia Research Reactor

International Nuclear Information System (INIS)

Burns, T.D. Jr.

1995-05-01

The non-surgical brain cancer treatment modality, Boron Neutron Capture Therapy (BNCT), requires the use of an epithermal neutron beam. This purpose of this thesis was to design an epithermal neutron beam at the University of Virginia Research Reactor (UVAR) suitable for BNCT applications. A suitable epithermal neutron beam for BNCT must have minimal fast neutron and gamma radiation contamination, and yet retain an appreciable intensity. The low power of the UVAR core makes reaching a balance between beam quality and intensity a very challenging design endeavor. The MCNP monte carlo neutron transport code was used to develop an equivalent core radiation source, and to perform the subsequent neutron transport calculations necessary for beam model analysis and development. The code accuracy was validated by benchmarking output against experimental criticality measurements. An epithermal beam was designed for the UVAR, with performance characteristics comparable to beams at facilities with cores of higher power. The epithermal neutron intensity of this beam is 2.2 x 10 8 n/cm 2 · s. The fast neutron and gamma radiation KERMA factors are 10 x 10 -11 cGy·cm 2 /n epi and 20 x 10 -11 cGy·cm 2 /n epi , respectively, and the current-to-flux ratio is 0.85. This thesis has shown that the UVAR has the capability to provide BNCT treatments, however the performance characteristics of the final beam of this study were limited by the low core power

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.

The Prospect of Neutron Scattering in The 21st Century : A Powerful Tool For Materials Research

International Nuclear Information System (INIS)

E-Kartini

2007-01-01

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 21 st 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. (author)

The spallation neutron source SINQ. A new large facility for research at PSI

International Nuclear Information System (INIS)

Bauer, G.S.; Crawford, J.F.

1994-01-01

This document is intended to familiarize the non-specialist with the principles of neutron scattering and some of its applications. It presents an overview of the foundations of neutron scattering, the basic types of instruments used, and their principles of operation. The design concept and some technical details of the spallation neutron source are described for the benefit of the scientifically or technically interested reader. In future this source will form the heart of the instruments available to PSI's wide community of neutron scattering researchers. (author) 32 figs., 1 tab

A newly developed technique of wireless remote controlled visual inspection system for neutron guides of cold neutron research facilities at HANARO

International Nuclear Information System (INIS)

Huh, Hyung; Cho, Yeong Garp; Kim, Jong In

2012-01-01

KAERI developed a neutron guide system for cold neutron research facilities at HANARO from 2003 to 2010. In 2008, the old plug shutter and instruments were removed, and a new plug and primary shutter were installed as the first cold neutron delivery system at HANARO. At the beginning of 2010, all the neutron guides and accessories had been successfully installed as well. The neutron guide system of HANARO consists of the in pile plug assembly with in pile guides, the primary shutter with in shutter guides, the neutron guides in the guide shielding room with secondary shutter, and the neutron guides in the neutron guide hall. Three kinds of glass materials were selected with optimum lengths by considering their lifetime, shielding, maintainability and cost as well. Radiation damage of the guides can occur on the coating and glass by neutron capturing in the glass. It is a big challenge to inspect a guide failure because of the difficult surrounding environment, such as high level radiation, limited working space, and massive hard work for removing and reinstalling the shielding blocks as shown in Fig 1. Therefore, KAERI has developed a wireless remote controlled visual inspection system for neutron guides using an infrared light camera mounted on the vehicle moving in the guide

System for detecting neutrons in the harsh radiation environment of a relativistic electron beam

International Nuclear Information System (INIS)

Kruse, L.W.

1978-06-01

Newly developed detectors and procedures allow measurement of neutron yield and energy in the harsh radiation environment of a relativistic electron beam source. A new photomultiplier tube design and special gating methods provide the basis for novel time-of-flight and total-yield detectors. The technique of activation analysis is expanded to provide a neutron energy spectrometer. There is a demonstrated potential in the use of the integrated system as a valuable diagnostic tool to study particle-beam fusion, intense ion-beam interactions, and pulsed neutron sources for simulating weapons effects. A physical lower limit of 10 8 neutrons into 4π is established for accurate and meaningful measurements in the REB environment

Political accountability and autonomous weapons

Directory of Open Access Journals (Sweden)

James Igoe Walsh

2015-09-01

Full Text Available Autonomous weapons would have the capacity to select and attack targets without direct human input. One important objection to the introduction of such weapons is that they will make it more difficult to identify and hold accountable those responsible for undesirable outcomes such as mission failures and civilian casualties. I hypothesize that individuals can modify their attribution of responsibility in predicable ways to accommodate this new technology. The results of a survey experiment are consistent with this; subjects continue to find responsible and hold accountable political and military leaders when autonomous weapons are used, but also attribute responsibility to the designers and programmers of such weapons.

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.

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

International Nuclear Information System (INIS)

Schefer, Juerg; Castellazzi, Denise; Shea-Braun, Margit

2001-01-01

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 14 n cm -2 s 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

Research and development activities of the Neutron Physics Division for the period January 1980 - December 1980

International Nuclear Information System (INIS)

Basu, T.K.; Bhakay-Tamhane, S.

1981-01-01

The highlights of the research and development (R and D) activities of the Neutron Physics Division of the Bhabha Atomic Research Centre, Bombay, during January - December 1980 are summarised. The R and D activities are in the fields of critical and subcritical fission systems, the plasma focus device, applied neutron physics, neutron and X-ray crystallography, materials physics and seismology. (M.G.B.)

International agreements on nuclear weapons

International Nuclear Information System (INIS)

Dombey, N.

1982-01-01

The satellite detection of a nuclear explosion in the South Atlantic and Israel's destruction of a research reactor in Iraq make it essential to strengthen existing monitoring and enforcement programs to prevent proliferation. While there was no reliable evidence that either South Africa or Iraq was violating non-proliferation agreements, worst case scenarios can demonstrate to unfriendly countries that South Africa had diverted fuel to test a nuclear weapon and that Iraq is intending to produce weapons-grade plutonium 239. The situation can be improved by formulating better terms and conditions for internationalizing access to materials. Nuclear suppliers need to agree on terms that will assure their customers that contracts for civil programs will be honored. The International Atomic Energy Agency (IAEA), which includes both nuclear suppliers and customers, could achieve stronger agreements that take into account recent technological advances that will expand enrichment and reprocessing activities. 23 references, 1 figure

Disposition of excess weapons plutonium from dismantled weapons

International Nuclear Information System (INIS)

Jardine, L.J.

1997-01-01

With the end of the Cold War and the implementation of various nuclear arms reduction agreements, US and Russia have been actively dismantling tens of thousands of nuclear weapons. As a result,large quantities of fissile materials, including more than 100 (tonnes?) of weapons-grade Pu, have become excess to both countries' military needs. To meet nonproliferation goals and to ensure the irreversibility of nuclear arms reductions, this excess weapons Pu must be placed in secure storage and then, in timely manner, either used in nuclear reactors as fuel or discarded in geologic repositories as solid waste. This disposition in US and Russia must be accomplished in a safe, secure manner and as quickly as practical. Storage of this Pu is a prerequisite to any disposition process, but the length of storage time is unknown. Whether by use as fuel or discard as solid waste, disposition of that amount of Pu will require decades--and perhaps longer, if disposition operations encounter delays. Neither US nor Russia believes that long-term secure storage is a substitute for timely disposition of excess Pu, but long-term, safe, secure storage is a critical element of all excess Pu disposition activities

Progress report on neutron scattering research. April 1, 2002 - March 31, 2003

International Nuclear Information System (INIS)

Koizumi, Satoshi; Matsuda, Masaaki; Kurihara, Kazuo

2004-03-01

This issue summarizes research progress in neutron scattering at Japan Atomic Energy Research Institute (JAERI) by utilizing the research reactor JRR-3 during the period between April 1, 2002 and March 31, 2003. (author)

Research reactor operations for neutron activation analysis

International Nuclear Information System (INIS)

Tv'ehlov, Yu.

2002-01-01

The IAEA Special Manual devoted to quality control during neutron activation analysis (NAA) on research and test reactors is discussed. Three parts of the publication involve presentation of common rules for performance of NAA, quantitative and qualitative analyses, statistic and systematic errors, safety regulations and radioactive waste management. Besides, the publication contains practical manual for the performance of NAA, and examples of different NAA regulating registration forms are presented [ru

Neutronics conceptual design of the innovative research reactor core using uranium molybdenum fuel

International Nuclear Information System (INIS)

Tukiran S; Surian Pinem; Tagor MS; Lily S; Jati Susilo

2012-01-01

The multipurpose of research reactor utilization make many countries build the new research reactor. Trend of this reactor for this moment is multipurpose reactor type with a compact core to get high neutron flux at the low or medium level of power. The research newest. Reactor in Indonesia right now is already 25 year old. Therefore, it is needed to design a new research reactor, called innovative research reactor (IRR) and then as an alternative to replace the old research reactor. The aim of this research is to get the optimal configuration of equilibrium core with the acceptance criteria are minimum thermal neutron flux is 2.5E14 n/cm 2 s at the power level of 20 MW (minimum), length of cycle of more than 40 days, and the most efficient of using fuel in the core. Neutronics design has been performed for new fuel of U-9Mo-AI with various fuel density and reflector. Design calculation has been performed using WIMSD-5B and BATAN-FUEL computer codes. The calculation result of the conceptual design shows four core configurations namely 5x5, 5x7, 6x5 and 6x6. The optimalization result for equilibrium core of innovative research reactor is the 5x5 configuration with 450 gU fuel loading, berilium reflector, maximum thermal neutron flux at reflector is 3.33E14 n/cm 2 sand length of cycle is 57 days is the most optimal of IRR. (author)

The German Debate on Tactical Nuclear Weapons

International Nuclear Information System (INIS)

Meier, Olivier

2008-01-01

This report analyses the debate in Germany about tactical nuclear weapons deployments in Europe. It is mainly based on interviews conducted with senior officials from the German Federal Foreign Ministry, the Federal Ministry of Defence, senior members of Parliament as well as experts from research institutes and think-tanks. The interviews focused on the more recent past in the German debate as well as the future of tactical nuclear weapon deployments in Germany and Europe. The report concludes that while a change of Germany's position on tactical nuclear weapons is unlikely to change in the short-term, several developments will make it unlikely that the continued involvement of Germany in NATO nuclear sharing will have to be debated in the medium term. Should the next Parliamentary elections, which will take place in 2009 at the latest, result in a Social Democrat-led government, a push for a reduction of Germany's involvement in NATO nuclear sharing appears possible. A conservative-led government is likely to maintain the nuclear status quo within NATO

Application of neutron noise analysis to a swimming pool research reactor

International Nuclear Information System (INIS)

Behringer, K.; Lescano, V.H.; Meier, F.; Phildius, J.; Winkler, H.

1982-01-01

This work is part of a programme of establishing practical applications of neutron noise techniques to a swimming pool research reactor and deals with two different items: (1) The identification of local boiling caused e.g. by a partial blockage of the coolant flow in a fuel element. Local boiling can easily lead to a burn-out situation. The onset of boiling can be detected by neutron noise analysis and a boiling detection system is presently under development. (2) The measurement of the time evolution of the reactivity induced by xenon after reactor shut-down by an on-line reactivity meter based on neutron noise analysis. From the data, the prompt neutron decay constant at delayed critical, the equilibrium xenon reactivity worth, and an estimate of the average steady-state power flux in the core before reactor shut-down were obtained. (author)

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)

Progress report on neutron scattering research. April 1, 2000 - March 31, 2001

International Nuclear Information System (INIS)

Aizawa, Kazuya; Katano, Susumu; Koizumi, Satoshi

2002-03-01

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, 2000 and March 31, 2001. (author)

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)

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)

Switzerland: Overview of activities on Neutron Imaging (NI) and Cultural Heritage (CH) studies - Paul Scherrer Institut

International Nuclear Information System (INIS)

Mannes, David

2012-01-01

Historical bronze objects play an important rule in cultural heritage research as this material was used for a broad variety of different purposes (tools, weapons, jewellery, cult objects,…) since more than 5000 years in most parts of the world (Africa, Asia, Europe). Furthermore this group of copper alloys shows high durability and has low susceptibility for corrosion, which explains the large number of objects, which have stand the test of time and wait to be studied. For the study of cultural heritage objects non-destructive testing methods are in many cases required and generally preferred. Neutron imaging provides a unique opportunity to thoroughly characterize bronze objects and to provide information on the inner structure also from larger objects while other conventional methods such as X-ray methods are restricted to surface regions of such metal objects. In the scope of this CRP we propose an interdisciplinary platform for non-destructive investigations of historical bronze objects using neutrons. The platform will provide a forum and link users from the cultural heritage area with partners from the neutron imaging community. As outcome we anticipate a document listing the possibilities and limitations of neutron imaging (such as neutron-radiography, -tomography, energy selective imaging,…) and other neutron based techniques (e.g. diffraction, PGAA,...) to investigate certain questions and problems from the cultural heritage area regarding bronze objects. The document should also contain possible methodical approaches (i.e. how to perform certain investigations) and list partners from the neutron imaging community, which could help in the planning and realization of investigations. The platform will intensify the collaboration and strengthen the connections between the involved research institutes from both areas neutron physics and cultural heritage and result in a long-lasting synergetic effect

Measuring neutron noise induced by travelling air bubbles in a research reactor

International Nuclear Information System (INIS)

Por, G.; Horanyi, S.

1983-05-01

Travelling air bubble experiments carried out in a research reactor confirm an earlier proposed model. The sink structure could be found experimentally in APSD of neutron signals and was used to determine the bubble velocity. The measurements show that neutron detectors measure the velocity of the travelling bubbles, the thermocouples that of the water flow. (author)

Upgrades of the epithermal neutron beam at the Brookhaven Medical Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Liu, Hungyuan B.; Brugger, R.M.; Rorer, D.C.

1994-12-31

The first epithermal neutron beam at the Brookhaven Medical Research Reactor (BMRR) was installed in 1988 and produced a neutron beam that was satisfactory for the development of NCT with epithermal neutrons. This beam was used routinely until 1992 when the beam was upgraded by rearranging fuel elements in the reactor core to achieve a 50% increase in usable flux. Next, after computer modeling studies, it was proposed that the Al and Al{sub 2}O{sub 3} moderator material in the shutter that produced the epithermal neutrons could be rearranged to enhance the beam further. However, this modification was not started because a better option appeared, namely to use fission plates to move the source of fission neutrons closer to the moderator and the patient irradiation position to achieve more efficient moderation and production of epithermal neutrons. A fission plate converter (FPC) source has been designed recently and, to test the concept, implementation of this upgrade has started. The predicted beam parameters will be 12 x 10{sup 9} n{sub epi}/cm{sup 2}sec accompanying with doses from fast neutrons and gamma rays per epithermal neutron of 2.8 x 10{sup -11} and < 1 x 10{sup -11} cGycm{sup 2}/n, respectively, and a current-to-flux ratio of epithermal neutrons of 0.78. This conversion could be completed by late 1996.

Influence of core model parameters on the characteristics of neutron beams of the research reactor

Directory of Open Access Journals (Sweden)

N. A. Khafizova

2013-12-01

Full Text Available IRT MEPhI reactor is equipped with a number of facilities at horizontal experimental channels (HEC. Knowing of parameters influencing spatio-angular distribution of irradiation fields is essential for each application area. The research for neutron capture therapy (NCT facility at HEC of the reactor was made. Calculation methods have been used to estimate how the reactor core parameters influence neutron beam characteristics at the HEC output. The impact of neutron source model in Monte Carlo calculations by MCNP code on the parameters of neutron and secondary photon field at the output of irradiation beam tubes of research reactor is estimated. The study shows that specifying neutron source with fission reaction rate distribution in SDEF option gives almost the same results as criticality calculation considered the most accurate. Our calculations show that changes of the core operational parameters have insignificant influence on characteristics of neutron beams at HEC output.

Upgrading of neutron radiography/tomography facility at research reactor

International Nuclear Information System (INIS)

Abd El Bar, Waleed; Mongy, Tarek

2014-01-01

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.)

Neutron imaging: A non-destructive tool for materials testing. Report of a coordinated research project 2003-2006

International Nuclear Information System (INIS)

2008-09-01

The enhancement of utilization of research reactors is one of the major objectives of the IAEA's project on Effective Utilization of Research Reactors. In particular, the improvement of existing installations for neutron imaging and the effective utilization of such facilities are intended. From the experience of Type A facilities, it is obvious that some investment is required to come from simple neutron imaging methods (film, track-etch foils) to the more enhanced ones. Related to the installation and operation of the whole reactor system, the volume of the investment for an imaging device is minor. Also compared to the installations for neutron scattering research, neutron imaging systems are relatively cheap, but very efficient in the use of the neutrons. Therefore, one of the aims of the CRP was to look for adapted solutions for the individual reactor installation and beam line. Specific Research Objectives: To optimize the neutron beams for imaging purpose using modern simulation techniques; To enhance the beam intensity using modern layout principles, neutron optics, like focusing and beam guides and filters; To develop a standardized, low cost, neutron image grabber and analyzer for efficient data collection that can be used with low intensity sources; To improve signal processing techniques used in neutron imaging applications. Expected Research Outputs: Neutron radiography is used at research reactor centres in many Member States, but the facilities are not optimized for attractive potential applications. This fact has been brought out at various discussion meetings. The CRP is aimed at improving the design of beam lines in terms of neutron collimation and intensity; Improvements in resolution are normally achieved at a cost in intensity. For an instrument exhibiting good resolution, one needs to employ a fast counting system. It is proposed to work along these lines to develop an optimised detection system. Many facilities, at present, have small CCD

Experimental validation of GADRAS's coupled neutron-photon inverse radiation transport solver

International Nuclear Information System (INIS)

Mattingly, John K.; Mitchell, Dean James; Harding, Lee T.

2010-01-01

Sandia National Laboratories has developed an inverse radiation transport solver that applies nonlinear regression to coupled neutron-photon deterministic transport models. The inverse solver uses nonlinear regression to fit a radiation transport model to gamma spectrometry and neutron multiplicity counting measurements. The subject of this paper is the experimental validation of that solver. This paper describes a series of experiments conducted with a 4.5 kg sphere of α-phase, weapons-grade plutonium. The source was measured bare and reflected by high-density polyethylene (HDPE) spherical shells with total thicknesses between 1.27 and 15.24 cm. Neutron and photon emissions from the source were measured using three instruments: a gross neutron counter, a portable neutron multiplicity counter, and a high-resolution gamma spectrometer. These measurements were used as input to the inverse radiation transport solver to evaluate the solver's ability to correctly infer the configuration of the source from its measured radiation signatures.

Prompt-gamma spectrometry for the optimization of reactor neutron beams in biomedical research

International Nuclear Information System (INIS)

Borisov, G.I.; Komkov, M.M.; Leonov, V.F.

1988-01-01

In order to select the optimal spectral composition and size for the reactor neutron beams applied to in vivo analysis and therapy in biomedical research it is necessary to determine the spatial slow-neutron flux distributions produced by the beam in the irradiated object and to calculate or measure the neutron dose equivalents of both the original spectrum and the moderated neutrons. In this study the maximum neutron dose equivalents are found by spectrometry of the prompt-γ emission from the interaction of neutrons with atomic nuclei in the irradiated object. Different spectral distributions were produced by using an unfiltered beam together with filters of quartz, cadmium, 10 B, iron, aluminum, and sulfur. The phantom used was a tank filled with an aqueous solution of urea. Cadmium-containing organs were simulated. For in vivo neutron-activation analysis of human tissues at a depth of 2-5 cm it was found advisable to use neutrons of 20-40 keV mean energy with a beam area of at least 45 cm 2

Verification of Chemical Weapons Destruction

International Nuclear Information System (INIS)

Lodding, J.

2010-01-01

The Chemical Weapons Convention is the only multilateral treaty that bans completely an entire category of weapons of mass destruction under international verification arrangements. Possessor States, i.e. those that have chemical weapons stockpiles at the time of becoming party to the CWC, commit to destroying these. All States undertake never to acquire chemical weapons and not to help other States acquire such weapons. The CWC foresees time-bound chemical disarmament. The deadlines for destruction for early entrants to the CWC are provided in the treaty. For late entrants, the Conference of States Parties intervenes to set destruction deadlines. One of the unique features of the CWC is thus the regime for verifying destruction of chemical weapons. But how can you design a system for verification at military sites, while protecting military restricted information? What degree of assurance is considered sufficient in such circumstances? How do you divide the verification costs? How do you deal with production capability and initial declarations of existing stockpiles? The founders of the CWC had to address these and other challenges in designing the treaty. Further refinement of the verification system has followed since the treaty opened for signature in 1993 and since inspection work was initiated following entry-into-force of the treaty in 1997. Most of this work concerns destruction at the two large possessor States, Russia and the United States. Perhaps some of the lessons learned from the OPCW experience may be instructive in a future verification regime for nuclear weapons. (author)

Internationalization to prevent the spread of nuclear weapons

International Nuclear Information System (INIS)

1980-01-01

The recent International Nuclear Fuel Cycle Evaluation (INFCE) has concluded that, in a world in which an increasing number of countries are using nuclear energy for peaceful purposes, no technical ways exist to prevent the spread of nuclear weapons. Non-proliferation is a political problem and must, therefore, be solved by political means. The reasons why countries want nuclear weapons - whether to meet their real or perceived security requirements or for political prestige - must be removed. Resolution of regional conflicts would diminish the stimulus for proliferation, while significant nuclear disarmament measures would de-emphasize the role of nuclear weapons in international politics. Meanwhile, institutional arrangements could minimize the risks of nuclear weapon proliferation. One such arrangement could be the internationalization of the sensitive, that is, the most proliferation-prone, elements of the nuclear fuel cycle. This book analyses some of the political, economic, technical and legal issues involved in internationalizing the nuclear fuel cycle. It consists of two parts. Part I is SIPRI's (Stockholm International Peace Research Institute) evaluation of the advantages, as well as the weaknesses, of the existing proposals for internationalization. Part II contains the papers contributed to the SIPRI symposium on 'internationalization of the nuclear fuel cycle', which was held in October/ November 1979. (author)

Non-classical neutron beams for fundamental and solid state research

International Nuclear Information System (INIS)

Rauch, H.

2008-01-01

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. (author)

Neutron guides and scientific neutron equipment at CILAS/GMI

International Nuclear Information System (INIS)

Gautier-Picard, P.

2003-01-01

CILAS company is the world's leading supplier of complete neutron guides systems. The neutron optics with multilayer coatings produced by CILAS have become an international standard for neutron beam transportation in the modern research institutes. During the last 30 years, CILAS designed, produced and installed more than 5000 meters of guides in many European, American and Asian countries. To reinforce its leadership and presence in neutron research, CILAS acquired the company Grenoble Modular Instruments (GMI), a leading company in high precision mechanics, engineering and manufacturing of spectrometers and scientific equipment for neutron and synchrotron research. (author)

CORE SIM: A multi-purpose neutronic tool for research and education

International Nuclear Information System (INIS)

Demaziere, Christophe

2011-01-01

Highlights: → A highly flexible neutronic core simulator was developed. → The tool estimates the static neutron flux, the eigenmodes, and the neutron noise. → The tool was successfully validated via many benchmark cases. → The tool can be used for research and education. → The tool is freely available. - Abstract: This paper deals with the development, validation, and demonstration of an innovative neutronic tool. The novelty of the tool resides in its versatility, since many different systems can be investigated and different kinds of calculations can be performed. More precisely, both critical systems and subcritical systems with an external neutron source can be studied, and static and dynamic cases in the frequency domain (i.e. for stationary fluctuations) can be considered. In addition, the tool has the ability to determine the different eigenfunctions of any nuclear core. For each situation, the static neutron flux, the different eigenmodes and eigenvalues, the first-order neutron noise, and their adjoint functions are estimated, as well as the effective multiplication factor of the system. The main advantages of the tool, which is entirely MatLab based, lie with the robustness of the implemented numerical algorithms, its high portability between different computer platforms and operative systems, and finally its ease of use since no input deck writing is required. The present version of the tool, which is based on two-group diffusion theory, is mostly suited to investigate thermal systems. The definition of both the static and dynamic core configurations directly from the static macroscopic cross-sections and their fluctuations, respectively, makes the tool particularly well suited for research and education. Some of the many benchmark cases used to validate the tool are briefly reported. The static and dynamic capabilities of the tool are also demonstrated for the following configurations: a vibrating control rod, a perturbation traveling upwards

HANARO Neutron Radiography Facility and Fuel Cell Research

International Nuclear Information System (INIS)

Kim, Taejoo

2013-01-01

Fuel cell which generates electric energy from hydrogen and oxygen is one of noticed renewable energy system because this has high efficiency and free from CO 2 . Especially, PEMFC (Polymer Electrolyte Membrane Fuel Cell) is focused by automotive companies because PEMFC, which has high power rate per volume and low operating temperature (60∼80), is suited due to the compact design and short start-up time. The water management is one of the most critical issues for fuel cell commercialization. In order to make a proper scheme for water management, thein formation of water distribution and behavior is very important. Neutron imaging is the best method to visualize the water at fuel cell and has been applied worldwide with qualitative and quantitative results. Because the NRF has large beam size (350Χ450mm 2 ) and relatively high neutron flux (2Χ107 n/cm 2 sec), it is suitable for large scale fuel cell research. Neutron imaging technique was used to investigate the water distribution and behavior in PEMFC under different operating conditions. The NRF has contributed the improvement of fuel cell performance and is one of the best choices for fuel cell study

Basic and Applied Research at the Los Alamos Neutron Science Center

International Nuclear Information System (INIS)

Lisowski, P.W.

2003-01-01

The Los Alamos Neutron Science Center, or LANSCE, is an accelerator-based national user facility for research in basic and applied science. At present LANSCE has two experimental areas primarily using neutrons generated by 800-MeV protons striking tungsten target systems. A third area uses the proton beam for radiography. This paper describes the three LANSCE experimental areas, gives highlights of the past operating period, and discusses plans for the future

Weapons Storage Area Survey of Munitions Storage Igloos at Medina Annex, San Antonio, Texas

Science.gov (United States)

2013-11-13

Attachment 2 Contaminants of Concern 1. General. Early nuclear weapons used polonium -beryllium (Po-Be) initiators to generate neutrons during the... foods . b. Compositions. Figure 2-1 is a histogram of key isotopic mixtures of uranium by mass. The composition for DU is a moderately depleted...200 199 230 210 255 286 Min = 171 6 258 193 243 199 188 196 171 212 190 210 207 223 203 211 214 237 257 Median = 209 A B C D E F G H I J K L M N O P Q

Weapons of mass destruction - current security threat

International Nuclear Information System (INIS)

Durdiak, J.; Gafrik, A.; Pulis, P.; Susko, M.

2005-01-01

This publication brings a complex and comprehensive view of the weapons of mass destruction phenomenon in the context of present military and political situation. It emphasizes the threat posed by proliferation of these destructive devices and their carriers as well as the threat present in their possession by unpredictable totalitarian regimes or terrorist groups. The publication is structured into four basic parts: Introduction Into The Topic, Nuclear Weapons, Chemical Weapons and Biological Weapons. The Introduction reflects the latest developments on the field of military technologies, which lead to the development of new destructive devices with characteristics comparable to basic types of WMDs - nuclear, chemical and biological. Based on the definition of WMD as 'weapon systems with enormous impact causing mass destruction, population, equipment and material losses', the modern mass destruction devices are assorted here, such as ecological, radiological and beam weapons, aerosol and container intelligent ammunition, the outburst of dangerous chemical substances from infrastructure, non-conventional weapons and military devices. The Nuclear Weapons part depicts the most destructive device of mass destruction mankind ever invented in close detail. It maps the history of most significant discoveries in nuclear physics, development and construction of the first nuclear weapons, accumulation of nuclear warheads and their carriers in the Cold war era, attempts of nuclear disarmament and reducing the number of nuclear weapons in possession of superpowers and their proliferation in the world's crisis regions including North Korea and Iran. The chapters devoted to theoretical grounds and physical principles of nuclear and thermonuclear weapons' functioning, the main categories and types, as well as destructive effects and consequences of use contain an adequate mathematical apparatus. This chapter's conclusion brings the overview of nuclear armament of states that

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

Global strike hypersonic weapons

Science.gov (United States)

Lewis, Mark J.

2017-11-01

Beginning in the 1940's, the United States has pursued the development of hypersonic technologies, enabling atmospheric flight in excess of five times the speed of sound. Hypersonic flight has application to a range of military and civilian applications, including commercial transport, space access, and various weapons and sensing platforms. A number of flight tests of hypersonic vehicles have been conducted by countries around the world, including the United States, Russia, and China, that could lead the way to future hypersonic global strike weapon systems. These weapons would be especially effective at penetrating conventional defenses, and could pose a significant risk to national security.

Calculation And Design Of A New Configuration For Radiation Shielding At Neutron Beam No.3 For Fundamental And Applied Researches

International Nuclear Information System (INIS)

Vuong Huu Tan; Tran Tuan Anh; Nguyen Kien Cuong; Nguyen Canh Hai; Nguyen Xuan Hai; Pham Ngoc Son; Ho Huu Thang

2011-01-01

The tangential horizontal channel of No. 3 of the Dalat Research Reactor has been opened and used during the 1990s. The utilizations of the thermal neutron beam at this channel were the Neutron Radiography and the Prompt Gamma Neutron Activation Analysis method (PGNAA). At present, the neutron beam used for nuclear structure data researches based on the Summing of Amplitude Coincident Pulses system (SACP). Beside, several related research equipments have been set up and operated for the research purposes. A renovation of the neutron channel, therefore, will play an important role in safe and effective utilizations of the neutron beam in fields of nuclear physic training and researches. A new configuration for radiation shielding has been simulated by MCNP code. The calculated results of dose rates for neutron and gamma at working positions are in range of dose rate limit. (author)

Few-Nucleon Research at TUNL: Probing Two- and Three-Nucleon Interactions with Neutrons

Science.gov (United States)

Howell, C. R.; Tornow, W.; Witała, H.

2016-03-01

The central goal of few-nucleon research at the Triangle Universities Nuclear Laboratory (TUNL) is to perform measurements that contribute to advancing ab-initio calculations of nuclear structure and reactions. The program aims include evaluating theoretical treatments of few-nucleon reaction dynamics through strategically comparing theory predictions to data, determining properties of the neutron-neutron interaction that are not accessible in two-nucleon reactions, and searching for evidence of longrange features of three-nucleon interactions, e.g., spin and isospin dependence. This paper will review studies of three- and four-nucleon systems at TUNL conducted using unpolarized and polarized neutron beams. Measurements of neutron-induced reactions performed by groups at TUNL over the last six years are described in comparison with theory predictions. The results are discussed in the context of the program goals stated above. Measurements of vector analyzing powers for elastic scattering in A=3 and A=4 systems, differential cross sections for neutron-deuteron elastic scattering and neutrondeuteron breakup in several final-state configurations are described. The findings from these studies and plans for the coming three years are presented in the context of worldwide activities in this front, in particular, research presented in this session.

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.

The Manuel Lujan, Jr. Neutron Scattering Center, LANSCE experiment reports: 1990 Run Cycle

International Nuclear Information System (INIS)

DiStravolo, M.A.

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 65μA 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

Progress in the neutronic core conversion (HEU-LEU) analysis of Ghana research reactor-1.

Energy Technology Data Exchange (ETDEWEB)

Anim-Sampong, S.; Maakuu, B. T.; Akaho, E. H. K.; Andam, A.; Liaw, J. J. R.; Matos, J. E.; Nuclear Engineering Division; Ghana Atomic Energy Commission; Kwame Nkrumah Univ. of Science and Technology

2006-01-01

The Ghana Research Reactor-1 (GHARR-1) is a commercial version of the Miniature Neutron Source Reactor (MNSR) and has operated at different power levels since its commissioning in March 1995. As required for all nuclear reactors, neutronic and thermal hydraulic analysis are being performed for the HEU-LEU core conversion studies of the Ghana Research Reactor-1 (GHARR-1) facility, which is a commercial version of the Miniature Neutron Source Reactor (MNSR). Stochastic Monte Carlo particle transport methods and tools (MCNP4c/MCNP5) were used to fine-tune a previously developed 3-D MCNP model of the GHARR-1 facility and perform neutronic analysis of the 90.2% HEU reference and candidate LEU (UO{sub 2}, U{sub 3}Si{sub 2}, U-9Mo) fresh cores with varying enrichments from 12.6%-19.75%. In this paper, the results of the progress made in the Monte Carlo neutronic analysis of the HEU reference and candidate LEU fuels are presented. In particular, a comparative performance assessment of the LEU with respect to neutron flux variations in the fission chamber and experimental irradiation channels are highlighted.

Neutronics analysis of Dalat Nuclear Research Reactor by MVP/GMVP code

International Nuclear Information System (INIS)

Nguyen Kien Cuong; Toru Obara

2008-01-01

The paper presents neutronics calculation for Dalat Nuclear Research Reactor (DNRR) to validate MVP/GMVP Code. Beside fresh core calculation, burnt core and burn up distribution were also carried out and compared with experimental data or result obtained from other codes. With complex geometry and operating history like DNRR, burn up calculation by Monte Carlo Method is the better choice owing to the use of exact geometry description and continuous neutron energy in calculation. The discrepancy between calculated data and experimental data is good to compare. By using Monte Carlo method, continuous neutron energy from JENDL3.3 library and combined with burn up calculation, MVP/GMVP Code is a very useful tool for reactor calculation. (author)

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.

For a convention for nuclear weapon elimination

International Nuclear Information System (INIS)

2008-03-01

This document contains two texts linked with the project of an international convention for the elimination of nuclear weapons (the text of this project has been sent to the UN General Secretary and is part of an international campaign to abolish nuclear weapons, ICAN). These two texts are contributions presented in London at the Global Summit for a Nuclear Weapon-free World. The first one calls into question the deterrence principle and the idea of a nuclear weapon-based security. It calls for different forms of action to promote a nuclear weapon-free world. The second text stresses the role and the responsibility of states with nuclear weapons in nuclear disarmament and in the reinforcement of the nuclear non proliferation treaty (NPT)

Neutron nuclear physics under the neutron science project

Energy Technology Data Exchange (ETDEWEB)

Chiba, Satoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1997-11-01

The concept of fast neutron physics facility in the Neutron Science Research project is described. This facility makes use of an ultra-short proton pulse (width < 1 ns) for fast neutron time-of-flight works. The current design is based on an assumption of the maximum proton current of 100 {mu}A. Available neutron fluence and energy resolution are explained. Some of the research subjects to be performed at this facility are discussed. (author)

Nuclear power and weapons proliferation

International Nuclear Information System (INIS)

Greenwood, T.; Rathjens, C.W.; Ruina, J.

1977-01-01

The relationship between nuclear weapons development and nuclear electric power is examined. A brief description of nuclear weapons design is first given. This is then followed by a discussion of various aspects of nuclear power technology and of how they affect a nuclear weapon programme. These include fuel cycles, chemical reprocessing of spent fuel, uranium enrichment, and the control of dissemination of nuclear technology. In conclusion there is a discussion of possible political and institutional controls for limiting nuclear proliferation. (U.K.)

Proposed nuclear weapons nonproliferation policy concerning foreign research reactor spent nuclear fuel. Summary

International Nuclear Information System (INIS)

1995-03-01

The United States Department of Energy and United States Department of State are jointly proposing to adopt a policy to manage spent nuclear fuel from foreign research reactors. Only spent nuclear fuel containing uranium enriched in the United States would be covered by the proposed policy. The purpose of the proposed policy is to promote U.S. nuclear weapons nonproliferation policy objectives, specifically by seeking to reduce highly-enriched uranium from civilian commerce. This is a summary of the Draft Environmental Impact Statement. Environmental effects and policy considerations of three Management Alternative approaches for implementation of the proposed policy are assessed. The three Management Alternatives analyzed are: (1) acceptance and management of the spent nuclear fuel by the Department of Energy in the United States, (2) management of the spent nuclear fuel at one or more foreign facilities (under conditions that satisfy United States nuclear weapons nonproliferation policy objectives), and (3) a combination of components of Management Alternatives 1 and 2 (Hybrid Alternative). A No Action Alternative is also analyzed. For each Management Alternative, there are a number of alternatives for its implementation. For Management Alternative 1, this document addresses the environmental effects of various implementation alternatives such as varied policy durations, management of various quantities of spent nuclear fuel, and differing financing arrangements. Environmental impacts at various potential ports of entry, along truck and rail transportation routes, at candidate management sites, and for alternate storage technologies are also examined. For Management Alternative 2, this document addresses two subalternatives: (1) assisting foreign nations with storage; and (2) assisting foreign nations with reprocessing of the spent nuclear fuel

A Small-Animal Irradiation Facility for Neutron Capture Therapy Research at the RA-3 Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Emiliano Pozzi; David W. Nigg; Marcelo Miller; Silvia I. Thorp; Amanda E. Schwint; Elisa M. Heber; Veronica A. Trivillin; Leandro Zarza; Guillermo Estryk

2007-11-01

The National Atomic Energy Commission of Argentina (CNEA) has constructed a thermal neutron source for use in Boron Neutron Capture Therapy (BNCT) applications at the RA-3 research reactor facility located in Buenos Aires. The Idaho National Laboratory (INL) and CNEA have jointly conducted some initial neutronic characterization measurements for one particular configuration of this source. The RA-3 reactor (Figure 1) is an open pool type reactor, with 20% enriched uranium plate-type fuel and light water coolant. A graphite thermal column is situated on one side of the reactor as shown. A tunnel penetrating the graphite structure enables the insertion of samples while the reactor is in normal operation. Samples up to 14 cm height and 15 cm width are accommodated.

Polarized neutrons

International Nuclear Information System (INIS)

Williams, W.G.

1988-01-01

The book on 'polarized neutrons' is intended to inform researchers in condensed matter physics and chemistry of the diversity of scientific problems that can be investigated using polarized neutron beams. The contents include chapters on:- neutron polarizers and instrumentation, polarized neutron scattering, neutron polarization analysis experiments and precessing neutron polarization. (U.K.)

Basic to industrial research on neutron platform in Japan

Indian Academy of Sciences (India)

Building on these successes, a new spallation neutron source (KENS) was con- structed at KEK (the present High Energy Accelerator Research Organization) in. 618. Pramana – J. Phys., Vol. 71, No. ... Ministry of Education, Science and Culture (MONBUSHO) planned the Hadron. Project consisting of four major facilities ...

Effects of the use of ABC weapons

International Nuclear Information System (INIS)

Karl-Rueckert, E.

1980-01-01

The effects of ABC-weapons are presented. The various classes of chemical weapons and their effects are discussed. It is pointed out that there is hardly a means of protection against these weapons. (MG) [de

Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods

International Nuclear Information System (INIS)

Liu, Shichang; Wang, Guanbo; Liang, Jingang; Wu, Gaochen; Wang, Kan

2015-01-01

Highlights: • DRAGON & DONJON were applied in burnup calculations of plate-type research reactors. • Continuous-energy Monte Carlo burnup calculations by RMC were chosen as references. • Comparisons of keff, isotopic densities and power distribution were performed. • Reasons leading to discrepancies between two different approaches were analyzed. • DRAGON & DONJON is capable of burnup calculations with appropriate treatments. - Abstract: The burnup-dependent core neutronics analysis of the plate-type research reactors such as JRR-3M poses a challenge for traditional neutronics calculational tools and schemes for power reactors, due to the characteristics of complex geometry, highly heterogeneity, large leakage and the particular neutron spectrum of the research reactors. Two different theoretical approaches, the deterministic and the stochastic methods, are used for the burnup-dependent core neutronics analysis of the JRR-3M plate-type research reactor in this paper. For the deterministic method the neutronics codes DRAGON & DONJON are used, while the continuous-energy Monte Carlo code RMC (Reactor Monte Carlo code) is employed for the stochastic one. In the first stage, the homogenizations of few-group cross sections by DRAGON and the full core diffusion calculations by DONJON have been verified by comparing with the detailed Monte Carlo simulations. In the second stage, the burnup-dependent calculations of both assembly level and the full core level were carried out, to examine the capability of the deterministic code system DRAGON & DONJON to reliably simulate the burnup-dependent behavior of research reactors. The results indicate that both RMC and DRAGON & DONJON code system are capable of burnup-dependent neutronics analysis of research reactors, provided that appropriate treatments are applied in both assembly and core levels for the deterministic codes

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...

Research in an emerging 'big science' discipline. The case of neutron scattering in Spain

International Nuclear Information System (INIS)

Borja Gonzalez-Albo; Maria Bordons; Pedro Gorria

2010-01-01

Neutron scattering (NS) is a 'big science' discipline whose research spans over a wide spectrum of fields, from fundamental or basic science to technological applications. The objective of this paper is to track the evolution of Spanish research in NS from a bibliometric perspective and to place it in the international context. Scientific publications of Spanish authors included in the Web of Science (WoS 1970-2006) are analysed with respect to five relevant dimensions: volume of research output, impact, disciplinary diversity, structural field features and internationalisation. NS emerges as a highly internationalised fast-growing field whose research is firmly rooted in Physics, Chemistry and Engineering, but with applications in a wide range of fields. International collaboration links -present in around 70% of the documents- and national links have largely contributed to mould the existing structure of research in the area, which evolves around major neutron scattering facilities abroad. The construction of a new European neutron source (ESS) would contribute to the consolidation of the field within the EU, since it will strengthen research and improve current activity. (author)

A Poor Man's Nuclear Deterrent: Assessing the Value of Radiological Weapons for State Actors

Science.gov (United States)

Donohue, Nathan

The threat of weapons of mass destruction is an issue which remains at the forefront on national security. Nuclear, chemical, and biological weapons are all considered very dangerous by both state and non-state actors. Radiological weapons exist in that same category yet are not held in the same regard; the reason that is given is that these types of weapons are not the weapons of mass destruction that the other three are. Instead, radiological weapons are better considered weapons of mass disruption. Accordingly, in the academic and policy literature there has been very little perceived value associated with such weapons for use by state actors. However the historical focus on the military efficacy of radiological weapons has obscured the obvious truth that they may pose significant value for state actors. What this research shows is that the explosion of a radiological weapon could disrupt a target area in ways which could cripple the economy of an adversary state and promote widespread fear concerning exposure to radiation. Any such attack would not only necessitate large scale evacuation, but cleanup, decontamination, demolition, territory exclusion, and relocation. Moreover, the effects of such an attack would be unlikely to remain an isolated event as evacuated and displaced citizens spread across the nation carrying both fear and residual radiation. All of these factors would only be compounded by a state actor's ability to not only develop such weapons, but to manufacture them in such a composition that contemporary examples of such weapons grossly underestimate their impact. Accordingly, radiological weapons could hold great value for any state actor wishing to pursue their development and to threaten their use. Moreover, "while RDDs may not be well suited as "military weapons" in the classic sense, the use of RDDs could be powerfully coercive."1 In that sense, state actors could even acquire radiological weapons for their deterrent value. 1James L. Ford

Bulk hydrogen analysis, using neutrons. Final report of the second research co-ordination meeting

International Nuclear Information System (INIS)

1998-11-01

The aims of the Second Co-ordination Meting (RCM) of the Coordinated Research Programme (CRP) were to report on and review progress against the work programme set at the beginning of the CRP and to discuss the work plans for the second half of the programme. In many cases hydrogen is required to be measured in a bulk medium rather than merely at a surface. For this reason neutrons are used due to their high penetrating power in dense material. In addition, the mass attenuation coefficient for neutrons in hydrogen is significantly larger than for all other elements, meaning that neutrons have a higher probability of interacting with hydrogen than with other elements in the sample matrix. Neutrons have been used in the following areas: Fast Neutron Transmission, Scattering and Activation Technique; Digital Neutron Imaging; Hydrogen Detection by Epithermal Neutrons; Microscopic Behaviour of Hydrogen in Bulk Materials

Next generation neutron scattering at Neutron Science Center project in JAERI

International Nuclear Information System (INIS)

Yamada, Yasusada; Watanabe, Noboru; Niimura, Nobuo; Morii, Yukio; Katano, Susumu; Aizawa, Kazuya; Suzuki, Jun-ichi; Koizumi, Satoshi; Osakabe, Toyotaka.

1997-01-01

Japan Atomic Energy Research Institute (JAERI) has promoted neutron scattering researches by means of research reactors in Tokai Research Establishment, and proposes 'Neutron Science Research Center' to develop the future prospect of the Tokai Research Establishment. The scientific fields which will be expected to progress by the neutron scattering experiments carried out at the proposed facility in the Center are surveyed. (author)

Nuclear power and nuclear weapons

International Nuclear Information System (INIS)

Vaughen, V.C.A.

1983-01-01

The proliferation of nuclear weapons and the expanded use of nuclear energy for the production of electricity and other peaceful uses are compared. The difference in technologies associated with nuclear weapons and nuclear power plants are described

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.)

Cylindrical IEC neutron source design for driven research reactor operation

International Nuclear Information System (INIS)

Miley, G.H.; Ulmen, B.; Amadio, G.; Leon, H.; Hora, H.

2009-01-01

A resurgence in nuclear power use is now underway worldwide. However, due many university research reactors shutdown, they must rely on using subcritical assemblies which employs a cylindrical Inertial Electrostatic Confinement (IEC) device to provide a fusion neutron source. The source is inserted in a fuel element position, with its power input controlled externally at a control panel. This feature opens the way to use of the critical assembly for a number of transient experiments such as sub-critical pulsing and neutron wave propagation. That in turn adds important new insights and excitement for the student teaching laboratory. (author)

Polymer research by neutron scattering

International Nuclear Information System (INIS)

Richter, D.

1993-01-01

Polymer physics aims on an understanding of the macroscopic behavior of polymer systems on the basis of their molecular structure and dynamics. For this purpose neutrons serve as a unique probe, allowing a simultaneous investigation of polymer structure and dynamics on a molecular scale. Furthermore, hydrogen deuterium exchange facilitates molecular labeling and offers the possibility to observe selected chains or chain parts in dense systems. Neutron small angle scattering reveals information on the conformation and possible aggregation of polymer chains. Data on linear and star like molecules are shown as examples. High resolution neutron spin-echospectroscopy observes the molecular dynamics of long chain molecules. Results on the large scale motion of chins in polymer melts are presented. finally, experiments on chain relaxation close to the glass transition are displayed. Three distinctly different relaxation processes are revealed. (author)

Research on application of system of neutron, thermohydraulic and safety analysis codes in order to simulation of the Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Pham Van Lam; Le Vinh Vinh; Huynh Ton Nghiem

2004-01-01

Requirements of neutron, thermohydraulic and safety analysis calculation are very important because of issuing new version of SAR for DNRR, research on construction of new research reactor and nuclear power plant. Research on application of system of neutron, thermohydraulic and safety analysis codes in order to simulation of the Dalat Nuclear Research Reactor has been done in the frame work of research theme in the year 2002-2003. The purposes of the research are maintaining safety operation of the DNRR and enhancement of man power and calculation and safety analysis tool potential. (author)

Design of small-animal thermal neutron irradiation facility at the Brookhaven Medical Research Reactor

International Nuclear Information System (INIS)

Liu, H.B.

1996-01-01

The broad beam facility (BBF) at the Brookhaven Medical Research Reactor (BMRR) can provide a thermal neutron beam with flux intensity and quality comparable to the beam currently used for research on neutron capture therapy using cell-culture and small-animal irradiations. Monte Carlo computations were made, first, to compare with the dosimetric measurements at the existing BBF and, second, to calculate the neutron and gamma fluxes and doses expected at the proposed BBF. Multiple cell cultures or small animals could be irradiated simultaneously at the so-modified BBF under conditions similar to or better than those individual animals irradiated at the existing thermal neutron irradiation Facility (TNIF) of the BMRR. The flux intensity of the collimated thermal neutron beam at the proposed BBF would be 1.7 x 10 10 n/cm 2 ·s at 3-MW reactor power, the same as at the TNIF. However, the proposed collimated beam would have much lower gamma (0.89 x 10 -11 cGy·cm 2 /n th ) and fast neutron (0.58 x 10 -11 cGy·cm 2 /n th ) contaminations, 64 and 19% of those at the TNIF, respectively. The feasibility of remodeling the facility is discussed

Few-Nucleon Research at TUNL: Probing Two- and Three-Nucleon Interactions with Neutrons

Directory of Open Access Journals (Sweden)

Howell C.R.

2016-01-01

Full Text Available The central goal of few-nucleon research at the Triangle Universities Nuclear Laboratory (TUNL is to perform measurements that contribute to advancing ab-initio calculations of nuclear structure and reactions. The program aims include evaluating theoretical treatments of few-nucleon reaction dynamics through strategically comparing theory predictions to data, determining properties of the neutron-neutron interaction that are not accessible in two-nucleon reactions, and searching for evidence of longrange features of three-nucleon interactions, e.g., spin and isospin dependence. This paper will review studies of three- and four-nucleon systems at TUNL conducted using unpolarized and polarized neutron beams. Measurements of neutron-induced reactions performed by groups at TUNL over the last six years are described in comparison with theory predictions. The results are discussed in the context of the program goals stated above. Measurements of vector analyzing powers for elastic scattering in A=3 and A=4 systems, differential cross sections for neutron-deuteron elastic scattering and neutrondeuteron breakup in several final-state configurations are described. The findings from these studies and plans for the coming three years are presented in the context of worldwide activities in this front, in particular, research presented in this session.

Terror weapons. Ridding the world of nuclear, biological and chemical weapons - Commission on mass destruction weapons; Armes de terreur. Debarrasser le monde des armes nucleaires, biologiques et chimiques - Commission sur les armes de destruction massive

Energy Technology Data Exchange (ETDEWEB)

Blix, H.; Journe, V.

2010-07-01

This book approaches in 8 chapters the ambitious challenge of ridding the world of all mass destruction weapons: 1 - re-launching disarmament; 2 - terror weapons: nature of threats and answers (weakness of traditional answers, counter-proliferation); 3 - nuclear weapons: preventing proliferation and terrorism, reducing threat and nuclear weapons number, from regulation to banning); 4 - biological or toxin weapons; 5 - chemical weapons; 6 - vectors, anti-missile defenses and space weapons; 7 - exports control, international assistance and non-governmental actors; 8 - respect, verification, enforcement and role of the United Nations. The recommendations and works of the Commission are presented in appendix together with the declaration adopted on April 30, 2009. (J.S.)

Research of boron conversion coating in neutron detector with boron deposited GEM

International Nuclear Information System (INIS)

Ye Di; Sun Zhijia; Zhou Jianrong; Wang Yanfeng; Yang Guian; Xu Hong; Chen Yuanbai; Xiao Yu; Diao Xungang

2014-01-01

GEM is a flourishing new gas detector and nowadays its technology become more mature. It has outstanding properties, such as excellent position resolution, high counting rate, radiation resistance, simple and flexible signal readout, can be large-area detector, wide application range. Detector with boron deposited GEM uses multilayer GEM with deposited boron film as neutron conversion carrier which reads out the information of neutron shot from the readout electrode with gas amplification from every GEM layer. The detector is high performance which can meet the demands of neutron detector of a new generation. Boron deposited neutron conversion electrode with boron deposited cathode and GEM included is the core part of the detector. As boron is a high-melting-point metalloid (> 2 000 ℃), electroplating and thermal evaporation are inappropriate ways. So finding a way to deposit boron on electrode which can meet the demands become a key technology in the development of neutron detector with boron deposited GEM. Compared with evaporation, sputtering has features such as low deposition temperature, high film purity, nice adhesive, thus is appropriate for our research. Magnetron sputtering is a improved way of sputtering which can get lower sputtering air pressure and higher target voltage, so that we can get better films. Through deposit process, the research uses magnetron sputtering to deposit pure boron film on copper electrode and GEM film. This method can get high quality, nice adhere, high purity, controllable uniformity, low cost film with high speed film formation. (authors)

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.)

A neutronic feasibility study for LEU conversion of the Brookhaven Medical Research Reactor (BMRR).

Energy Technology Data Exchange (ETDEWEB)

Hanan, N. A.

1998-01-14

A neutronic feasibility study for converting the Brookhaven Medical Research Reactor from HEU to LEU fuel was performed at Argonne National Laboratory in cooperation with Brookhaven National Laboratory. Two possible LEU cores were identified that would provide nearly the same neutron flux and spectrum as the present HEU core at irradiation facilities that are used for Boron Neutron Capture Therapy and for animal research. One core has 17 and the other has 18 LEU MTR-type fuel assemblies with uranium densities of 2.5g U/cm{sup 3} or less in the fuel meat. This LEU fuel is fully-qualified for routine use. Thermal hydraulics and safety analyses need to be performed to complete the feasibility study.

Fundamental neutron physics at a 1 MW long pulse spallation neutron source

International Nuclear Information System (INIS)

Greene, G.L.

1995-01-01

Modern neutron sources and modern neutron science share a common origin in mid twentieth 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 the study of condensed matter with modern neutron sources being primarily used (and primarily justified) as tools for condensed matter research. The study of elementary particles has, of course, led to the development of rather different tools and is now dominated by activities carried out 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 the continuation of this program of research

When thin is sexy - neutron reflectometry instrumentation at the Australian replacement research reactor

International Nuclear Information System (INIS)

James, M.

2003-01-01

Full text: Neutron and X-ray reflectometry are techniques used to probe the structure of surfaces, thin-films or buried interfaces as well as processes occurring at surfaces and interfaces such as adsorption, adhesion and inter-diffusion. Applications cover adsorbed surfactant layers, self-assembled monolayers, biological membranes, electrochemical and catalytic interfaces, polymer coatings and photosensitive films. Contrast variation and selective deuteration of hydrogenous materials are important aspects of the neutron-based technique. Neutron reflectometry probes the structure of materials normal to the surface at depths of up to several thousand Angstroms, with an effective depth resolution of a few Angstroms. Neutron reflectometry experiments have been performed by a number of Australian researchers at overseas facilities for more than a decade, however this capability has previously been absent in this country. A neutron reflectometer has been recognised as one of the highest priority instruments to be constructed at the new 20MW research reactor facility at Lucas Heights (due for completion in 2006). In this presentation we report the design of the time-of-flight reflectometer to be constructed at the new research facility. The reflectometer will operate with a vertical scattering plane and thus be able to measure specular reflectometry from both solid and liquid samples. A series of disc choppers will enable the instrument resolution (ΔQ/Q) to be varied from 2% to > 15%. The detection system will consist of a 2-dimenional position sensitive detector that will also allow the measurement of off-specular reflectivity

Workshop: Research and development plans for high power spallation neutron testing at BNL

International Nuclear Information System (INIS)

1996-01-01

This report consists of vugraphs from presentations at the meeting. The papers covered the following topics: (1) APS as a proton source; (2) target status for NSNS (National Spallation Neutron Source); (3) spallation neutron source in Japan; (4) liquid LiBi flow loop; and (5) research and development plans for high power tests at the AGS

Residual radioactive contamination of the test site at Emu from nuclear weapons tests conducted in 1953

International Nuclear Information System (INIS)

Maclagan, D.S.; Cooper, M.B.; Duggleby, J.C.

1979-08-01

The detailed distributions and soil concentrations of long-lived radionuclides remaining from nuclear weapons trials conducted at Emu in October 1953, are presented. Significant radiation levels due to long-lived neutron activation products in soil, 60 Co and 152 Eu, occur only in the immediate vicinity of the ground zeros of TOTEM 1 and TOTEM 2. It is shown that the levels of contamination due to fallout products in the soil are well below those which would constitute a health hazard to occupants of the area

Neutron physics and nuclear data measurements with accelerators and research reactors

International Nuclear Information System (INIS)

1988-08-01

The report contains a collection of lectures devoted to the latest theoretical and experimental developments in the field of fast neutron physics and nuclear data measurements. The possibilities offered by particle accelerators and research reactors for research and technological applications in these fields are pointed out. Refs, figs and tabs

The applied research program of the High Flux Neutron Generator at the National Nuclear Center, Havana

International Nuclear Information System (INIS)

Perez, G.; Martin, G.; Ceballos, C.; Padron, I.; Shtejer, K.; Perez, N.; Guibert, R.; Ledo, L.M.; Cruz Inclan, Carlos

2001-01-01

The Havana High Flux Neutron Generator facility is an intense neutron source based on a 20 mA duoplasmatron ion source and a 250 kV high voltage power supply. It has been installed in the Neutron Generator Laboratory at the Center of Applied Technologies and Nuclear Research in 1997. This paper deal outlined the future applied program to be carried out in this facility in the next years. The Applied Research Program consists on install two nuclear analytic techniques: the PELAN technique which uses the neutron generator in the pulse mode and the Low Energy PIXE technique which uses the same facility as a low energy proton accelerator for PIXE analysis. (author)

Bugs and gas: Agreements banning chemical and biological weapons

Science.gov (United States)

Mikulak, Robert P.

2017-11-01

The use of chemical or biological weapons, whether by a State or terrorists, continues to be a serious security concern. Both types of weapons are prohibited by multilateral treaties that have very broad membership, but both the Biological Weapons Convention and the Chemical Weapons Convention are facing major challenges. In particular, the continued use of chemical weapons in the Syrian civil war by government forces risks eroding the norm against the use of such weapons. This paper briefly explore the recent history of efforts to constrain chemical and biological weapons and outlines challenges for the future.

Nuclear experts and nuclear weapons proliferation

International Nuclear Information System (INIS)

Mueller, H.

1979-01-01

In Germany the issue of nuclear weapons proliferation has attracted scant attention. Most potential nuclear weapon states are important trade partners of the FRG and, since further proliferation of nuclear weapons could worsen conflicts involving these, it should be in the FRG's interest to limit proliferation. The security of the FRG is also dependent on the common interest of the great powers to avoid nuclear war. The contradictory positions of Usa and the USSR on nuclear weapons policy regarding themselves and non-nuclear weapon states encourages less developed countries to see nuclear weaponry as useful. The NPT and IAEA safeguards have only limited inhibiting effect. The nuclear export policy of the FRG has been dominated by short term economic advantage, neglecting the negative long term effects of decreased political stability. The FRG should formulate a policy based on self-restraint, positive stimuli and extension of controls, using its economic strength to deter proliferation. (JIW)

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.

The Manuel Lujan Jr. Neutron Scattering Center (LANSCE) experiment reports 1993 run cycle. Progress report

International Nuclear Information System (INIS)

Farrer, R.; Longshore, A.

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

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

International Nuclear Information System (INIS)

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

Summary Report of Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Major Actinides

International Nuclear Information System (INIS)

Capote Noy, R.

2013-09-01

A summary is given of the Second Research Coordination Meeting on Prompt Fission Neutron Spectra of Actinides. Experimental data and modelling methods on prompt fission neutron spectra were reviewed. Extensive technical discussions held on theoretical methods to calculate prompt fission spectra. Detailed coordinated research proposals have been agreed. Summary reports of selected technical presentations at the meeting are given. The resulting work plan of the Coordinated Research Programme is summarized, along with actions and deadlines. (author)

Reframing the debate against nuclear weapons

International Nuclear Information System (INIS)

Tyson, Rhianna

2005-01-01

'Some 35,000 nuclear weapons remain in the arsenals of the nuclear powers, with thousands still deployed on hair-trigger alert. Whatever rationale these weapons may once have had has long since dwindled. Political, moral, and legal constraints on actually using them further undermine their strategic utility without, however, reducing the risks of inadvertent war or proliferation. The objective of nuclear non-proliferation is not helped by the fact that the nuclear weapon States continue to insist that those weapons in their hands enhance security, while in the hands of others they are a threat to world peace. If we were making steady progress towards disarmament, this situation would be less alarming. Unfortunately, the reverse is true.' - United Nations Secretary-General Kofi Annan. 'Something is wrong with the nuclear disarmament and non-proliferation regime. Although seemingly well-equipped with an arsenal of legal and political mechanisms, such as the Nuclear Non-Proliferation Treaty (NPT), the 1996 Advisory Opinion of the International Court of Justice (ICJ), decades' worth of General Assembly (GA) resolutions and even a recent slew of ad-hoc, plurilateral initiatives such as the Proliferation Security Initiative, the regime created to prevent the catastrophe of nuclear war remains inadequate. This insufficiency is even starker when viewed in relation to the regimes controlling other weapons of mass destruction. Despite its own challenges, the Organization for the Prohibition on Chemical Weapons remains relatively well-funded and well-situated to facilitate the implementation of the Chemical Weapons Convention (CWC). Even the Biological and Toxin Weapons Convention (BTWC), while still lacking the necessary verification mechanisms, has managed to effectively criminalize not just the use and threat of use of biological weapons, but also their production, development and stockpiling. Meanwhile, the anti-nuclear regime seems to be faltering. Progress made in

Experimental assessment of the performance of a proposed lead slowing-down spectrometer at WNR/PSR [Weapons Neutron Research/Proton Storage Ring

International Nuclear Information System (INIS)

Moore, M.S.; Koehler, P.E.; Michaudon, A.; Schelberg, A.; Danon, Y.; Block, R.C.; Slovacek, R.E.; Hoff, R.W.; Lougheed, R.W.

1990-01-01

In November 1989, we carried out a measurement of the fission cross section of 247 Cm, 250 Cf, and 254 Es on the Rensselaer Intense Neutron Source (RINS) at Rensselaer Polytechnic Institute (RPI). In July 1990, we carried out a second measurement, using the same fission chamber and electronics, in beam geometry at the Los Alamos Neutron Scattering Center (LANSCE) facility. Using the relative count rates observed in the two experiments, and the flux-enhancement factors determined by the RPI group for a lead slowing-down spectrometer compared to beam geometry, we can assess the performance of a spectrometer similar to RINS, driven by the Proton Storage Ring (PSR) at the Los Alamos National Laboratory. With such a spectrometer, we find that is is feasible to make measurements with samples of 1 ng for fission 1 μg for capture, and of isotopes with half-lives of tens of minutes. It is important to note that, while a significant amount of information can be obtained from the low resolution RINS measurement, a definitive determination of average properties, including the level density, requires that the resonance structure be resolved. 12 refs., 5 figs., 3 tabs

Experimental assessment of the performance of a proposed lead slowing-down spectrometer at WNR/PSR (Weapons Neutron Research/Proton Storage Ring)

Energy Technology Data Exchange (ETDEWEB)

Moore, M.S.; Koehler, P.E.; Michaudon, A.; Schelberg, A. (Los Alamos National Lab., NM (USA)); Danon, Y.; Block, R.C.; Slovacek, R.E. (Rensselaer Polytechnic Inst., Troy, NY (USA)); Hoff, R.W.; Lougheed, R.W. (Lawrence Livermore National Lab., CA (USA))

1990-01-01

In November 1989, we carried out a measurement of the fission cross section of {sup 247}Cm, {sup 250}Cf, and {sup 254}Es on the Rensselaer Intense Neutron Source (RINS) at Rensselaer Polytechnic Institute (RPI). In July 1990, we carried out a second measurement, using the same fission chamber and electronics, in beam geometry at the Los Alamos Neutron Scattering Center (LANSCE) facility. Using the relative count rates observed in the two experiments, and the flux-enhancement factors determined by the RPI group for a lead slowing-down spectrometer compared to beam geometry, we can assess the performance of a spectrometer similar to RINS, driven by the Proton Storage Ring (PSR) at the Los Alamos National Laboratory. With such a spectrometer, we find that is is feasible to make measurements with samples of 1 ng for fission 1 {mu}g for capture, and of isotopes with half-lives of tens of minutes. It is important to note that, while a significant amount of information can be obtained from the low resolution RINS measurement, a definitive determination of average properties, including the level density, requires that the resonance structure be resolved. 12 refs., 5 figs., 3 tabs.

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)

Progress report on neutron activation analysis at Dalat Nuclear Research Reactor

International Nuclear Information System (INIS)

Tuan, Nguyen Ngoc

2003-01-01

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)

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.

Framework for a sustainable development of neutron beam work in the smaller research reactors

International Nuclear Information System (INIS)

Carvalho, F.G.; Margaca, F.M.A.

1995-01-01

The authors analyze the present situation of research reactors for neutron beam work in the light of the changes that took place in the nuclear field during the last decades. Trends in supply and demand of neutron beam time in view of the specific requirements of the techniques and of the user's community are outlined. It is argued that resources, both human and material, should be considered in a global perspective, encompassing the national, regional and international levels, where national facilities, mostly low flux research reactors, should be looked upon as a valuable component of a commonwealth of resources to be usefully exploited for the benefit of the neutron user's community at large. The importance of international cooperation to develop a higher level of research reactor utilization is emphasized while suggestions concerning the role of IAEA are made, particularly, to promote the mobility of scientists and engineers directed from developed to less developed countries (LDC's) where research reactors are in operation. The potential of small research reactors in LDC's as an instrument of the country's general scientific and technological development is pointed out as well as difficulties commonly experienced and essential requirements of a successful performance with emphasis on the importance of establishing close links with the national scientific community and especially with university groups. The scientific and technological relevance of neutron scattering techniques is discussed. Reference is made to the techniques best suited to modest research reactor facilities as well as to the importance of developing a local competence in instrument design, optimization and construction. (author). 12 refs

Weapons material and the commercial fuel cycle

International Nuclear Information System (INIS)

Steyn, J.J.

1993-01-01

In 1991, the United States and the former USSR had arsenals of ∼18,000 and 27,200 nuclear weapons, respectively. Approximately 10,000 of the US and 13,000 of the former USSR weapons were in the strategic category, and the remainder were tactical weapons. The dramatic changes in the political climate between the United States and the republics of the former USSR have resulted in the signing of the Strategic Arms Reduction Treaty (START I and II), agreements to substantially reduce nuclear weapons arsenals. Tactical weapons have already been collected in Russia, and strategic weapons are to be collected by the end of 1994. The major issues in accomplishing the treaty reductions appear to be funding, transport safety, storage capacity, and political issues between Russia and Ukraine because the latter seems to be using its weapons for political leverage on other matters. Collectively, the US and former USSR warhead stockpiles contain tremendous inventories of high-enriched uranium and weapons-grade plutonium which if converted to light water reactor fuel would equate to an enormous economic supply of natural uranium, conversion services, and enrichment separative work. The potential for this material entering the light water reactor fuel marketplace was enhanced in July 1992, when the two US industrial companies, Nuclear Fuel Services and Allied-Signal, announced that they had reached a preliminary agreement with the Russian ministry, Minatom, and the Russian Academay of Sciences to convert Russian high-enriched uranium to low-enriched uranium