İçme ve sulama sularında bor kirliliği ve bor giderme yöntemleri

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Meltem Bilici Başkan

2014-03-01

Full Text Available Periyodik cetvelin 3A grubunda yer alan bor yüksek iyonlaşma potansiyeline sahip olması nedeniyle yarı metal olarak kabul edilir. Yerkabuğundaki ortalama bor konsantrasyonu 10 mg/kg'dır. Bor doğada Ca, Na ve Mg'un tuzları şeklinde bulunur. Yüksek konsantrasyonlarda ve ekonomik boyutlardaki bor yatakları; borun oksijen ile bağlanmış bileşikleri şeklinde daha çok Türkiye ve ABD'nin kurak, volkanik ve hidrotermal aktivitesi olan bölgelerinde bulunmaktadır. Bor, bitkiler için gerekli bir mikro besin elementi olmanın yanı sıra, gerekli tüm besin elementleri içerisinde, eksiklik belirtilerine neden olan miktarı ile toksik etki yapan miktarı, birbirine çok yakın olan tek elementtir. Bor su ortamında genellikle borik asit ve kısmen de borat tuzları formlarında bulunmaktadır. Pek çok endüstride kullanım alanı bulan bor bileşiklerinin endüstriyel gelişmelere bağlı olarak yüzeysel sularda bulunan konsantrasyonu artış göstermektedir. Yüzeysel sularda bulunan bor aynı zamanda evsel atıksulardan da kaynaklanmaktadır. Türkiye'de içme ve sulama sularını en çok kirleten toksik elementlerin başında bor gelmektedir. Bu nedenle bor giderimi hem insan sağlığı açısından hem de sağlıklı tarım ürünü yetiştirilebilmesi açısından oldukça önemlidir. Sulardan bor giderimi için uygulanan temel yöntemler arasında iyon değişimi, ultrafiltrasyon, ters osmoz ve adsorbsiyon gelmektedir.

Structure of Bor1 supports an elevator transport mechanism for SLC4 anion exchangers.

Science.gov (United States)

Thurtle-Schmidt, Bryan H; Stroud, Robert M

2016-09-20

Boron is essential for plant growth because of its incorporation into plant cell walls; however, in excess it is toxic to plants. Boron transport and homeostasis in plants is regulated in part by the borate efflux transporter Bor1, a member of the solute carrier (SLC) 4 transporter family with homology to the human bicarbonate transporter Band 3. Here, we present the 4.1-Å resolution crystal structure of Arabidopsis thaliana Bor1. The structure displays a dimeric architecture in which dimerization is mediated by centralized Gate domains. Comparisons with a structure of Band 3 in an outward-open state reveal that the Core domains of Bor1 have rotated inwards to achieve an occluded state. Further structural comparisons with UapA, a xanthine transporter from the nucleobase-ascorbate transporter family, show that the downward pivoting of the Core domains relative to the Gate domains may access an inward-open state. These results suggest that the SLC4, SLC26, and nucleobase-ascorbate transporter families all share an elevator transport mechanism in which alternating access is provided by Core domains that carry substrates across a membrane.

Polarized localization and borate-dependent degradation of the Arabidopsis borate transporter BOR1 in tobacco BY-2 cells [v1; ref status: indexed, http://f1000r.es/kv

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Noboru Yamauchi

2013-09-01

Full Text Available In Arabidopsis the borate transporter BOR1, which is located in the plasma membrane, is degraded in the presence of excess boron by an endocytosis-mediated mechanism. A similar mechanism was suggested in rice as excess boron decreased rice borate transporter levels, although in this case whether the decrease was dependent on an increase in degradation or a decrease in protein synthesis was not elucidated. To address whether the borate-dependent degradation mechanism is conserved among plant cells, we analyzed the fate of GFP-tagged BOR1 (BOR1-GFP in transformed tobacco BY-2 cells. Cells expressing BOR1-GFP displayed GFP fluorescence at the plasma membrane, especially at the membrane between two attached cells. The plasma membrane signal was abolished when cells were incubated in medium with a high concentration of borate (3 to 5 mM. This decrease in BOR1-GFP signal was mediated by a specific degradation of the protein after internalization by endocytosis from the plasma membrane. Pharmacological analysis indicated that the decrease in BOR1-GFP largely depends on the increase in degradation rate and that the degradation was mediated by a tyrosine-motif and the actin cytoskeleton. Tyr mutants of BOR1-GFP, which has been shown to inhibit borate-dependent degradation in Arabidopsis root cells, did not show borate-dependent endocytosis in tobacco BY-2 cells. These findings indicate that the borate-dependent degradation machinery of the borate transporter is conserved among plant species.

Acoustic noises of the BOR-60 reactor steam generators when simulating leaks with argon and steam

International Nuclear Information System (INIS)

Sokolov, V.M.; Golushko, V.V.; Afanas'ev, V.A.; Grebenkin, Yu.P.; Muralev, A.B.

1985-01-01

Background acoustic noises of stea generators in different operational regimes and noises of argon and steam small leads (about 0.1 g/s) are studied to determine the possibility of designing the acoustic system for leak detection in sodium-water steamgenerators. Investigations are carried out at the 30 MW micromodule steam generator being in operation at the BOR-60 reactor as well as at the 20 MW tank type steam generator. Immersed ransduceres made of lithium niobate 6 mm in-diameter and waveguide transducers made of a stainless steel in the form of rods 10 mm in-diameter and 500 mm long are used as acoustic monitors. It is shown that the leak noise is more wide-band than the background noise of the steam generator and both high and low frequencies appear in the spectrum. The use of monitors of different types results in similar conslusions inrelation to the character of background noises and leak signals (spectral density, signal to-noise ratio) in the ase of similar bandroidths of the transduceres. A conclusion is made that the change of operational regimes leads to changes of background noise level, which can be close to the reaction of

Fusion technology: The Iter fusion experiment

International Nuclear Information System (INIS)

Dietz, K.J.

1994-01-01

Plans for the Iter international fusion experiment, in which the European Union, Japan, Canada, Russia, Sweden, Switzerland, and the USA cooperate, were begun in 1985, and construction work started in early 1994. These activities serve for the preparation of the design and construction documents for a research reactor in which a stable fusion plasma is to be generated. This is to be the basis for the construction of a fusion reactor for electricity generation. Preparatory work was performed in the Tokamak experiments with JET and TFTR. The fusion power of 1.5 GW will be attained, thus enabling Iter to keep a deuterium-tritium plasma burning. (orig.) [de

Impact assessment of mine drainage water and municipal wastewater on the surface water in the vicinity of Bor

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Gardić Vojka R.

2015-01-01

Full Text Available Mining and copper production in Bor, in the past hundred years, had a huge impact on the environment of town, but also in a wide region. In the area of Bor, in the zone of Mining and Smelting Company (RTB activity, over 29,000 ha of land under forests and fields is degraded. The area of degraded agricultural land in the Bor municipality is over 60% of total agricultural land. Wastewater, generated in the sites of RTB Bor, pollute the Bor River and Krivelj River, which still flow into the Timok River and Danube River. These pollutions are often presented by low pH value, increased content of heavy metal ions, suspended particles and fine particles of flotation tailings, which is deposited in the valleys of these rivers on the area of over 2000 hectares. During the decades of exploitation of ore from the open pit Bor at different locations ("Visoki Planir" - also called “Oštreljski planir”, "Severni planir" dump of ore body "H" (RTH gangue and tailings were delayed. The largest amount of tailings, about 150 million tons, was postponed on location Visoki planir. The effect of the mining waste and the impact of the whole process of processing copper ore to the final products on the environment, was conducted during the 4th study period of the project "Management of mining waste-tailing dump in the Bor region," supported by the Japan Society for the Promotion Science (Eng. Japan Society for the Promotion of Science and the Japan international cooperation Agency and the Ministry of environment, Mining and Spatial planning of the Republic of Serbia. Influence of season on the level of pollutants in soil and water, the impact on water quality in the river Timok and the River Danube, was conducted during first three periods of project. This paper presents the results of the third study period. The third period of research, which was conducted over a period of 17. 10. 2012 to 17. 01.2013 year, included a review of pollution sources and define their

Mechanical properties and TEM examination of RAFM steels irradiated up to 70 dpa in BOR-60

Energy Technology Data Exchange (ETDEWEB)

Gaganidze, E., E-mail: Ermile.Gaganidze@kit.edu [Karlsruher Institut fuer Technologie, Institut fuer Angewandte Materialien, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Petersen, C.; Materna-Morris, E.; Dethloff, C.; Weiss, O.J.; Aktaa, J. [Karlsruher Institut fuer Technologie, Institut fuer Angewandte Materialien, Hermann-von-Helmholtz-Platz 1, 76344 Eggenstein-Leopoldshafen (Germany); Povstyanko, A.; Fedoseev, A.; Makarov, O.; Prokhorov, V. [Joint Stock Company ' State Scientific Centre Research Institute of Atomic Reactors' , 433510 Dimitrovgrad-10, Ulyanovsk Region (Russian Federation)

2011-10-01

Mechanical properties of Reduced Activation Ferritic/Martensitic (RAFM) steels were studied after irradiation in BOR-60 reactor to a neutron displacement damage of 70 dpa at 330-340 deg. C. Yield stress and Ductile-to-Brittle-Transition-Temperature of EUROFER97 indicate saturation of hardening and embrittlement. The phenomenological models for description of microstructure evolution and resulting irradiation hardening and embrittlement are discussed. The evolution of yield stress with dose is qualitatively understood within a Whapham and Makin model. Dislocation loops examined in TEM are considered a main source for low-temperature irradiation hardening. The analysis of the fatigue data in terms of the inelastic strain reveals comparable fatigue behaviour both for unirradiated and irradiated conditions, which can be described by a common Manson-Coffin relation. The study of helium effects in B-doped model steels indicated progressive material embrittlement with helium content. Post-irradiation annealing of RAFM steels yielded substantial recovery of mechanical properties.

SHB1/HY1 Alleviates Excess Boron Stress by Increasing BOR4 Expression Level and Maintaining Boron Homeostasis in Arabidopsis Roots

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Qiang Lv

2017-05-01

Full Text Available Boron is an essential mineral nutrient for higher plant growth and development. However, excessive amounts of boron can be toxic. Here, we report on the characterization of an Arabidopsis mutant, shb1 (sensitive to high-level of boron 1, which exhibits hypersensitivity to excessive boron in roots. Positional cloning demonstrated that the shb1 mutant bears a point mutation in a gene encoding a heme oxygenase 1 (HO1 corresponding to the HY1 gene involved in photomorphogenesis. The transcription level of the SHB1/HY1 gene in roots is up-regulated under excessive boron stimulation. Either overexpressing SHB1/HY1 or applying the HO1 inducer hematin reduces boron accumulation in roots and confers high boron tolerance. Furthermore, carbon monoxide and bilirubin, catalytic products of HO1, partially rescue the boron toxicity-induced inhibition of primary root growth in shb1. Additionally, the mRNA level of BOR4, a boron efflux transporter, is reduced in shb1 roots with high levels of boron supplementation, and hematin cannot relieve the boron toxicity-induced root inhibition in bor4 mutants. Taken together, our study reveals that HO1 acts via its catalytic by-products to promote tolerance of excessive boron by up-regulating the transcription of the BOR4 gene and therefore promoting the exclusion of excessive boron in root cells.

Radioactivity of long-lived nuclides in the primary circuit of the reactor BOR-60 during operation with defective fuel elements

International Nuclear Information System (INIS)

Gryazev, V.M.; Kizin, V.D.; Lisitsyn, E.S.; Polyakov, V.I.; Chechetkin, Y.V.

1978-06-01

The summarized results of measurements of the enrichment and distribution of radioactive nuclides from corrosion and of fission products during the four years of operation of BOR-60, including a longer period of operation with detective fuel elements in the core, are presented. It is shown that for operation with approximately 1% leaking fuel rods radiation exposure becomes worse manily because of release and enrichment of cesium isotopes in the coolant. Of the other fission products, the largest contribution to the dose rate in pipework and components is given by 140 Ba / 140 La and 95 Nb. On operation with 0.1 to 0.2% of leaking fuel rods, this contribution is comparable to that of the corrosion products 60 Co and 54 Mn. The radioactivity of corrosion products in the circuit has not increased within the last three years and was about one order of magnitude lower than the theoretical values. The corrosion and fission products are nonuniformly distributed over the circuit. Concentration of 95 Nb and 60 Co in the pipe for 'cold' sodium is larger by a factor of 2 - 5 and of 140 Ba and 54 Mn by a factor of 10-20 than in the pipes for 'hot' sodium. Most of the cobalt was found to deposit in the heat exchanges. The effectiveness of emptying the pipes from coolant in order to reduce the dose sate is assessed. (orig.) [de

High power microwave diagnostic for the fusion energy experiment ITER

DEFF Research Database (Denmark)

Korsholm, Søren Bang; Leipold, Frank; Goncalves, B.

2016-01-01

Microwave diagnostics will play an increasingly important role in burning plasma fusion energy experiments like ITER and beyond. The Collective Thomson Scattering (CTS) diagnostic to be installed at ITER is an example of such a diagnostic with great potential in present and future experiments....... The ITER CTS diagnostic will inject a 1 MW 60 GHz gyrotron beam into the ITER plasma and observe the scattering off fluctuations in the plasma — to monitor the dynamics of the fast ions generated in the fusion reactions....

Irradiation Microstructure of Austenitic Steels and Cast Steels Irradiated in the BOR-60 Reactor at 320°C

Science.gov (United States)

Yang, Yong; Chen, Yiren; Huang, Yina; Allen, Todd; Rao, Appajosula

Reactor internal components are subjected to neutron irradiation in light water reactors, and with the aging of nuclear power plants around the world, irradiation-induced material degradations are of concern for reactor internals. Irradiation-induced defects resulting from displacement damage are critical for understanding degradation in structural materials. In the present work, microstructural changes due to irradiation in austenitic stainless steels and cast steels were characterized using transmission electron microscopy. The specimens were irradiated in the BOR-60 reactor, a fast breeder reactor, up to 40 dpa at 320°C. The dose rate was approximately 9.4x10-7 dpa/s. Void swelling and irradiation defects were analyzed for these specimens. A high density of faulted loops dominated the irradiated-altered microstructures. Along with previous TEM results, a dose dependence of the defect structure was established at 320°C.

MARKETING MIX BY BED OCCUPANCY RATIO (BOR

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Abdul Muhith

2017-04-01

Full Text Available Introduction: Bed Occupancy Ratio (BOR in RSI Arafah Mojosari during the last three years are at under ideal rate and the lowest of the three existing hospitals in the area of Mojosari. The purpose of this study was to determine the relationship marketing mix with Bed Occupancy Ratio in RSI Arafah Mojosari. Methods: This research uses analytic methods with crossectional approach. Variables in the study is marketing mix and Bed Occupancy Ratio (BOR. The population in this study were all patients hospitalized in the RSI Arafah Mojosari. Samples amounted 44 respondents taken by the Stratified random sampling technique. Data were collected using the questionnaire and analyzed using Fisher's Exact test. Result: The results obtained more than 50% of respondents (59.1% rate well against the marketing mix is developed by the hospital management and the majority of respondents (79.5% are in the treatment room that has a number BOR is not ideal. Fisher Exact test test results obtained probabililty value=0.02<0.05 so that H0 is rejected, which means there is a relationship marketing mix with the Bed Occupancy Ratio in RSI Arafah Mojosari. Discussion: Hospitals which able to develop the marketing mix very well, can attract consumers to use inpatient services at the hospital, with that BOR value will increase as the increased use of inpatient services. Hospital management must be able to formulate a good marketing mix strategy that hospital marketing objectives can be achieved. Conformity between service quality and service rates must be addressed, otherwise it extent of media promotions can attract patients to inpatient services.

One-Step Leapfrog LOD-BOR-FDTD Algorithm with CPML Implementation

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Yi-Gang Wang

2016-01-01

Full Text Available An unconditionally stable one-step leapfrog locally one-dimensional finite-difference time-domain (LOD-FDTD algorithm towards body of revolution (BOR is presented. The equations of the proposed algorithm are obtained by the algebraic manipulation of those used in the conventional LOD-BOR-FDTD algorithm. The equations for z-direction electric and magnetic fields in the proposed algorithm should be treated specially. The new algorithm obtains a higher computational efficiency while preserving the properties of the conventional LOD-BOR-FDTD algorithm. Moreover, the convolutional perfectly matched layer (CPML is introduced into the one-step leapfrog LOD-BOR-FDTD algorithm. The equation of the one-step leapfrog CPML is concise. Numerical results show that its reflection error is small. It can be concluded that the similar CPML scheme can also be easily applied to the one-step leapfrog LOD-FDTD algorithm in the Cartesian coordinate system.

Eogenetic caves in conglomerate: an example from Udin Boršt, Slovenia

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Lipar Matej

2011-01-01

Full Text Available Udin Boršt is a karstified terrace of carbonate rock, which is of fluvioglacial origin, and is situated in the north-western part of Slovenia. There are 15 registered caves, which have been interpreted as caves in conglomerate, while karst of Udin Boršt itself was interpreted as conglomerate karst, shallow karst or isolated karst. In this article, caves in Udin Boršt have been interpreted as eogenetic caves. Based on porosity and bedding material, different types of caves and cave passages have developed. Four general types of eogenetic caves found in Udin Boršt are; linear stream caves, shelter caves, breakdown caves and vadose shafts.

Nuclear fusion experimental study on 16 O + 60 Ni system

International Nuclear Information System (INIS)

Silva, C.P. da.

1990-01-01

Nuclear fusion cross section measurements were performed in the energy range near The Coulomb Barrier (E Lab -> 40-72 MeV), for the system 16 O + 60 Ni, aiming the study of Fusion Process involving heavy ions. (L.C.J.A.)

Evolutionary divergence of plant borate exporters and critical amino acid residues for the polar localization and boron-dependent vacuolar sorting of AtBOR1

KAUST Repository

Wakuta, Shinji; Mineta, Katsuhiko; Amano, Taro; Toyoda, Atsushi; Fujiwara, Toru; Naito, Satoshi; Takano, Junpei

2015-01-01

Boron (B) is an essential micronutrient for plants but is toxic when accumulated in excess. The plant BOR family encodes plasma membrane-localized borate exporters (BORs) that control translocation and homeostasis of B under a wide range

Fusion neutronics experiments and analysis

International Nuclear Information System (INIS)

1992-01-01

UCLA has led the neutronics R ampersand D effort in the US for the past several years through the well-established USDOE/JAERI Collaborative Program on Fusion Neutronics. Significant contributions have been made in providing solid bases for advancing the neutronics testing capabilities in fusion reactors. This resulted from the hands-on experience gained from conducting several fusion integral experiments to quantify the prediction uncertainties of key blanket design parameters such as tritium production rate, activation, and nuclear heating, and when possible, to narrow the gap between calculational results and measurements through improving nuclear data base and codes capabilities. The current focus is to conduct the experiments in an annular configuration where the test assembly totally surrounds a simulated line source. The simulated line source is the first-of-a-kind in the scope of fusion integral experiments and presents a significant contribution to the world of fusion neutronics. The experiments proceeded through Phase IIIA to Phase IIIC in these line source simulation experiments started in 1989

Possibilities of sustainable development the RTB Bor

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Zeković Slavka

2006-01-01

Full Text Available The paper analysis the medium and long-term perspectives, framework and considered possibilities of sustainable development of RTB "Bor" in the period of transition. It is today the giant in the best quality copper production in the Balkans. In the paper are elaborated the problems of privatization, debt, investment, growth of copper production from own mines (and imported raw, opening of new mines, economical efficiency of production, environmental problems and impacts in the last time. The RTB "Bor" is a serious hot spot in Serbia. Unsustainability trends and process are identified, as follows: open-pit waste dumps, flotation tailings, mining and processing waste waters, air pollution; inefficiency useful of energy water and other inputs in copper complex; trans boundary character of emissions of dust; environmental degradation and quality of wide area and ecologically highly risk, etc.

Fusion Concept Exploration Experiments at PPPL

International Nuclear Information System (INIS)

Stewart Zweben; Samuel Cohen; Hantao Ji; Robert Kaita; Richard Majeski; Masaaki Yamada

1999-01-01

Small ''concept exploration'' experiments have for many years been an important part of the fusion research program at the Princeton Plasma Physics Laboratory (PPPL). this paper describes some of the present and planned fusion concept exploration experiments at PPPL. These experiments are a University-scale research level, in contrast with the larger fusion devices at PPPL such as the National Spherical Torus Experiment (NSTX) and the Tokamak Fusion Test Reactor (TFTR), which are at ''proof-of-principle'' and ''proof-of-performance'' levels, respectively

Studying the processes of sodium-water interaction in the BOR-60 reactor micromodule steam generator

International Nuclear Information System (INIS)

Tsykanov, V.A.; Antipin, G.K.; Borisov, V.V.

1981-01-01

Main results of experimental studies of emergency regimes of micromodule steam generator (MSG) at small and big leaks of water into sodium, realized using the 30 MW MSG, operating in the BOR-o0 reactor, are considered. The aims of the study are as follows: the modelling of macroleak in ''Nadja'' steam generator for the BN-350 reactor; testing the conceptions of alarm signalling and MSG protection; testing under real conditions of new perspective systems of leak detection; gaining the experimence and development of the ways to eliminate the consequences of accident caused by big water leak into sodium; accumulation of knowledge on restoration of MSG operating ability after accident; experimental test of calculational techniques for big leak accidents to use them in future for calculational studies of similar situations at other reactors equipped with sodium-water steam generators; refinement of characteristics of hydrodynamic and thermal effects interaction zone for big leak in real circuit during the plant operation. A series of experiments with the imitation of water leak into sodium by means of argon and steam supply through injection devices, located before the steam superheater module of one of the sections and between evaporator module of the same section, is conducted. The range of steam flow rate is 0.02-0.45 g/s. Duration of steam supply is 100-400 s. A conclusion is made that the results obtained can be used for steam generator of the BN-350 reactor [ru

Manufacturing of central control system of 'JT-60' a plasma feasibility experiment device

International Nuclear Information System (INIS)

Kondo, Ikuo; Kimura, Toyoaki; Murai, Katsuji; Iba, Daizo; Takemaru, Koichi.

1984-01-01

For constructing a critical-plasma-experiment apparatus JT-60, it was necessary to develop a new control system which enables to operate safely and smoothly a large scale nuclear fusion apparatus and to carry out efficient experiment. For the purpose, the total system control facility composed of such controllers as CAMAC system, timing system and protective interlock panel with multi-computer system as the core was developed. This system generalizes, keeps watch on and controls the total facilities as the key point of the control system of JT-60, and allows flexible operation control corresponding to the diversified experimental projects. At the same time, it carries out the fast real-time control of high temperature, high density plasma. In this paper, the system constitution, function and the main contents of development of the total system control facility are reported. JT-60 is constructed to attain the critical plasma condition as the premise of nuclear fusion reactors and to scientifically verify controlled nuclear fusion. Plasma expe riment will be started in April, 1985. The real-time control of plasma for carrying out high beta operation is planned, intending to develop future economical practical reactors. (Kako, I.)

Status of Cea-Minatom collaborative experiment Bora-Bora: fuels with high plutonium content

Energy Technology Data Exchange (ETDEWEB)

Zaboudko, L.; Kurina, I. [Institute for Physics and Power Engineering, IPPE, Kaluga region (Russian Federation); Mayorshin, A.; Kisly, V. [Research Institute for Atomic Reactors, RIAR, Uljanovsk region (Russian Federation); Menshikova, T.; Rogozkin, B. [All Russia Research Institute of Inorganic Materials, VNIINM, Moscow (Russian Federation); Pillon-Eymard, S.; Languille, A. [CEA Cadarache, Dir. de l' Energie Nucleaire, 13 - Saint Paul lez Durance (France); Thetford, R. [AEA Technology, Harwell (United Kingdom)

2001-07-01

The program of the experiment on the BOR-60 reactor with different fuel types is presented. It includes 3 phases: fuel fabrication, fuel irradiation on BOR-60, post-irradiation examination. The fuels studied are: MOX fuel UPu{sub 0.45}O{sub 2} made by two different techniques, nitride fuel (UPu{sub 0.45}N and UPu{sub 0.6}N) and inert-matrix fuel (PuN + ZrN and PuO{sub 2} + MgO). Results on fuel fabrication are presented. Description of the irradiation facility is given. Fuel irradiation conditions are discussed. Results of nitride fuel performance calculations by NITRAF code are shown. (author)

Identification of a human protein-derived HIV-1 fusion inhibitor targeting the gp41 fusion core structure.

Directory of Open Access Journals (Sweden)

Lijun Chao

Full Text Available The HIV-1 envelope glycoprotein (Env gp41 plays a crucial role in the viral fusion process. The peptides derived from the C-terminal heptad repeat (CHR of gp41 are potent HIV fusion inhibitors. However, the activity of these anti-HIV-1 peptides in vivo may be attenuated by their induction of anti-gp41 antibodies. Thus, it is essential to identify antiviral peptides or proteins with low, or no, immunogenicity to humans. Here, we found that the C-terminal fragment (aa 462-521 of the human POB1 (the partner of RalBP1, designated C60, is an HIV-1 fusion inhibitor. It bound to N36, the peptide derived from the N-terminal heptad repeat (NHR of gp41, and to the six-helix bundle (6-HB formed by N36 and C34, a CHR-peptide, but it did not bind to C34. Unlike the CHR-peptides, C60 did not block gp41 6-HB formation. Rather, results suggest that C60 inhibits HIV-1 fusion by binding to the 6-HB, in particular, the residues in the gp41 NHR domain that are exposed on the surface of 6-HB. Since 6-HB plays a crucial role in the late stage of fusion between the viral envelope and endosomal membrane during the endocytic process of HIV-1, C60 may serve as a host restriction factor to suppress HIV-1 entry into CD4+ T lymphocytes. Taken together, it can be concluded from these results that C60 can be used as a lead for the development of anti-HIV-1 therapeutics or microbicides for the treatment and prevention of HIV-1 infection, as well as a molecular probe to study the fusogenic mechanism of HIV-1.

On the re-emergence of motion and innovations in the Gábor Bódy's intermedia experiments

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Kamil Lipiński

2015-06-01

Full Text Available The article explores the main cases of Hungarian neo-avant-garde cinema in terms of re-emergence of visual material and the introduction of electronic innovations resulting in the transformation of reality. Among the research conducted in Béla Balázs Studio based on reframing the perception limits in the 1960s and the 1970s, the most innovative were Gábor Bódy's intermedia experiments. Along with launching K/3 subgroup within BBS, Bódy directed its objectives to reduce the material derived from reality and to visually intervene into media image electronically transforming the landscape of his films. Innovatively adapting the Sándor Weöres's verse, the film Narcissus and Psyche (1983 aimed at using hyper-real aesthetics to reframe the film reality. Starting from 1980, Bódy founded an international magazine Infermental to disseminate the advent of the video and electronics by creating a community drew on sharing news about emerging media image.

Kaliski's explosive driven fusion experiments

International Nuclear Information System (INIS)

Marshall, J.

1979-01-01

An experiment performed by a group in Poland on the production of DD fusion neutrons by purely explosive means is discussed. A method for multiplying shock velocities ordinarily available from high explosives by a factor of ten is described, and its application to DD fusion experiments is discussed

FUSION OF SENDAI VIRUS WITH HUMAN HL-60 AND CEM CELLS - DIFFERENT KINETICS OF FUSION FOR 2 ISOLATES

NARCIS (Netherlands)

DELIMA, MCP; NIR, S; FLASHER, D; KLAPPE, K; HOEKSTRA, D; DUZGUNES, N

1991-01-01

The kinetics of fusion of Sendai virus (Z strain) with the human promyelocytic leukemia cell line HL-60, and the human T lymphocytic leukemia cell line CEM was investigated. Fusion was monitored by fluorescence dequenching of octadecylrhodamine (R-18) incorporated in the viral membrane. For one

Experience with modular steam generator production and application of new testing methods

International Nuclear Information System (INIS)

Olesovsky

Experience is reviewed gained at the Trebic IBZKG plant with the production of modular steam generators. The plant started producing steam generators for the Jaslovske Bohunice nuclear power plant in 1965. In addition to the steam generator for the A-1, the plant also produced a loop for the Melekess power plant and a steam generator for the BOR-60 reactor. Operating experience gained so far allowed improving the quality of the BOR steam generator, especially in the tube-tube plate joint. A double tube plate was used and the welded joint shape was changed. As a result of high requirements on the quality of welded joints, the steam generator has successfully been in operation for more then 10,000 hours. The existing experience was utilized in designing a new steam generator named Nadya. Many design and technological requirements were presented concerning the Nadya generator and many new checking operations have been included in technology. (Kr)

Window of cold nuclear fusion and biased-pulse electrolysis experiment

International Nuclear Information System (INIS)

Takahashi, Akito; Jida, Toshiyuki; Maekawa, Fujio; Sugimoto, Hisashi; Yoshida, Shigeo

1989-01-01

Based on the electron screening effect and the excitation of deuteron harmonic oscillators in palladium lattice, theoretical aspects are given to explain the cold fusion phenomena and the possibility of nuclear heating. A narrow window is proposed to meet ≅ 10 watts per cubic centimeter for the nuclear heating, by the hypothetical excitation-screening model. A relatively wide window is feasible to meet a few fusion events per second per cc under the non-stationary conditions of deuteron-charging and discharging. For stationary lattice conditions, the probability of cold fusion is not feasible at all. To confirm the cold fusion phenomena, a heavy water electrolysis experiment was carried out using biased-pulse-electrolytic currents, expecting the enhancement of cold fusion events under charging and discharging of deuterons. For the neutron detection, a cross-checking system between a recoil-proton scintillation detector and a 3 He thermal neutron detector was employed to see coincident time-patterns of neutron emission from an electrolysis cell. To check the energy of emitted neutrons, pulse height spectrum of the recoil-proton detector was monitored. Up to the D-charging time of 300 hr, neutron yields of 1-2 n/s/cc were obtained for time-intervals of 60-200 hr. From the recoil-proton spectra, it was confirmed that 2.45 MeV neutrons by the D(d, n) 3 He fusion branch were emitted. The observed time-patterns of neutron emission suggest the existence of cold fusion under the charging and discharging conditions. (orig.)

Repetitive laser fusion experiment and operation using a target injection system

International Nuclear Information System (INIS)

Nishimura, Yasuhiko; Komeda, Osamu; Mori, Yoshitaka

2017-01-01

Since 2008, a collaborative research project on laser fusion development based on a high-speed ignition method using repetitive laser has been carried out with several collaborative research institutes. This paper reports the current state of operation of high repetition laser fusion experiments, such as target introduction and control based on a target injection system that allows free falling under 1 Hz, using a high repetition laser driver that has been under research and development, as well as the measurement of targets that freely fall. The HAMA laser driver that enabled high repetition fusion experiments is a titanium sapphire laser using a diode-pumped solid-state laser KURE-I of green light output as a driver pump light source. In order to carry out high repetition laser fusion experiments, the target injection device allows free falling of deuterated polystyrene solid sphere targets of 1 mm in diameter under 1 Hz. The authors integrated the developed laser and injection system, and succeeded first in the world in making the nuclear fusion reaction continuously by hitting the target to be injected with laser, which is essential technology for future laser nuclear fusion reactor. In order to realize repetition laser fusion experiments, stable laser, target synchronization control, and target position measurement technologies are indispensable. (A.O.)

Radiological safety design considerations for fusion research experiments

International Nuclear Information System (INIS)

Crase, K.W.; Singh, M.S.

1979-01-01

A wide variety of fusion research experiments are in the planning or construction stages. Two such experiments, the Nova Laser Fusion Facility and the Mirror Fusion Test Facility (MFTF), are currently under construction at Lawrence Livermore Laboratory. Although the plasma chamber vault for MFTF and the Nova target room will have thick concrete walls and roofs, the radiation safety problems are made complex by the numerous requirements for shield wall penetrations. This paper addresses radiation safety considerations for the MFTF and Nova experiments, and the need for integrated safety considerations and safety technology development during the planning stages of fusion experiments

Annual report of the Fusion Research Center for the period of April 1, 1982 to March 31, 1983

International Nuclear Information System (INIS)

1983-11-01

Research and development activities of the Fusion Research Center (Department of Thermonuclear Fusion Research and Department of Large Tokamak Development) from April 1982 to March 1983 are described. The JFT-2 tokamak was shutdown after 10 years operation. Operation test of a new device JFT-2M was near completion. In the joint JAERI-USDOE experiment on Doublet-III a record value of beta, 4.6 %, was achieved. Major efforts in theory and computation was on high beta tokamak stability, second stability regions being found for low m internal modes. The JT-60 program progressed as scheduled, installation of the tokamak machine being initiated in February 1983. A 100 kV test was completed of prototype unit for JT-60 NBI. In the development of a high power klystron for JT-60 LH heating, a test fabricated tube generated 1 MW, 10 s RF pulses. Development of TiC coatings for JT-60 first wall was successfully concluded. In the superconducting magnet technology, the Japanese coil for IEA Large Coil Task was installed in a test facility at ORNL after successful performance test at Naka site. A 10 T experiment of a Nb 3 Sn coil with 60 cm inner bore was made. Construction of the Tritium Process Laboratory was started in February 1983. Design studies of the Fusion Experimental Reactor and INTOR were continued. (author)

Aspects of energy reduction by autogenous copper production in the copper smelting plant Bor

International Nuclear Information System (INIS)

Najdenov, Ivan; Raić, Karlo T.; Kokeza, Gordana

2012-01-01

This work presents a comparative analysis of the energy consumption during copper production by the “standard” procedure (roasting in a fluo–solid reactor and smelting in a reverberatory furnace) in the Smelting Plant in Bor with modern autogenous procedures. All forms of expended energy were reduced to primary energy or to the same energy form, i.e., to the energy equivalent of the process (EEP), the raw material and the process materials. In addition, the energy equivalent of the process and waste products (water vapour, thermal energy and similar) were balanced. To complete the consumption of all energy generating products in copper production, they were reduced to conditional fuel (coal equivalent = 29.3 MJ/kg). Additionally, this study suggests replacement of the existing technology by an appropriate autogenous procedure and considers the prospects for further development of mining and metallurgy in Bor. Estimates of development perspectives for copper production should be comprehensive, based on complete and relevant data, as well as on real considerations of future development in world production. -- Highlights: ► “Standard” autogenous copper production in the Smelting Plant, Bor, Serbia. ► Comparation of energy consumption in “standard” with other autogenous procedures. ► All forms of energy are reduced to energy equivalent and conditional fuel. ► Replacement of existing technology with the appropriate autogenous procedure. ► Perspectives of further development of mining and metallurgy in Bor.

Substantiation of physical concepts of fast reactors in Russia: experience and prospects

Energy Technology Data Exchange (ETDEWEB)

Alekseev, P.N. [Russian Research Center ' Kurchatov Institute' (RRC KI), 1, Kurchatov Sq., Moscow, 123182 (Russian Federation); Vasiliev, B.A. [Experimental Design Bureau of Machine Building (OKBM) 15, Burnakovskiy Pr., N. Novgorod, 603074 (Russian Federation); Kormilitsyn, M.V. [State Scientific Center of Russian Federation - Research Institute of Atomic Reactors (NIIAR) Dimitrovgrad-10, Ulianovsk Reg., 433510 (Russian Federation); Lopatkin, A.V. [N.A. Dollezhal Research and Development Institute of Power Engineering (NIKIET) 2/8, M. Krasnoselskaya Str., Moscow, 107140 (Russian Federation); Seleznev, E.F. [All-Russian Research Institute for Nuclear Power Plant Operation (VNIIAES) 25, Ferganskaya, Moscow, 109507 (Russian Federation); Khomyakov, Yu.S.; Tsybulia, A.M. [State Scientific Center of the Russian Federation - A. I. Leypunsky Institute for Physics and Power Engineering (SSC RF- IPPE) 1, Bondarenko Sq., Obninsk, Kaluga Reg., 249033 (Russian Federation); Tocheny, L.V. [International Science and Technology Center (ISTC) 32-34 Krasnoproletarskaya Ulitsa, Moscow, 127473 (Russian Federation)

2008-07-01

The fast reactor concept in Russia has accumulated unique experience, since its advent in the 1950's and up to the present, from the creation of the first experimental installation BR-1, experimental reactors BR-5 and BOR-60, the pilot industrial reactors BN-350 in Kazakhstan and up to the BN-600 at Beloyarsk Atomic Power Station. Investigations on the first experimental installations BR-1 and BR-5/-10 proved the propriety of the idea that it is possible to create nuclear reactors that can produce more nuclear fuel than they consume, i.e. the idea of breeding. The architecture of such reactors was also designed, producing a current leader among fast reactors with sodium coolant and oxide uranium-plutonium fuel. Operational experience of BOR-60, BN-350 and, particularly, BN-600 confirmed the engineering and technical feasibility of the concept of fast reactors, the possibility for its realization both for power production and for certain other purposes as well, such as desalinisation of sea water (BN-350) and for radionuclide production (BN-350, BN-600), and it enabled the development and verification of different models, computer methods and codes. The paper presents a review of experience in the creation of plants with fast reactors, scientific research on these installations, principal results, the current status of experimental data analysis, and prospective directions in the development of fast reactors and the corresponding experimental basis in Russia. (authors)

Modeling, analysis and experiments for fusion nuclear technology

International Nuclear Information System (INIS)

Abdou, M.A.; Hadid, A.H.; Raffray, A.R.; Tillack, M.S.; Iizuka, T.

1988-01-01

Selected issues in the development of fusion nuclear technology (FNT) have been studied. These relate to (1) near-term experiments, modeling, and analysis for several key FNT issues, and (2) FNT testing in future fusion facilities. A key concern for solid breeder blankets is to reduce the number of candidate materials and configurations for advanced experiments to emphasize those with the highest potential. Based on technical analysis, recommendations have been developed for reducing the size of the test matrix and for focusing the testing program on important areas of emphasis. The characteristics of an advanced liquid metal MHD experiment have also been studied. This facility is required in addition to existing facilities in order to address critical uncertainties in MHD fluid flow and heat transfer. In addition to experiments, successful development of FNT will require models for interpreting experimental data, for planning experiments, and for use as a design tool for fusion components. Modeling of liquid metal fluid flows is a particular area of need in which substantial progress is expected, and initial efforts are reported here. Preliminary results on the modeling of tritium transport and inventory in solid breeders are also summarized. Finally, the thermo-mechanical behavior of liquid-metal-cooled limiters is analyzed and the parameter space for feasible designs is explored. Because of the renewed strong interest in a fusion engineering facility, a critical review and analysis of the important FNT testing requirements have been performed. Several areas have been emphasized due to their strong impact on the design and cost of the test facility. These include (1) the length of the plasma burn and the mode of operation (pulsed vs. steady-state), and (2) the need for a tritium-producing blanket and its impact on the availability of the device. (orig.)

Annual report of the Fusion Research Center for the period of April 1, 1984 to March 31, 1985

International Nuclear Information System (INIS)

1986-01-01

Research and development activities of the Fusion Research Center (Department of Large Tokamak Development and Department of Thermonuclear Fusion Research) from April 1984 to March 1985 are described. The JT-60 program progressed as scheduled. Commissioning of the JT-60 tokamak was completed by the end of the period under review. In parallel with installation and test of the tokamak machine, installation of basic diagnostic instruments and examination of the procedure for experiment had been made to meet the first phase Joule heating experiment. (The first plasma discharge was recorded on April 8, 1985). Construction of auxiliary heating systems had continued. A medium-sized tokamak, JFT-2M, had been operated for high-power ICRF heating and ECH assisted LH current drive experiments. Installation of a power supply for plasma shaping in JFT-2M was completed. In the field of plasma theory, detailed analysis had been made on nonlinear kink/tearing modes in a plasma with free boundary and also on ICRF heating. Development of a high-voltage, high-current He ion source for JT-60 plasma diagnostics had proceeded successfully, and tests of JT-60 LH and ICRF luanchers as well. Surface erosion of a new ceramics, SiC with BeO addition by proton bombardment was studied. In IEA's Large Coil Task, three coil test was made at ORNL. A 11 T experiment of TMC-1, a large-bore Nb 3 Sn coil was completed. Commissioning tests of tritium handling facilities had proceeded in the Tritium Process Laboratory. Design studies of the Fusion Experimental Reactor (FER) and INTOR had been advanced. (author)

Neutron irradiation experiments for fusion reactor materials through JUPITER program

International Nuclear Information System (INIS)

Abe, K.; Namba, C.; Wiffen, F.W.; Jones, R.H.

1998-01-01

A Japan-USA program of irradiation experiments for fusion research, ''JUPITER'', has been established as a 6 year program from 1995 to 2000. The goal is to study ''the dynamic behavior of fusion reactor materials and their response to variable and complex irradiation environment''. This is phase-three of the collaborative program, which follows RTNS-II program (phase-1: 1982-1986) and FFTF/MOTA program (phase-2: 1987-1994). This program is to provide a scientific basis for application of materials performance data, generated by fission reactor experiments, to anticipated fusion environments. Following the systematic study on cumulative irradiation effects, done through FFTF/MOTA program. JUPITER is emphasizing the importance of dynamic irradiation effects on materials performance in fusion systems. The irradiation experiments in this program include low activation structural materials, functional ceramics and other innovative materials. The experimental data are analyzed by theoretical modeling and computer simulation to integrate the above effects. (orig.)

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

OpenAIRE

Angelone, M.; Flammini, D.; Loreti, S.; Moro, F.; Pillon, M.; Villar, R.; Klix, A.; Fischer, U.; Kodeli, I.; Perel, R.L.; Pohorecky, W.

2017-01-01

A neutronics benchmark experiment on a pure Copper block (dimensions 60 × 70 × 70 cm3) aimed at testing and validating the recent nuclear data libraries for fusion applications was performed in the frame of the European Fusion Program at the 14 MeV ENEA Frascati Neutron Generator (FNG). Reaction rates, neutron flux spectra and doses were measured using different experimental techniques (e.g. activation foils techniques, NE213 scintillator and thermoluminescent detectors). This paper first sum...

Plug-welding of ODS cladding tube for BOR-60 irradiation. Welding condition setting. Device remodeling and welding

International Nuclear Information System (INIS)

Seki, Masayuki; Ishibashi, Fujio; Kono, Syusaku; Hirako, Kazuhito; Tsukada, Tatsuya

2003-04-01

Irradiation test in BOR-60 at RIAR to judge practical use prospect of ODS cladding tube at early stage is planned as Japan-Russia a joint research. RIAR does fuel design of fuel pin used for this joint research. JNC manufactures ODS cladding tube and bar materials (two steel kind of martensite and ferrite), upper endplug production. They are welded by pressurized resistance welding, and are inspected in JNC Tokai, transported to RIAR. And RIAR manufactures vibration packing fuel pin. On the upper endplug welding by pressurized resistance welding method, we worded on the problems such as decision of welding condition by changing the size and crystallization of cladding tube and the design of endplug, and the chucking device remodeling to correspond to the long scale cladding tube welding system (included handling) and of quality assurance method. Especially, use of long scale cladding tube caused problem that bending transformation occurred in cladding tube by welding pressure. However, we solved this problem by shortening the distance of cladding tube colette chuck and pressure receiving, and by putting the sleeve in an internal space of welding machine, losing the bending of cladding tube. Moreover, welding defects were occurred by the difference of an inside state, an inside defect and recrystallization of cladding tube. We solved the problem by inside grinding for the edge of tube, angle beam method by ultrasonic wave, and ultrasonic wave form confirmation. Manufacturing process with long scale cladding tube including heat-treatment to remove combustion return and remaining stress was established besides, Afterwards, welding of ODS cladding tube and upper endplug. As the quality assurance system, we constructed [Documented procedure (referred to JOYO)] based on [Document of the QA plan] by OEC. Welding and inspection were executed by the document procedure. It is thought that the quality assurance method become references for the irradiation test in JOYO in the

Overview of the Fusion Z-Pinch Experiment FuZE

Science.gov (United States)

Weber, T. R.; Shumlak, U.; Nelson, B. A.; Golingo, R. P.; Claveau, E. L.; McLean, H. S.; Tummel, K. K.; Higginson, D. P.; Schmidt, A. E.; UW/LLNL Team

2016-10-01

Previously, the ZaP device, at the University of Washington, demonstrated sheared flow stabilized (SFS) Z-pinch plasmas. Instabilities that have historically plagued Z-pinch plasma confinement were mitigated using sheared flows generated from a coaxial plasma gun of the Marshall type. Based on these results, a new SFS Z-pinch experiment, the Fusion Z-pinch Experiment (FuZE), has been constructed. FuZE is designed to investigate the scaling of SFS Z-pinch plasmas towards fusion conditions. The experiment will be supported by high fidelity physics modeling using kinetic and fluid simulations. Initial plans are in place for a pulsed fusion reactor following the results of FuZE. Notably, the design relies on proven commercial technologies, including a modest discharge current (1.5 MA) and voltage (40 kV), and liquid metal electrodes. Supported by DoE FES, NNSA, and ARPA-E ALPHA.

A new approach to the spectral analysis of liquid membrane oscillators by Gábor transformation

DEFF Research Database (Denmark)

Płocharska-Jankowska, E.; Szpakowska, M.; Mátéfi-Tempfli, Stefan

2006-01-01

Liquid membrane oscillators very frequently have an irregular oscillatory behavior. Fourier transformation cannot be used for these nonstationary oscillations to establish their power spectra. This important point seems to be overlooked in the field of chemical oscillators. A new approach...... is presented here based on Gábor transformation allowing one to obtain power spectra of any kind of oscillations that can be met experimentally. The proposed Gábor analysis is applied to a liquid membrane oscillator containing a cationic surfactant. It was found that the power spectra are strongly influenced...

Heating experiments of JT-60

International Nuclear Information System (INIS)

1987-01-01

In JT-60, after the finish of the first stage Joule experiment, the heating facilities were installed, and the heating experiment was started in August, 1986. As to neutral beam injection, the beam injection experiment at the maximum rating 20 MW carried out, and also as to RF, the injection experiment up to 1.4 MW was carried out in both ion cyclotron and low band hybrid waves. The results worthy of special mention in the heating experiment were the success in the current drive up to 1.7 MA at maximum using low band hybrid waves and the improvement of plasma confinement characteristics obtained by the compound heating of NBI and RF. In this paper, the main results of these heating experiments and their significance are explained. The JT-60 is the testing facilities for attaining the critical plasma condition by additionally heating the plasma which is generated by Joule electric discharge with NBI and RF heatings. The experimental operation cycle of the JT-60 consists of the unit cycle of two weeks, and the number of days in operation is nine days. The temperature of heated plasma rose to 70 million deg C in the 20 MW NBI heating. Hereafter, the improvement of confinement time by increasing the stored energy of plasma is attempted. (Kako, I.)

Annual report of the Fusion Research Center for the period of April 1, 1983 to March 31, 1984

International Nuclear Information System (INIS)

1985-03-01

Research and development activities of the Fusion Research Center (Department of Thermonuclear Fusion Research and Department of Large Tokamak Development) from April 1983 to March 1984 are described. Installation and commissioning of the new tokamak JFT-2M had been completed. The 2nd ICRF heating experiment and LH current drive experiment were started. In the field of plasma theory, the scaling law of the critical beta in a tokamak was obtained and the ICRF heating was analyzed in detail. The first phase of the cooperation of Doublet III will be finished in Sept. 1984. The JT-60 program progressed as scheduled. Installation of the tokamak machine, initiated in Feb. 1983, will be finished in Sept. 1984. The tests of power supply and control system on site and the fabrication of the neutral beam injectors in factory proceeded successfully. Performance tests of prototype injector unit for JT-60 NBI progressed as scheduled. A new advanced source plasma generator was developed to provide a high proton ratio exceeding 90%. Klystrons for JT-60 LH heating achieved the output power of 1 MW for 10 sec. Performance tests of titanium evaporators for JT-60 were completed. The Japanese coil for IEA Large Coil Task was installed in a test facility at ORNL and the partial cool-down was carried out. Construction of the Tritium Process Laboratory was completed. Design studies of the Fusion Experimental Reactor (FER) and INTOR proceeded. (author)

High dose neutron irradiation damage in beryllium as blanket material

Energy Technology Data Exchange (ETDEWEB)

Chakin, V.P. E-mail: fae@niiar.ru; Kazakov, V.A.; Teykovtsev, A.A.; Pimenov, V.V.; Shimansky, G.A.; Ostrovsky, Z.E.; Suslov, D.N.; Latypov, R.N.; Belozerov, S.V.; Kupriyanov, I.B. E-mail: vniinm.400@g23.relkom.ru

2001-11-01

The paper presents the investigation results of beryllium products that operated in the SM and BOR-60 reactors up to neutron doses of 2.8x10{sup 22} and 8.0x10{sup 22} cm{sup -2} (E>1 MeV), respectively. The calculated and experimental data are given on helium and tritium accumulation, swelling, micro-hardness and thermal conductivity. The microstructural investigation results of irradiated beryllium are also presented. It is shown that the rate of helium and tritium accumulation in beryllium in the SM and BOR-60 reactors is high enough, which is of interest from the viewpoint of modeling the working conditions of the DEMO fusion reactor. Swelling of beryllium at irradiation temperature of 70-150 deg. C and neutron fluence of 2.8x10{sup 22} cm{sup -2} (E>1 MeV) makes up 0.8-1.5%, at 400 deg. C and fluence of 8x10{sup 22} cm{sup -2} (E>1 MeV)-3.2-5.0%. Irradiation hardening and decrease of thermal conductivity strongly depend on the irradiation temperature and are more significant at reduced temperatures. All results presented in the paper were analyzed with due account of the supposed working parameters of the DEMO fusion reactor blanket.

High dose neutron irradiation damage in beryllium as blanket material

International Nuclear Information System (INIS)

Chakin, V.P.; Kazakov, V.A.; Teykovtsev, A.A.; Pimenov, V.V.; Shimansky, G.A.; Ostrovsky, Z.E.; Suslov, D.N.; Latypov, R.N.; Belozerov, S.V.; Kupriyanov, I.B.

2001-01-01

The paper presents the investigation results of beryllium products that operated in the SM and BOR-60 reactors up to neutron doses of 2.8x10 22 and 8.0x10 22 cm -2 (E>1 MeV), respectively. The calculated and experimental data are given on helium and tritium accumulation, swelling, micro-hardness and thermal conductivity. The microstructural investigation results of irradiated beryllium are also presented. It is shown that the rate of helium and tritium accumulation in beryllium in the SM and BOR-60 reactors is high enough, which is of interest from the viewpoint of modeling the working conditions of the DEMO fusion reactor. Swelling of beryllium at irradiation temperature of 70-150 deg. C and neutron fluence of 2.8x10 22 cm -2 (E>1 MeV) makes up 0.8-1.5%, at 400 deg. C and fluence of 8x10 22 cm -2 (E>1 MeV)-3.2-5.0%. Irradiation hardening and decrease of thermal conductivity strongly depend on the irradiation temperature and are more significant at reduced temperatures. All results presented in the paper were analyzed with due account of the supposed working parameters of the DEMO fusion reactor blanket

TMX: a new fusion plasma experiment

International Nuclear Information System (INIS)

Anon.

1977-01-01

The primary goal of the magnetic fusion energy program at LLL is the development of a technically and economically feasible approach to the generation of fusion energy. Results from our earlier 2XIIB experiment lead us to believe that a fusion power plant based on a mirror system is technically feasible, assuming a favorable extrapolation to plasmas of reactor size. Achieving economic feasibility is more difficult. For power-producing applications, a reactor needs a large Q, the ratio of fusion power output to the power injected to sustain the system. In a conventional mirror reactor, the fusion power is only about equal to the power injected by the neutral beams--that is, Q is only about unity. A new idea, the tandem mirror concept described in this article, promises to increase this gain, enhancing Q by at least a factor of 5

Irradiation capsule for testing magnetic fusion reactor first-wall materials at 60 and 2000C

International Nuclear Information System (INIS)

Conlin, J.A.

1985-08-01

A new type of irradiation capsule has been designed, and a prototype has been tested in the Oak Ridge Research Reactor (ORR) for low-temperature irradiation of Magnetic Fusion Reactor first-wall materials. The capsule meets the requirements of the joint US/Japanese collaborative fusion reactor materials irradiation program for the irradiation of first-wall fusion reactor materials at 60 and 200 0 C. The design description and results of the prototype capsule performance are presented

A hypothetical severe reactor accident in Sosnovyj Bor, Russia

International Nuclear Information System (INIS)

Lahtinen, J.; Toivonen, H.; Poellaenen, R.; Nordlund, G.

1993-12-01

Individual doses and short-term radiological consequences from a hypothetical severe accident at the Russian nuclear power plant in Sosnovyj Bor were estimated for two sites in Finland. The sites are Kotka, located 140 km from the plant, and Helsinki, 220 km from the plant. The release was assumed to start immediately after the shutdown of the reactor (a 1000 MW RBMK unit) which had been operating at nominal power level for a long time. An effective release height of 500 m was assumed. The prevailing meteorological conditions during the release were taken to present the situation typical of the area (effective wind speed 9 m/s, neutral dispersion conditions). The release fractions applied in the study were of the same order as in the Chernobyl accident, i.e. 100% for noble gases, 60% for iodines, 40% for cesium and 1-10% for other radiologically important nuclides. The release was assumed to last 24 hours. However, half of the nuclides were released during the first hour. No attention was paid to the actual sequence of events that could lead to such release characteristics and time behaviour. The concentration and dose calculations were performed with a modified version of the computer code OIVA developed in Finnish Centre for Radiation and Nuclear Safety. Inhalation dose and external doses from the release plume and from the deposited activity were calculated for adults only, and no sheltering was considered. (11 refs., 4 figs., 6 tabs.)

Advanced fusion in ICRF injected plasmas

International Nuclear Information System (INIS)

Carpignano, F.; Coppi, B.; Detragiache, P.; Migliuolo, S.; Nassi, M.; Rogers, B.

1994-01-01

Fusion burning of a D- 3 He mixture in a high density, high magnetic field, compact toroidal experiment (Ignitor) with a high injected power density at the ion cyclotron frequency (ICRF) is investigated. A superthermal tail (with energies exceeding 1 MeV in the central part of the plasma column) is induced in the distribution of the minority 3 He population ( 0 20 m -3 ). This stems from the high value of the peak RF power density absorbed by the minority species (ρ RF ∼ 60 MW/m 3 ) that should be obtained in Ignitor when the total injected power is about 18 MW. This experiment is suitable to begin the study of advanced fusion burning, because of the high plasma currents (I p 3 He fusion powers of the order of 1 MW should be attained. (author) 8 refs., 3 figs

Annual report of Naka Fusion Research Establishment from April 1, 2002 to March 31, 2003

International Nuclear Information System (INIS)

Tsuji, Hiroshi; Hamamatsu, Kiyotaka; Matsumoto, Hiroshi; Yoshida, Hidetoshi

2003-11-01

This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2002 to 31 March, 2003. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction. JT-60 program has continued to produce fruitful knowledge and understanding necessary to achieve reactor relevant performances of tokamak fusion devices. JFT-2M has made contributions in more basic areas of tokamak plasma research and development in pursuit of high performance plasma. The objectives of JT-60 research have been more shifted to physics R and Ds in support of the International Thermonuclear Experimental Reactor (ITER) and establishment of physics basis for a steady state tokamak fusion reactor like SSTR as a fusion power demonstration plant. In JFT-2M, the advanced material tokamak experiment program has been carried out to test the low activation ferritic steel for development of the structural material for a fusion reactor. In the area of theories and analyses, significant progress has been made in understanding of the ITB, energy confinement scaling in ITB plasmas, MHD equilibrium in the current hole region, asymmetric feature of divertor plasmas and the divertor detachment. In addition, through the project of numerical experiment on tokamak, the mechanism of the ion temperature gradient mode was clarified by particle simulations. The physics of divertor plasma was also studied by particle simulations. R and Ds of fusion reactor technologies have been carried out both to further improve technologies necessary for ITER construction, and to accumulate

On fusion/fission chain reactions in the Fleischmann-Pons cold fusion experiment

International Nuclear Information System (INIS)

Anghaie, S.; Froelich, P.; Monkhorst, H.J.

1990-01-01

In this paper the possibility of fusion/fission chain reactions following d-d source reactions in electrochemical cold fusion experiments have been investigated. The recycling factors for the charged particles in fusion reactions with consumable nuclei deuteron, 6 Li nd 7 Li, are estimated. It is concluded that, based on the established nuclear fusion cross sections and electronic stopping power, the recycling factor is four to five orders of magnitude less than required for close to critical conditions. It is argued that the cross generation of charged particles by neutrons does not play a significant role in this process, even if increased densities at the surface of electrodes do occur

Towards a reduced activation structural materials database for fusion DEMO reactors

International Nuclear Information System (INIS)

Moeslang, A.; Diegele, E.; Laesser, R.; Klimiankou, M.; Lindau, R.; Materna-Morris, E.; Rieth, M.; Lucon, E.; Petersen, C.; Schneider, H.-C.; Pippan, R.; Rensman, J.W.; Schaaf, B. van der; Tavassoli, F.

2005-01-01

The development of First Wall, Blanket and Divertor materials which are capable of withstanding many years the high neutron and heat fluxes, is a critical path to fusion power. Therefore, the timely availability of a sound materials database has become an indispensable element in international fusion road maps. In order to provide materials design data for short term needs of ITER Test Blanket Modules and for a DEMOnstration fusion reactor, a wealth of R and D results on the European reduced activation ferritic-martensitic steel EUROFER, and on oxide dispersion strengthened variants are being characterized, mainly in the temperature window 250-650 deg. C. The characterisation includes irradiations up to 15 dpa in the mixed spectrum reactor HFR and up to 75 dpa in the fast breeder reactor BOR60. Industrial EUROFER-batches of 3.5 and 7.5 tons have been produced with a variety of semi-finished, quality-assured product forms. To increase thermal efficiency of blankets, high temperature resistant SiC f /SiC channel inserts for liquid metal coolant tubes are also developed. Regarding radiation damage resistance, a broad based reactor irradiation programs counts several steps from ≤5dpa (ITER TBMs) up to 75 dpa (DEMO). For the European divertor designers, a materials data base is presently being set up for pure W and W alloys, and related reactor irradiations are foreseen with temperatures from 650-1000 deg. C. (author)

Gasdynamic Mirror Fusion Propulsion Experiment

Science.gov (United States)

Emrich, Bill; Rodgers, Stephen L. (Technical Monitor)

2000-01-01

A gasdynamic mirror (GDM) fusion propulsion experiment is currently being constructed at the NASA Marshall Space Flight Center (MSFC) to test the feasibility of this particular type of fusion device. Because of the open magnetic field line configuration of mirror fusion devices, they are particularly well suited for propulsion system applications since they allow for the easy ejection of thrust producing plasma. Currently, the MSFC GDM is constructed in three segments. The vacuum chamber mirror segment, the plasma injector mirror segment, and the main plasma chamber segment. Enough magnets are currently available to construct up to three main plasma chamber segments. The mirror segments are also segmented such that they can be expanded to accommodate new end plugging strategies with out requiring the disassembly of the entire mirror segment. The plasma for the experiment is generated in a microwave cavity located between the main magnets and the mirror magnets. Ion heating is accomplished through ambipolar diffusion. The objective of the experiment is to investigate the stability characteristics of the gasdynamic mirror and to map a region of parameter space within which the plasma can be confined in a stable steady state configuration. The mirror ratio, plasma density, and plasma "b" will be varied over a range of values and measurements subsequently taken to determine the degree of plasma stability.

Advanced fusion technologies developed for JT-60 superconducting tokamak

International Nuclear Information System (INIS)

Sakasai, Akira; Ishida, S.; Matsukawa, M.

2003-01-01

The modification of JT-60U is planned as a full superconducting tokamak (JT-60SC). The objectives of the JT-60SC program are to establish scientific and technological bases for the steady-state operation of high performance plasmas and utilization of reduced-activation materials in economically and environmentally attractive DEMO reactor. Advanced fusion technologies relevant to DEMO reactor have been developed in the superconducting magnet technology and plasma facing components for the design of JT-60SC. To achieve a high current density in a superconducting strand, Nb 3 Al strands with a high copper ratio of 4 have been newly developed for the toroidal field coils (TFC) of JT-60SC. The R and D to demonstrate applicability of Nb 3 Al conductor to the TFC by a react-and-wind technique have been carried out using a full-size Nb 3 Al conductor. A full-size NbTi conductor with low AC loss using Ni-coated strands has been successfully developed. A forced cooling divertor component with high heat transfer using screw tubes has been developed for the first time. The heat removal performance of the CFC target was successfully demonstrated on the electron beam irradiation stand. (author)

Design aspects of low activation fusion ignition experiments

International Nuclear Information System (INIS)

Cheng, E.T.; Creedon, R.L.; Hopkins, G.R.; Trester, P.W.; Wong, C.P.C.; Schultz, K.R.

1986-01-01

Preliminary design studies have been done exploring (1) materials selection, (2) shutdown biological dose rates, (3) mechanical design and (4) thermal design of a fusion ignition experiment made of low activation materials. From the results of these preliminary design studies it appears that an ignition experiment could be built of low activation materials, and that this design would allow hands-on access for maintenance

Fusion plasma physics research on the H-1 national facility

International Nuclear Information System (INIS)

Harris, J.

1998-01-01

Full text: Australia has a highly leveraged fusion plasma research program centred on the H-1 National Facility device at the ANU. H-1 is a heliac, a novel helical axis stellarator that was experimentally pioneered in Australia, but has a close correlation with the worldwide research program on toroidal confinement of fusion grade plasma. Experiments are conducted on H-1 by university researchers from the Australian Fusion Research Group (comprising groups from the ANU, the Universities of Sydney, Western Sydney, Canberra, New England, and Central Queensland University) under the aegis of AINSE; the scientists also collaborate with fusion researchers from Japan and the US. Recent experiments on H-1 have focused on improved confinement modes that can be accessed at very low powers in H-1, but allow the study of fundamental physics effects seen on much larger machines at higher powers. H-1 is now being upgraded in magnetic field and heating power, and will be able to confine hotter plasmas beginning in 1999, offering greatly enhanced research opportunities for Australian plasma scientists and engineers, with substantial spillover of ideas from fusion research into other areas of applied physics and engineering

Annual report of the Naka Fusion Research Establishment for the period of April 1 1989 to March 31 1990

International Nuclear Information System (INIS)

1990-09-01

Research and development activities of the Naka Fusion Research Establishment for the period of April 1989 to March 1990 are reported. The experiment on JT-60 was continued to October 1989. In the pellet injection experiment, plasma energy confinement was improved and the maximum fusion product reached 1.2 x 10 20 m -3 s keV. The portion of the bootstrap current was up to 80% of the total plasma current in the high poloidal beta discharge. The fabrication of the new vacuum vessel and poloidal field coils for the JT-60 machine upgrade (JT-60U) have been made. The experiment to improve the confinement on JFT-2M was conducted. The ergodic magnetic limiter coils were installed. Quasi-steady-state H-mode discharge (10 sec at maximum) was achieved and a new high-beta regime with the improved Troyon coefficient have been explored in DIII-D. As for theoretical and computational studies, thermal instabilities of an edge plasma, plasma performance determined by the MHD instabilities and burning plasma problems were investigated. A new type of a vacuum pump--the ceramic turbo-viscous pump--has been developed. In the high heat flux technology, small-scale divertor samples are manufactured by means of brazing carbon fiber reinforced carbon composite to copper heat sinks. The thermal cycle tests show they endure against a heat flux up to 10MW/m 2 . As for the development of plasma heating technology, the 50 keV-10A negative hydrogen beam was extracted by means of seeding cesium in the ion plasma generator. 1.4 MW-10sec RF was generated from an improved electron gun in the modified 2GHz-range klystron. Nb 3 Sn superconducting coil with an inner diameter of 1.0 m was successfully magnetized up to 7 T in 1 sec. The gram-level tritium experiments were performed. Conceptual design of the International Thermonuclear Experimental Reactor (ITER) is proceeding under the auspices of the IAEA. Design study of the Fusion Experimental Reactor (FER) concept has been conducted. (J.P.N.)

Laser fusion experiments at the Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1975-01-01

A short review is given of some of the important dates in the experimental fusion program at Livermore. A few of the parameters of the laser systems which are being used for these experiments are mentioned. Some information about specialized diagnostics which have been developed at the Livermore Laboratory for these experiments is described. The focusing arrangements for each of the systems are discussed. Experiments both on planar targets and on targets for laser fusion are described

Bioleaching of copper from old flotation tailings samples (Copper Mine Bor, Serbia

Directory of Open Access Journals (Sweden)

Stanković Srđan

2015-01-01

Full Text Available Bioleaching of samples taken from depths of 10, 15, and 20 meters from old flotation tailings of the Copper Mine Bor was conducted in shaken flasks using extremely acidic water of Lake Robuleas lixiviant. Yield of copper after five weeks of the bioleaching experiment was 68.34±1.21% for 15 m sample, 72.57±0.57% for 20 m sample and 97.78±5.50% for 10 m sample. The obtained results were compared to the results of acid leaching of the same samples and it was concluded that bioleaching was generally more efficient for the treatment of samples taken from depths of 10 m and 20 m. The content of pyrite in the 20 m sample, which contained the highest amount of this mineral, was reduced after bioleaching. Benefits of this approach are: recovery of substantial amounts of copper, reducing the environmental impact of flotation tailings and the application of abundant and free water from the Robule acidic lake as lixiviant. Results of the experiment showed that bioleaching can be more efficient than acid leaching for copper extraction from flotation tailings with higher sulfide contents. [Projekat Ministarstva nauke Republike Srbije, br. 176016 i br. 173048

Environmental impact of mining activity in Bor area as indicated by the distribution of heavy metals and bacterial population dynamics in sediment

Directory of Open Access Journals (Sweden)

Filimon M. N.

2016-01-01

Full Text Available The environmental impact of inorganic pollution is pronounced in water adjacent to Bor Copper Smelter Complex (RTB Bor, Serbia, with Cu, Zn, Pb, and As being the main determinants of aquatic pollution pattern. Communities of microorganisms present in the sediments are mainly affected by heavy metal pollution. Some groups of bacteria can be considered pollution bio-indicators, due to their sensibility and ability to bioaccumulate heavy metals, thus contributing to reducing pollution. This study investigates the relationships between trace element accumulation and heterogeneity in sediment bacteria community structure found in water streams adjacent to the Bor Copper Smelter Complex (RTB Bor, Serbia. Our results showed no contamination with copper, zinc, nickel, iron, and chromium, but did show a low to moderate contamination with lead and a moderate to high contamination with arsenic in aquatic sediments within the area of interest. Spatial heterogeneity in sediment-associated bacterial communities did not relate significantly to location of sampling sites, except for iron reducing bacteria. Iron reducing bacteria and nitrifying bacteria were the best distinguishing groups of bacteria. However, only iron reducing bacteria were significantly influenced by sampling locations. The iron reducing bacteria has correlated negatively with the degree of sediment contamination with lead, and therefore, we suggest that this group of bacteria could serve as potential bio-indicators of inorganic water contamination in Bor RTB area.

Pre-evaluation of fusion shielding benchmark experiment

International Nuclear Information System (INIS)

Hayashi, K.; Handa, H.; Konno, C.

1994-01-01

Shielding benchmark experiment is very useful to test the design code and nuclear data for fusion devices. There are many types of benchmark experiments that should be done in fusion shielding problems, but time and budget are limited. Therefore it will be important to select and determine the effective experimental configurations by precalculation before the experiment. The authors did three types of pre-evaluation to determine the experimental assembly configurations of shielding benchmark experiments planned in FNS, JAERI. (1) Void Effect Experiment - The purpose of this experiment is to measure the local increase of dose and nuclear heating behind small void(s) in shield material. Dimension of the voids and its arrangements were decided as follows. Dose and nuclear heating were calculated both for with and without void(s). Minimum size of the void was determined so that the ratio of these two results may be larger than error of the measurement system. (2) Auxiliary Shield Experiment - The purpose of this experiment is to measure shielding properties of B 4 C, Pb, W, and dose around superconducting magnet (SCM). Thickness of B 4 C, Pb, W and their arrangement including multilayer configuration were determined. (3) SCM Nuclear Heating Experiment - The purpose of this experiment is to measure nuclear heating and dose distribution in SCM material. Because it is difficult to use liquid helium as a part of SCM mock up material, material composition of SCM mock up are surveyed to have similar nuclear heating property of real SCM composition

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume I

International Nuclear Information System (INIS)

Abdou, M.

1984-10-01

The following chapters are included in this study: (1) fusion nuclear issues, (2) survey of experimental needs, (3) requirements of the experiments, (4) non-fusion facilities, (5) fusion facilities for nuclear experiments, and (6) fusion research and development scenarios

Finanční analýza podniku BRISK Tábor, a.s.

OpenAIRE

Hašek, Jan

2008-01-01

Diploma is focused on Financial analysis, importance of it, users, implementation analysis on factual company -- BRISK Tábor, a.s., evaluation based on analysis financial statements, ratio indicators, working capital, balance order, scheme of indicators, analysis of financial arm and comparison intercompany.

Pengaruh Perbedaan Kelas Umur terhadap Produktivitas Getah Pinus merkusii Jungh et de Vriese Ras Lahan Jawa melalui Penyadapan Getah Metode Bor

Directory of Open Access Journals (Sweden)

Agus Sukarno

2013-09-01

Full Text Available Pinus merkusii Jungh et de Vriese merupakan tanaman asli Indonesia, yang sebaran alaminya di Aceh, Tapanuli dan Kerinci. Penyadapan getah dengan metode bor pada kelas umur yang berbeda belum pernah dilakukan. Tujuan penelitian untuk mengetahui perbedaan produksi getah pinus di antara  kelas umur. Penelitian dilakukan di RPH Oro-oro Ombo, BKPH Pujon, KPH Malang pada tanaman pinus kelas umur III, IV,  V  dan VI  dengan ketinggian tempat antara 1.100 m –1.250 m dari permukaan air laut.  Waktu penelitian bulan September sampai dengan Nopember 2010.  Jumlah pohon yang disadap di setiap kelas umur sebanyak 150 - 160 pohon dengan dua lubang per pohon.  Penyadapan getah menggunakan bor mesin, kantong plastik tahan minyak diikatkan pada ujung pipa untuk menampung getah.  Pemungutan getah dilakukan sehari setelah penyadapan. Analisis  data  menggunakan  one way anova, apabila terdapat perbedaan yang nyata,  dilakukan uji lanjut dengan orthogonal polynomial. Produksi getah di antara kelas umur, menunjukkan perbedaan yang nyata. Produksi getah kelas umur III (36,5 g/ 2 lubang/1 hari meningkat pada kelas umur IV (62,9 g/2 lubang/1 hari dan menurun pada kelas umur V  (24,61 g/2 lubang/1 hari.  Produksi getah pada kelas umur VI (38,3 g/ 2 lubang/1 hari hampir sama dengan kelas umur III. Hasil uji lanjut orthogonal polynomial  menunjukkan respons  bersifat kuadratik (p=0,09 antara produksi getah dengan kelas umur. Kata Kunci: Pinus, kelas umur, getah, metode bor

The Penning fusion experiment-ions

International Nuclear Information System (INIS)

Schauer, M. M.; Umstadter, K. R.; Barnes, D. C.

1999-01-01

The Penning fusion experiment (PFX) studies the feasibility of using a Penning trap as a fusion confinement device. Such use would require spatial and/or temporal compression of the plasma to overcome the Brillouin density limit imposed by the nonneutrality of Penning trap plasmas. In an earlier experiment, we achieved enhanced plasma density at the center of a pure, electron plasma confined in a hyperbolic, Penning trap by inducing spherically convergent flow in a nonthermal plasma. The goal of this work is to induce similar flow in a positive ion plasma confined in the virtual cathode provided by a spherical, uniform density electron plasma. This approach promises the greatest flexibility in operating with multi-species plasmas (e.g. D + /T + ) or implementing temporal compression schemes such as the Periodically Oscillating Plasma Sphere of Nebel and Barnes. Here, we report on our work to produce and diagnose the necessary electron plasma

A1.5 Fusion Performance

Energy Technology Data Exchange (ETDEWEB)

Amendt, P

2011-03-31

Analysis and radiation hydrodynamics simulations for expected high-gain fusion target performance on a demonstration 1-GWe Laser Inertial Fusion Energy (LIFE) power plant in the mid-2030s timeframe are presented. The required laser energy driver is 2.2 MJ at a 0.351-{micro}m wavelength, and a fusion target gain greater than 60 at a repetition rate of 16 Hz is the design goal for economic and commercial attractiveness. A scaling-law analysis is developed to benchmark the design parameter space for hohlraum-driven central hot-spot ignition. A suite of integrated hohlraum simulations is presented to test the modeling assumptions and provide a basis for a near-term experimental resolution of the key physics uncertainties on the National Ignition Facility (NIF). The NIF is poised to demonstrate ignition by 2012 based on the central hot spot (CHS) mode of ignition and propagating thermonuclear burn [1]. This immediate prospect underscores the imperative and timeliness of advancing inertial fusion as a carbon-free, virtually limitless source of energy by the mid-21st century to substantially offset fossil fuel technologies. To this end, an intensive effort is underway to leverage success at the NIF and to provide the foundations for a prototype 'LIFE.1' engineering test facility by {approx}2025, followed by a commercially viable 'LIFE.2' demonstration power plant operating at 1 GWe by {approx}2035. The current design goal for LIFE.2 is to accommodate {approx}2.2 MJ of laser energy (entering the high-Z radiation enclosure or 'hohlraum') at a 0.351-{micro}m wavelength operating at a repetition rate of 16 Hz and to provide a fusion target yield of 132 MJ. To achieve this design goal first requires a '0-d' analytic gain model that allows convenient exploration of parameter space and target optimization. This step is then followed by 2- and 3-dimensional radiation-hydrodynamics simulations that incorporate laser beam transport, x

Superconducting focusing quadrupoles for heavy ion fusion experiments

Energy Technology Data Exchange (ETDEWEB)

Sabbi, G.L.; Faltens, A.; Leitner, M.; Lietzke, A.; Seidl, P.; Barnard, J.; Lund, S.; Martovetsky, N.; Gung, C.; Minervini, J.; Radovinsky, A.; Schultz, J.; Meinke, R.

2003-05-01

The Heavy Ion Fusion (HIF) Program is developing superconducting focusing magnets for both near-term experiments and future driver accelerators. In particular, single bore quadrupoles have been fabricated and tested for use in the High Current Experiment (HCX) at Lawrence Berkeley National Laboratory (LBNL). The next steps involve the development of magnets for the planned Integrated Beam Experiment (IBX) and the fabrication of the first prototype multi-beam focusing arrays for fusion driver accelerators. The status of the magnet R&D program is reported, including experimental requirements, design issues and test results.

Optimization of heavy metals total emission, case study: Bor (Serbia)

Science.gov (United States)

Ilić, Ivana; Bogdanović, Dejan; Živković, Dragana; Milošević, Novica; Todorović, Boban

2011-07-01

The town of Bor (Serbia) is one of the most polluted towns in southeastern Europe. The copper smelter which is situated in the centre of the town is the main pollutant, mostly because of its old technology, which leads to environmental pollution caused by higher concentrations of SO 2 and PM 10. These facts show that the word is about a very polluted region in Europe which, apart from harming human health in the region itself, poses a particular danger for wider area of southeastern Europe. Optimization of heavy metal's total emission was undertaken because years of long contamination of the soil with heavy metals of anthropogenic origin created a danger that those heavy metals may enter the food chains of animals and people, which can lead to disastrous consequences. This work represents the usage of Geographic Information System (GIS) for establishing a multifactor assessment model to quantitatively divide polluted zones and for selecting control sites in a linear programming model, combined with PROMETHEE/GAIA method, Screen View modeling system, and linear programming model. The results show that emissions at some control sites need to be cut for about 40%. In order to control the background of heavy metal pollution in Bor, the ecological environment must be improved.

User's manual of JT-60 experimental data analysis system

International Nuclear Information System (INIS)

Hirayama, Takashi; Morishima, Soichi; Yoshioka, Yuji

2010-02-01

In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is a user's manual of the JT-60 experimental data analysis system. (author)

Mobility and natural attenuation of metals and arsenic in acidic waters of the drainage system of Timok River from Bor copper mines (Serbia) to Danube River.

Science.gov (United States)

Đorđievski, Stefan; Ishiyama, Daizo; Ogawa, Yasumasa; Stevanović, Zoran

2018-06-22

Bor, Krivelj, and Bela Rivers belong to the watershed of Timok River, which is a tributary of transboundary Danube River. These rivers receive metal-rich acidic wastewater from metallurgical facilities and acid mine drainage (AMD) from mine wastes around Bor copper mines. The aim of this study was to determine the mobility and natural attenuation of metals and arsenic in rivers from Bor copper mines to Danube River during the year 2015. The results showed that metallurgical facilities had the largest impact on Bor River by discharging about 400 t of Cu per year through highly acidic wastewater (pH = 2.6). The highest measured concentrations of Cu in river water and sediments were 40 mg L -1 and 1.6%, respectively. Dissolution of calcite from limestone bedrock and a high concentration of bicarbonate ions in natural river water (about 250 mg L -1 ) enhanced the neutralization of acidic river water and subsequent chemical precipitation of metals and arsenic. Decreases in the concentrations of Al, Fe, Cu, As, and Pb in river water were mainly due to precipitation on the river bed. On the other hand, dilution played an important role in the decreases in concentrations of Mn, Ni, Zn, and Cd. Chemically precipitated materials and flotation tailings containing Fe-rich minerals (fayalite, magnetite, and pyrite) were transported toward Danube River during the periods of high discharge. This study showed that processes of natural attenuation in catchments with limestone bedrock play an important role in reducing concentrations of metals and arsenic in AMD-bearing river water.

Elements of Successful and Safe Fusion Experiment Operations

International Nuclear Information System (INIS)

Rule, K.; Cadwallader, L.; Takase, Y.; Norimatsu, T.; Kaneko, O.; Sato, M.; Savercool, R.

2009-01-01

A group of fusion safety professionals contribute to a Joint Working Group (JWG) that performs occupational safety walkthroughs of US and Japanese fusion experiments on a routine basis to enhance the safety of visiting researchers. The most recent walkthrough was completed in Japan in March 2008 by the US Safety Monitor team. This paper gives the general conclusions on fusion facility personnel safety that can be drawn from the series of walkthroughs

Current state of nuclear fusion research

International Nuclear Information System (INIS)

Naraghi, M.

1985-01-01

During the past quarter century, plasma physics and nuclear fusion research have gone through impressive development. Tokamak, is realized to be the number one candidate for nuclear fusion reactor. Two large experiments, one called Joint European Torus (JET) at Culham, England, and the other JT-60 project in Japan have been completed and have reported preliminary results. In JET an average electron density of 4x10 13 pcls/ cm 3 , ion temperatures of 3Kev and energy confinement of 0.8 sec have been achieved. However, the Zeff has been even equal to 10 which unfortunately is a source of plasma energy loss. JT-60 has not offered any appreciable results yet, however, the objectives and initial tests promise long pulse duration, with very high ion and plasma densities. Both experiments have promised to achieve conditions approaching those needed in a fusion reactor. Other important experiments will be discussed and the role of third world countries will be emphasized. (Author)

Cryogenic system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1992-01-01

This report presents a review of cryogenic system operating experiences, from particle accelerator, fusion experiment, space research, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of cryogenic component failure rates and accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with cryogenic systems are discussed, including ozone formation, effects of spills, and modeling spill behavior. This information should be useful to fusion system designers and safety analysts, such as the team working on the International Thermonuclear Experimental Reactor design

Annual report of the Fusion Research and Development Center for the period of April 1, 1980 to March 31, 1981

International Nuclear Information System (INIS)

1982-03-01

Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1980 to 1981 are described. In plasma physics research, 1.5 MW NBI heating experiments were successfully made on JFT-2 to yield an average beta value of 2.5% without any deleterious effect on plasma confinement. Joint JAERI-US/DOE ECRH experiments revealed detailed physics of plasma heating. Installation of a 1 MW ICRF system was completed. In the Doublet-III experiment, a JAERI-US/DOE cooperation program, extensive studies were made on Joule heated dee-shaped Plasmas. In theory and computation emphasis was placed on beta optimization of tokamaks. Construction of JT-60 was continued as planned. Manufacturing of the major components and facilities was advanced well, e.g. 14 out of the 19 toroidal field coils were completed. Construction of the buildings was continued at the Naka site. In plasma heating technology, construction of the JT-60 prototype NBI unit was in progress, and development works on ion sources and beam line components as well. Trial fabrication of high power klystrons for JT-60 RF heating was started. In superconducting magnet technology, cool-down tests of cluster coils were successfully made. Manufacturing of the Japanese coil for the Large Coil Task under the auspiece of IEA, and of a Nb 3 Sn test module coil was continued. A test facility for the LCT coil was completed. Basic studies on key processes of tritium technology were continued using hydrogen and deuterium. Design of the Tritium Process Laboratory was continued. Development of first wall materials for JT-60 was advanced. Extensive tests were made on a number of low-Z coatings. Design studies of INTOR, a cooperative work in IAEA, were continued. In addition, design of the Fusion Experimental Reactor was started on a conventional type tokamak reactor and swimming pool type one. (author)

Finanční analýza podniku IDEAL AUTOMOTIVE Bor, s.r.o.

OpenAIRE

Velebová, Štěpánka

2009-01-01

The aim of this bachelor thesis is to identify the financial situation of IDEAL AUTOMOTIVE Bor, Ltd., determine the strenghts and weaknesses of the company, and suggest some ideas of what to do in the future, so that the company could prosper

Conventional sources of fast neutrons in 'cold fusion' experiments

International Nuclear Information System (INIS)

Cribier, M.; Spiro, M.; Favier, J.

1989-04-01

In 'cold fusion' experiments with heavy water a source of neutrons is the dissociation of deuterium induced by alpha particles emitted by natural occurring radioisotopes. We evaluate the rate of fast neutron emission as a function of the concentration of U, Th, Rn in contact with deuterium and discuss the possibility that the neutrons claimed to have been observed in 'cold fusion' experiments could be due to this conventional source

Necropolis on Bor lake: New reports on Bronze age burial

Directory of Open Access Journals (Sweden)

Kapuran Aleksandar

2011-01-01

Full Text Available This article deals with the social and anthropological aspects of burial rituals during the Middle Bronze Age in Timočka Krajina. Decades of systematic research of necropolises and reconnaissance in the basin of the Crni Timok proved an increase in number of sites around ore - rich areas of the east Kučaj mountains as well as around Romuliana site and the fertile valleys of Džanovo polje (Map. 1. The quantitative increase in settlements was reflected by the emergence of large necropolises, only three of which have been systematically explored; those in Trnjani, Magura and Bor Lake (Fig. 1; Plan 1. Analysis of geographical features of many settlements and their position in relation to natural resources helped define two communities, one of which carried out mining and metallurgical activities, while the other group engaged in the production of food. Both groups lived in the immediate vicinity and mutual dependence, functioning within a developed market for copper production. During the exploration of the necropolis near Bor Lake in 1997, the remains of burnt skeletons were collected from burial structures 2/97 and 13/97 (Fig. 2; Plans 2 and 3. Anthropological analysis of the cremated remains of the deceased showed that high temperatures were used during the cremation process, which we assume could have only been achieved in metallurgical furnaces. This is confirmed by the fact that the skeletal fragments contain traces of melted metal, as well as finds of bronze slag inside urns and grave structures in the necropolis in Trnjani (Figs. 3 and 4; Tables 1-4. Burial ritual of this kind was not proved by systematic archaeological research of necropolises in the basin of Crni Timok, although anthropological data collected from necropolises linked to metallurgical settlements may indicate some guidelines in the ritual cremation of prominent members of these communities. [Projekat Ministarstva nauke Republike Srbije, br. 177020: Arheologija Srbije

Annual report of Naka Fusion Research Establishment for the period from April 1, 1992 to March 31, 1993

International Nuclear Information System (INIS)

Ohta, Mitsuru; Shimizu, Katsuhiro; Fujii, Tuneyuki; Nishi, Masataka; Matoba, Tohru; Kanazawa, Tetsuo

1993-10-01

Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1992 to March 31, 1993. The main objectives of JT-60U experiments in FY1992 were to improve plasma confinement properties and to study non-inductive current drive. High-βp H-mode performance obtained in March 1993 was highlighted, in particular, a world-record fusion-triple-product of 1.1 x 10 21 m -3 · s · keV, and record values for JT-60 of neutron yield rate of 5.6 x 10 16 s -1 , stored energy of 8.3 MJ, and H-factor of 3.6. The JFT-2M continued to study divertor biasing and ergodic limiter experiments, and disruption control by ECH. The study in Plasma Theory and Computation focused on scaling laws of the thermal energy confinement and the bootstrap current, the iron temperature gradient instability, the MHD stability, the rotation damping by external magnetic error field, and the burning plasma of D- 3 He fusion. As for the fusion engineering research, the vacuum technology advanced the development of a high resolution quadrupole mass spectrometer, etc. The super-conducting Demo Poloidal Coil achieved pulsed operation with 7 T in 0.5 s, and newly developed conductors made of Nb 3 Al and Nb 3 Sn showed 40 kA at 12 T and 82 kA at 13.6 T, respectively. A high energy H - beam of 350 kV, 0.17 A was produced with a current density of 10 mA/cm 2 . Much effort was made in developing the ECH gyrotron with an output power of 460 kW at 120 GHz for 100 ms. The main progress in the Tritium Systems Test Assembly (a US/Japan collaboration) was continuous loop run for 25 days. The developed plasma facing components posed no problem under a heat flux of 20 MW/m 2 for 30 s over 1000 thermal cycles. (J.P.N.)

Fire protection system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor

Fire protection system operating experience review for fusion applications

Energy Technology Data Exchange (ETDEWEB)

Cadwallader, L.C.

1995-12-01

This report presents a review of fire protection system operating experiences from particle accelerator, fusion experiment, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of fire protection system component failure rates and fire accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with these systems are discussed, including spurious operation. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor.

Activation and Radiation Damage Behaviour of Russian Structural Materials for Fusion Reactors in the Fission and Fusion Reactors

International Nuclear Information System (INIS)

Blokhin, A.; Demin, N.; Chernov, V.; Leonteva-Smirnova, M.; Potapenko, M.

2006-01-01

Various structural low (reduced) activated materials have been proposed as a candidate for the first walls-blankets of fusion reactors. One of the main problems connected with using these materials - to minimise the production of long-lived radionuclides from nuclear transmutations and to provide with good technological and functional properties. The selection of materials and their metallurgical and fabrication technologies for fusion reactor components is influenced by this factor. Accurate prediction of induced radioactivity is necessary for the development of the fusion reactor materials. Low activated V-Ti-Cr alloys and reduced activated ferritic-martensitic steels are a leading candidate material for fusion first wall and blanket applications. At the present time a range of compositions and an impurity level are still being investigated to better understand the sensitive of various functional and activation properties to small compositional variations and impurity level. For the two types of materials mentioned above (V-Ti-Cr alloys and 9-12 % Cr f/m steels) and manufactured in Russia (Russia technologies) the analysis of induced activity, hydrogen and helium-production as well as the accumulation of such elements as C, N, O, P, S, Zn and Sn as a function of irradiation time was performed. Materials '' were irradiated '' by fission (BN-600, BOR-60) and fusion (Russian DEMO-C Reactor Project) typical neutron spectra with neutron fluency up to 10 22 n/cm 2 and the cooling time up to 1000 years. The calculations of the transmutation of elements and the induced radioactivity were carried out using the FISPACT inventory code, and the different activation cross-section libraries like the ACDAM, FENDL-2/A and the decay data library FENDL-2/D. It was shown that the level of impurities controls a long-term behaviour of induced activity and contact dose rate for materials. From this analysis the concentration limits of impurities were obtained. The generation of gas

Utilization of fusion neutrons in the tokamak fusion test reactor for blanket performance testing and other nuclear engineering experiments

International Nuclear Information System (INIS)

Caldwell, C.S.; Pettus, W.G.; Schmotzer, J.K.; Welfare, F.; Womack, R.

1979-01-01

In addition to developing a set of reacting-plasma/blanket-neutronics benchmark data, the TFTR fusion application experiments would provide operational experience with fast-neutron dosimetry and the remote handling of blanket modules in a tokamak reactor environment; neutron streaming and hot-spot information invaluable for the optimal design of penetrations in future fusion reactors; and the identification of the most damage-resistant insulators for a variety of fusion-reactor components

Vacuum system operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1994-03-01

This report presents a review of vacuum system operating experiences from particle accelerator, fusion experiment, space simulation chamber, and other applications. Safety relevant operating experiences and accident information are discussed. Quantitative order-of-magnitude estimates of vacuum system component failure rates and accident initiating event frequencies are presented for use in risk assessment, reliability, and availability studies. Safety concerns with vacuum systems are discussed, including personnel safety, foreign material intrusion, and factors relevant to vacuum systems being the primary confinement boundary for tritium and activated dusts. This information should be useful to fusion system designers and safety analysts, such as the team working on the Engineering Design Activities for the International Thermonuclear Experimental Reactor

P2X1 Receptor Antagonists Inhibit HIV-1 Fusion by Blocking Virus-Coreceptor Interactions.

Science.gov (United States)

Giroud, Charline; Marin, Mariana; Hammonds, Jason; Spearman, Paul; Melikyan, Gregory B

2015-09-01

HIV-1 Env glycoprotein-mediated fusion is initiated upon sequential binding of Env to CD4 and the coreceptor CXCR4 or CCR5. Whereas these interactions are thought to be necessary and sufficient to promote HIV-1 fusion, other host factors can modulate this process. Previous studies reported potent inhibition of HIV-1 fusion by selective P2X1 receptor antagonists, including NF279, and suggested that these receptors play a role in HIV-1 entry. Here we investigated the mechanism of antiviral activity of NF279 and found that this compound does not inhibit HIV-1 fusion by preventing the activation of P2X1 channels but effectively blocks the binding of the virus to CXCR4 or CCR5. The notion of an off-target effect of NF279 on HIV-1 fusion is supported by the lack of detectable expression of P2X1 receptors in cells used in fusion experiments and by the fact that the addition of ATP or the enzymatic depletion of ATP in culture medium does not modulate viral fusion. Importantly, NF279 fails to inhibit HIV-1 fusion with cell lines and primary macrophages when added at an intermediate stage downstream of Env-CD4-coreceptor engagement. Conversely, in the presence of NF279, HIV-1 fusion is arrested downstream of CD4 binding but prior to coreceptor engagement. NF279 also antagonizes the signaling function of CCR5, CXCR4, and another chemokine receptor, as evidenced by the suppression of calcium responses elicited by specific ligands and by recombinant gp120. Collectively, our results demonstrate that NF279 is a dual HIV-1 coreceptor inhibitor that interferes with the functional engagement of CCR5 and CXCR4 by Env. Inhibition of P2X receptor activity suppresses HIV-1 fusion and replication, suggesting that P2X signaling is involved in HIV-1 entry. However, mechanistic experiments conducted in this study imply that P2X1 receptor is not expressed in target cells or involved in viral fusion. Instead, we found that inhibition of HIV-1 fusion by a specific P2X1 receptor antagonist, NF

Fusion-fission dynamics and perspectives of future experiments

International Nuclear Information System (INIS)

Zagrebaev, V.I.; Itkis, M.G.; Oganessian, Yu.Ts.

2003-01-01

The paper is focused on reaction dynamics of superheavy-nucleus formation and decay at beam energies near the Coulomb barrier. The aim is to review the things we have learned from recent experiments on fusion-fission reactions leading to the formation of compound nuclei with Z ≥ 102 and from their extensive theoretical analysis. Major attention is paid to the dynamics of formation of very heavy compound nuclei taking place in strong competition with the process of fast fission (quasifission). The choice of collective degrees of freedom playing a fundamental role and finding the multidimensional driving potential and the corresponding dynamic equation regulating the whole process are discussed. A possibility of deriving the fission barriers of superheavy nuclei directly from performed experiments is of particular interest here. In conclusion, the results of a detailed theoretical analysis of available experimental data on the 'cold' and 'hot' fusion-fission reactions are presented. Perspectives of future experiments are discussed along with additional theoretical studies in this field needed for deeper understanding of the fusion-fission processes of very heavy nuclear systems

Peculiarities of 137Cs accumulation by macromycetes in dry bors of Ukrainian Polessye

International Nuclear Information System (INIS)

Orlov, O.O.; Kurbet, T.B.; Kalyish, O.B.; Prishchepa, O.L.

2001-01-01

The main ecological peculiarities of dry bor in Ukrainian Polessye were given. Research were carried out in Central Polessie of Ukraine during 1997 - 1999. Results were obtained due to spectrometric measurement of specific activity of 137 Cs in fruit bodies of mushrooms and in the soil. Species composition of macromycetes was divided on homogeneous groups on intensity of 13 7Cs accumulation. Amanita porphyria, A. muscaria and Tricholoma portentosum belong to the group of weak 137 Cs accumulation from the soil (TF = 15 - 20); Amanita pantherina, A. phalloides, Cantharellus cibarius, Boletus edulis, Tricholoma flavovirens and Laccaria laccata - to the group of moderate radionuclide accumulation (TF = 30 - 55). The group of strong 137 Cs accumulation (TF = 100 - 180) consists of Suillus variegates, S. bovines and Hydnum imbricatum; and group of very strong accumulation (TF 200 - 280) - of Xerocomus badius, Lactarius rufus, Russula xerampelina, Cortinarius varius and Paxillus involutus. Cortinarius sanguineus (with TF 400) is an accumulator of 137 Cs. Comparative evaluation of dry bor was given from the point of view of purchase of edible macromycetes in it

Operation and management manual of JT-60 experimental data analysis system

International Nuclear Information System (INIS)

Hirayama, Takashi; Morishima, Soichi

2014-03-01

In the Japan Atomic Energy Agency Naka Fusion Institute, a lot of experiments have been conducted by using the large tokamak device JT-60 aiming to realize fusion power plant. In order to optimize the JT-60 experiment and to investigate complex characteristics of plasma, JT-60 experimental data analysis system was developed and used for collecting, referring and analyzing the JT-60 experimental data. Main components of the system are a data analysis server and a database server for the analyses and accumulation of the experimental data respectively. Other peripheral devices of the system are magnetic disk units, NAS (Network Attached Storage) device, and a backup tape drive. This is an operation and management manual the JT-60 experimental data analysis system. (author)

FENDL-3 benchmark test with neutronics experiments related to fusion in Japan

International Nuclear Information System (INIS)

Konno, Chikara; Ohta, Masayuki; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi

2014-01-01

Highlights: •We have benchmarked FENDL-3.0 with integral experiments with DT neutron sources in Japan. •The FENDL-3.0 is as accurate as FENDL-2.1 and JENDL-4.0 or more. •Some data in FENDL-3.0 may have some problems. -- Abstract: The IAEA supports and promotes the gathering of the best data from evaluated nuclear data libraries for each nucleus involved in fusion reactor applications and compiles these data as FENDL. In 2012, the IAEA released a major update to FENDL, FENDL-3.0, which extends the neutron energy range from 20 MeV to greater than 60 MeV for 180 nuclei. We have benchmarked FENDL-3.0 versus in situ and TOF experiments using the DT neutron source at FNS at the JAEA and TOF experiments using the DT neutron source at OKTAVIAN at Osaka University in Japan. The Monte Carlo code MCNP-5 and the ACE file of FENDL-3.0 supplied from the IAEA were used for the calculations. The results were compared with measured ones and those obtained using the previous version, FENDL-2.1, and the latest version, JENDL-4.0. It is concluded that FENDL-3.0 is as accurate as or more so than FENDL-2.1 and JENDL-4.0, although some data in FENDL-3.0 may be problematic

Experiences with a Barista Robot, FusionBot

Science.gov (United States)

Limbu, Dilip Kumar; Tan, Yeow Kee; Wong, Chern Yuen; Jiang, Ridong; Wu, Hengxin; Li, Liyuan; Kah, Eng Hoe; Yu, Xinguo; Li, Dong; Li, Haizhou

In this paper, we describe the implemented service robot, called FusionBot. The goal of this research is to explore and demonstrate the utility of an interactive service robot in a smart home environment, thereby improving the quality of human life. The robot has four main features: 1) speech recognition, 2) object recognition, 3) object grabbing and fetching and 4) communication with a smart coffee machine. Its software architecture employs a multimodal dialogue system that integrates different components, including spoken dialog system, vision understanding, navigation and smart device gateway. In the experiments conducted during the TechFest 2008 event, the FusionBot successfully demonstrated that it could autonomously serve coffee to visitors on their request. Preliminary survey results indicate that the robot has potential to not only aid in the general robotics but also contribute towards the long term goal of intelligent service robotics in smart home environment.

Annual report of Naka Fusion Research Establishment from April 1, 2003 to March 31, 2004

International Nuclear Information System (INIS)

Hoshino, Katsumichi; Umeda, Naotaka; Tsuji, Hiroshi; Yoshida, Hidetoshi; Nagami, Masayuki

2004-11-01

This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2003 to 31 March, 2004. The activities in the Naka Fusion Research Establishment are highlighted by researches in JT-60 and JFT-2M, theoretical and analytical plasma researches, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction. (J.P.N.)

Evaluation of performance of select fusion experiments and projected reactors. Final report

International Nuclear Information System (INIS)

Miley, G.H.

1978-10-01

The performance of NASA Lewis fusion experiments (SUMMA and Bumpy Torus) is compared with other experiments and that necessary for a power reactor. Key parameters cited are gain (fusion power/input power) and the time average fusion power, both of which may be more significant for real fusion reactors than the commonly used Lawson parameter. The NASA devices are over 10 orders of magnitude below the required powerplant values in both gain and time average power. The best experiments elsewhere are also as much as 4 to 5 orders of magnitude low. However, the NASA experiments compare favorably with other alternate approaches that have received less funding than the mainline experiments. The steady-state character and efficiency of plasma heating are strong advantages of the NASA approach. The problem, though, is to move ahead to experiments of sufficient size to advance in gain and average power parameters

Tritium experience in the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Skinner, C.H.; Blanchard, W.; Hosea, J.; Mueller, D.; Nagy, A.; Hogan, J.

1998-01-01

Tritium management is a key enabling element in fusion technology. Tritium fuel was used in 3.5 years of successful deuterium-tritium (D-T) operations in the Tokamak Fusion Test Reactor (TFTR) at the Princeton Plasma Physics Laboratory. The D-T campaign enabled TFTR to explore the transport, alpha physics, and MHD stability of a reactor core. It also provided experience with tritium retention and removal that highlighted the importance of these issues in future D-T machines. In this paper, the authors summarize the tritium retention and removal experience in TFTR and its implications for future reactors

Fire hazard analysis for fusion energy experiments

International Nuclear Information System (INIS)

Alvares, N.J.; Hasegawa, H.K.

1979-01-01

The 2XIIB mirror fusion facility at Lawrence Livermore Laboratory (LLL) was used to evaluate the fire safety of state-of-the-art fusion energy experiments. The primary objective of this evaluation was to ensure the parallel development of fire safety and fusion energy technology. Through fault-tree analysis, we obtained a detailed engineering description of the 2XIIB fire protection system. This information helped us establish an optimum level of fire protection for experimental fusion energy facilities as well as evaluate the level of protection provided by various systems. Concurrently, we analyzed the fire hazard inherent to the facility using techniques that relate the probability of ignition to the flame spread and heat-release potential of construction materials, electrical and thermal insulations, and dielectric fluids. A comparison of the results of both analyses revealed that the existing fire protection system should be modified to accommodate the range of fire hazards inherent to the 2XIIB facility

Driven reconnection in magnetic fusion experiments

International Nuclear Information System (INIS)

Fitzpatrick, R.

1995-11-01

Error fields (i.e. small non-axisymmetric perturbations of the magnetic field due to coil misalignments, etc.) are a fact of life in magnetic fusion experiments. What effects do error fields have on plasma confinement? How can any detrimental effects be alleviated? These, and other, questions are explored in detail in this lecture using simple resistive magnetohydrodynamic (resistance MHD) arguments. Although the lecture concentrates on one particular type of magnetic fusion device, namely, the tokamak, the analysis is fairly general and could also be used to examine the effects of error fields on other types of device (e.g. Reversed Field Pinches, Stellerators, etc.)

Axial lumbar interbody fusion: a 6-year single-center experience

Directory of Open Access Journals (Sweden)

Zeilstra DJ

2013-08-01

Full Text Available Dick J Zeilstra,1 Larry E Miller,2,3 Jon E Block3 1Bergman Clinics, Naarden and NedSpine, Ede, The Netherlands; 2Miller Scientific Consulting, Inc, Arden, NC, USA; 3The Jon Block Group, San Francisco, CA, USA Introduction: The aim of this study is to report our 6-year single-center experience with L5–S1 axial lumbar interbody fusion (AxiaLIF. Methods: A total of 131 patients with symptomatic degenerative disc disease refractory to nonsurgical treatment were treated with AxiaLIF at L5–S1, and were followed for a minimum of 1 year (mean: 21 months. Main outcomes included back and leg pain severity, Oswestry Disability Index score, working status, analgesic medication use, patient satisfaction, and complications. Computed tomography was used to determine postoperative fusion status. Results: No intraoperative complications, including vascular, neural, urologic, or bowel injuries, were reported. Back and leg pain severity decreased by 51% and 42%, respectively, during the follow-up period (both P < 0.001. Back function scores improved 50% compared to baseline. Clinical success, defined as improvement ≥30%, was 67% for back pain severity, 65% for leg pain severity, and 71% for back function. The employment rate increased from 47% before surgery to 64% at final follow-up (P < 0.001. Less than one in four patients regularly used analgesic medications postsurgery. Patient satisfaction with the AxiaLIF procedure was 83%. The fusion rate was 87.8% at final follow-up. During follow-up, 17 (13.0% patients underwent 18 reoperations on the lumbar spine, including pedicle screw fixation (n = 10, total disc replacement of an uninvolved level (n = 3, facet screw fixation (n = 3, facet screw removal (n = 1, and interbody fusion at L4–L5 (n = 1. Eight (6.1% reoperations were at the index level. Conclusion: Single-level AxiaLIF is a safe and effective means to achieve lumbosacral fusion in patients with symptomatic degenerative disc disease. Keywords: Axia

Parameter studies for a two-component fusion experiment

International Nuclear Information System (INIS)

Towner, H.H.

1975-01-01

The sensitivity of the energy multiplication of a two-component fusion experiment is examined relative to the following parameters: energy confinement time (tau/sub E/), particle confinement time (tau/sub p/), effective Z of the plasma (Z/sub eff/), injection rate (j/sub I/) and injection energy (E/sub I/). The Energy Research and Development Administration recently approved funding for such a fusion device (the Toroidal Fusion Test Reactor or TFTR) which will be built at the Princeton Plasma Physics Laboratory. Hence, such a parameter study seems both timely and necessary. This work also serves as an independent check on the design values proposed for the TFTR to enable it to achieve energy breakeven (F = 1). Using the nominal TFTR design parameters and a self-consistent ion-electron power balance, the maximum F-value is found to be approximately 1.2 which occurs at an injection energy of approximately 210 KeV. The injector operation, i.e. its current and energy capability are shown to be a very critical factor in the TFTR performance. However, if the injectors meet the design objectives, there appears to be sufficient latitude in the other parameters to offer reasonable assurance that energy breakeven can be achieved. (U.S.)

Mission and design of the Fusion Ignition Research Experiment (FIRE)

International Nuclear Information System (INIS)

Meade, D.M.; Jardin, S.C.; Schmidt, J.

2001-01-01

Experiments are needed to test and extend present understanding of confinement, macroscopic stability, alpha-driven instabilities, and particle/power exhaust in plasmas dominated by alpha heating. A key issue is to what extent pressure profile evolution driven by strong alpha heating will act to self-organize advanced configurations with large bootstrap current fractions and internal transport barriers. A design study of a Fusion Ignition Research Experiment (FIRE) is underway to assess near term opportunities for advancing the scientific understanding of self-heated fusion plasmas. The emphasis is on understanding the behavior of fusion plasmas dominated by alpha heating (Q≥5) that are sustained for durations comparable to the characteristic plasma time scales (≥20 τ E and ∼τ skin , where τ skin is the time for the plasma current profile to redistribute at fixed current). The programmatic mission of FIRE is to attain, explore, understand and optimize alpha-dominated plasmas to provide knowledge for the design of attractive magnetic fusion energy systems. The programmatic strategy is to access the alpha-heating-dominated regime with confidence using the present advanced tokamak data base (e.g., Elmy-H-mode, ≤0.75 Greenwald density) while maintaining the flexibility for accessing and exploring other advanced tokamak modes (e. g., reversed shear, pellet enhanced performance) at lower magnetic fields and fusion power for longer durations in later stages of the experimental program. A major goal is to develop a design concept that could meet these physics objectives with a construction cost in the range of $1B. (author)

Semi empirical model for astrophysical nuclear fusion reactions of 1≤Z≤15

International Nuclear Information System (INIS)

Manjunatha, H.C.; Seenappa, L.; Sridhar, K.N.

2017-01-01

The fusion reaction is one of the most important reactions in the stellar evolution. Due to the complicated reaction mechanism of fusion, there is great uncertainty in the reaction rate which limits our understanding of various stellar objects. Low z elements are formed through many fusion reactions such as "4He+"1"2C→"1"6O, "1"2C+"1"2C→"2"0Ne+"4He, "1"2C+"1"2C→"2"3Na, "1"2C+"1"2C→"2"3Mg, "1"6O+"1"6O→"2"8Si+"4He, "1"2C+"1H→"1"3N and "1"3C+"4He→"1"6O. A detail study is required on Coulomb and nuclear interaction in formation of low Z elements in stars through fusion reactions. For astrophysics, the important energy range extends from 1 MeV to 3 MeV in the center of mass frame, which is only partially covered by experiments. In the present work, we have studied the basic fusion parameters such as barrier heights (V_B), positions (R_B), curvature of the inverted parabola (ħω_1) for fusion barrier, cross section and compound nucleus formation probability (P_C_N) and fusion process in the low Z element (1≤Z≤15) formation process. For each isotope, we have studied all possible projectile-target combinations. We have also studied the astrophysical S(E) factor for these reactions. Based on this study, we have formulated the semi empirical relations for barrier heights (V_B), positions (R_B), curvature of the inverted parabola and hence for the fusion cross section and astrophysical S(E) factor. The values produced by the present model compared with the experiments and data available in the literature. (author)

Energetic Particle Physics In Fusion Research In Preparation For Burning Plasma Experiments

Energy Technology Data Exchange (ETDEWEB)

Gorelenkov, Nikolai N [PPPL

2013-06-01

The area of energetic particle (EP) physics of fusion research has been actively and extensively researched in recent decades. The progress achieved in advancing and understanding EP physics has been substantial since the last comprehensive review on this topic by W.W. Heidbrink and G.J. Sadler [1]. That review coincided with the start of deuterium-tritium (DT) experiments on Tokamak Fusion Test reactor (TFTR) and full scale fusion alphas physics studies. Fusion research in recent years has been influenced by EP physics in many ways including the limitations imposed by the "sea" of Alfven eigenmodes (AE) in particular by the toroidicityinduced AEs (TAE) modes and reversed shear Alfven (RSAE). In present paper we attempt a broad review of EP physics progress in tokamaks and spherical tori since the first DT experiments on TFTR and JET (Joint European Torus) including helical/stellarator devices. Introductory discussions on basic ingredients of EP physics, i.e. particle orbits in STs, fundamental diagnostic techniques of EPs and instabilities, wave particle resonances and others are given to help understanding the advanced topics of EP physics. At the end we cover important and interesting physics issues toward the burning plasma experiments such as ITER (International Thermonuclear Experimental Reactor).

Annual report of the Naka Fusion Research Establishment for the period of April 1, 1990 to March 31, 1991

International Nuclear Information System (INIS)

1991-10-01

R and D activities of the Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1990 to March 31, 1991. Since the shutdown of JT-60 in November 1989, the reconstruction work of the JT-60 device was continued until the end of March 1991. In the JT-60 Upgrade, the poloidal field coils and vacuum vessel were renewed and the plasma current was planned to increase up to 6 MA with lower single null divertor. The divertor plates were designed to be toroidally continuous and to use high-heat-conduction C/C composite materials. Another objective of JT-60U is to facilitate tokamak experiments with deuterium as the working gas. In the JFT-2M program, a system for divertor bias experiments was brought into operation and initial experiments were started to study its effects on plasma discharges. Effects of ergodic magnetic limiter on H-modes were examined and stationary H-modes were obtained under the control of ergodic magnetic limiter currents. The DIII-D program was highlighted by the attainment of 11% beta with a double null divertor plasma. As for the fusion engineering research, development activities of the ceramic turbo-viscous pump and the surface insulation techniques for the tokamak in-vessel components are remarked in the vacuum technology area. In the high heat flux experiments with the JAERI Electron Beam Irradiation Stand (JEBIS), carbon-based materials and refractory metals were tested to evaluate surface erosion at plasma disruptions. The ITER Conceptual Design Activities, which began in April 1988 under the auspices of the IAEA, were successfully completed in December 1990. A lot of contributions to the program were made by JAERI people to support the design and R and D activities and to prepare a plan for the forthcoming Engineering Design Activities. (J.P.N.)

Annual report of Naka Fusion Research Establishment. From April 1, 1995 to March 31, 1996

Energy Technology Data Exchange (ETDEWEB)

Shimada, Michiya; Asakura, Nobuyuki; Moriyama, Shinichi; Yamanishi, Toshihiko; Seki, Masahiro; Takahashi, Ichiro [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment; eds.

1996-11-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1995 to March 31, 1996. The activities in Naka Fusion Research Establishment are highlighted by high-temperature plasma research in JT-60U and JFT-2M, and progress in ITER-EDA, including technology development. (author)

Annual report of Naka Fusion Research Establishment from April 1, 1997 to March 31, 1998

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-11-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1997 to March 31, 1998. The activities in Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M, and progress in ITER-EDA, including technology development. (J.P.N.)

New piezo driven gas inlet valve for fusion experiments

International Nuclear Information System (INIS)

Usselmann, E.; Hemmerich, J.L.; How, J.; Holland, D.; Orchard, J.; Winkel, T.; Schargitz, U.; Pocheim, N.

1989-01-01

The gas inlet valves used at the JET experiment are described and their performances are discussed. A new gas-valve development suitable to replace the existing valves at JET and for future use in large fusion experiments is presented. The new valve is equipped with a piezo-electric translator and has a dosing range of 0-800 mbarls -1 for D 2 . The operating mode of the valve is fail-safe closed with a leak-rate of ≤ 10 -9 mbarls -1 . The design, the test results and throughput values in dependence of filling pressure and control voltage are presented and experiences with the prototype valve as a new gas inlet valve for the JET operation are described

Production of hollow microspheres for inertial confinement fusion experiments

International Nuclear Information System (INIS)

Cook, R.

1994-12-01

The targets used in inertial confinement fusion (ICF) experiments at the Lawrence Livermore National Laboratory are plastic capsules roughly 0.5 mm in diameter. The capsules, which typically have wall thicknesses from 20 to 60 μm, must possess extraordinary symmetry and concentricity and must have surface finishes of less than 1000 Angstrom peak-to-valley variation over surface contours of from 10 to 100's of μm. This paper reviews the fabrication of these capsules, focusing on the production of the thin-walled polystyrene microshell mandrel around which the capsule is built. The relationship between the capsule characteristics, especially surface finish, and capsule performance is discussed, as are the methods of surface characterization and modification necessary for experiments designed to study the effects of surface roughness on implosion dynamics. Targets for the next generation of ICF facilities using more powerful laser drivers will have to be larger while meeting the same or even more stringent symmetry and surface finish requirements. Some of the technologies for meeting these needs are discussed briefly

Fusion technology development annual report, October 1, 1995--September 30, 1996

International Nuclear Information System (INIS)

1997-03-01

In FY96, the General Atomics (GA) Fusion Group made significant contributions to the technology needs of the magnetic fusion program. The work is reported in the following sections on Fusion Power Plant Design Studies (Section 2), Plasma Interactive Materials (Section 3), SiC/SiC Composite Material Development (Section 4), Magnetic Diagnostic Probes (Section 5) and RF Technology (Section 6). Meetings attended and publications are listed in their respective sections. The overall objective of GA's fusion technology research is to develop the technologies necessary for fusion to move successfully from present-day physics experiments to ITER and other next-generation fusion experiments, and ultimately to fusion power plants. To achieve this overall objective, the authors carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and they conduct research to develop basic knowledge about these technologies, including plasma technologies, fusion nuclear technologies, and fusion materials. They continue to be committed to the development of fusion power and its commercialization by US industry

Cold, muon-catalyzed fusion - just another swarm experiment?

International Nuclear Information System (INIS)

Robson, R.E.

1992-01-01

The paper briefly reviewed the muon-catalyzed fusion cycle and indicated how it may be likened to a swarm experiment. In particular, it has been pointed out that an external electric field can influence the properties of a muon swarm (and reactive derivatives), just as it can for ion and electron swarms. Since n 0 is typically around liquid hydrogen densities, very large fields, E≥10 9 V/m, would be required to achieve the desired outcome. This is presently achievable in small regions of intense laser focus, but it remains to be seen whether muon-catalyzed fusion experiments can actually be influenced in this way. 20 refs., 4 figs

Csapody, Tamás. 2014. Bortól Szombathelyig - Tanulmányok a bori munkaszolgálatról és a bori munkaszolgálatosok részleges névlistája ('From Bor to Szombathely- Studies on the Forced Labor Service at Bor Camp and the Partial List of the Forced Laborers in Bor'. Budapest: Zrinyi Kadó. 254 pp. ; Csapody, Tamás. 2015. A Cservenkai tömeggyilkosság ('The Mass Murder at Cservenka'. Budapest: Zsidó Tudományok Szabadegyeteme Alapítvány. 150 pp.

Directory of Open Access Journals (Sweden)

Julia Bock

2016-10-01

Full Text Available Csapody, Tamás. 2014. Bortól Szombathelyig - Tanulmányok a bori munkaszolgálatról és a bori munkaszolgálatosok részleges névlistája ('From Bor to Szombathely- Studies on the Forced Labor Service at Bor Camp and the Partial List of the Forced Laborers in Bor'. Budapest: Zrinyi Kadó. 254 pp. ; Csapody, Tamás. 2015. A Cservenkai tömeggyilkosság ('The Mass Murder at Cservenka'. Budapest: Zsidó Tudományok Szabadegyeteme Alapítvány. 150 pp. (e-book; a shorter version is accessible at: http://zsido.com/konyvek/a-cservenkai-tomeggyilkossag/.

Inertial fusion experiments and theory

International Nuclear Information System (INIS)

Mima, Kunioki; Tikhonchuk, V.; Perlado, M.

2011-01-01

Inertial fusion research is approaching a critical milestone, namely the demonstration of ignition and burn. The world's largest high-power laser, the National Ignition Facility (NIF), is under operation at the Lawrence Livermore National Laboratory (LLNL), in the USA. Another ignition machine, Laser Mega Joule (LMJ), is under construction at the CEA/CESTA research centre in France. In relation to the National Ignition Campaign (NIC) at LLNL, worldwide studies on inertial fusion applications to energy production are growing. Advanced ignition schemes such as fast ignition, shock ignition and impact ignition, and the inertial fusion energy (IFE) technology are under development. In particular, the Fast Ignition Realization Experiment (FIREX) at the Institute of Laser Engineering (ILE), Osaka University, and the OMEGA-EP project at the Laboratory for Laser Energetics (LLE), University Rochester, and the HiPER project in the European Union (EU) for fast ignition and shock ignition are progressing. The IFE technology research and development are advanced in the frameworks of the HiPER project in EU and the LIFE project in the USA. Laser technology developments in the USA, EU, Japan and Korea were major highlights in the IAEA FEC 2010. In this paper, the status and prospects of IFE science and technology are described.

Vacuum engineering for fusion research and fusion reactors

International Nuclear Information System (INIS)

Pittenger, L.C.

1976-01-01

The following topics are described: (1) surface pumping by cryogenic condensation, (2) operation of large condensing cryopumps, (3) pumping for large fusion experiments, and (4) vacuum technology for fusion reactors

Numerical Experiments Providing New Insights into Plasma Focus Fusion Devices

Directory of Open Access Journals (Sweden)

Sing Lee

2010-04-01

Full Text Available Recent extensive and systematic numerical experiments have uncovered new insights into plasma focus fusion devices including the following: (1 a plasma current limitation effect, as device static inductance is reduced towards very small values; (2 scaling laws of neutron yield and soft x-ray yield as functions of storage energies and currents; (3 a global scaling law for neutron yield as a function of storage energy combining experimental and numerical data showing that scaling deterioration has probably been interpreted as neutron ‘saturation’; and (4 a fundamental cause of neutron ‘saturation’. The ground-breaking insights thus gained may completely change the directions of plasma focus fusion research.

Physics Regimes in the Fusion Ignition Research Experiment (FIRE)

International Nuclear Information System (INIS)

D.M. Meade; S.C.Jardin; C.E. Kessel; M.A. Ulrickson; J.H. Schultz; P.H. Rutherford; J.A. Schmidt; J.C. Wesley; K.M. Young; N.A.Uckan; R.J. Thome; P. Heitzenroeder; B.E. Nelson; and C.C.Baker

2001-01-01

Burning plasma science is recognized widely as the next frontier in fusion research. The Fusion Ignition Research Experiment (FIRE) is a design study of a next-step burning plasma experiment with the goal of developing a concept for an experimental facility to explore and understand the strong nonlinear coupling among confinement, magnetohydrodynamic (MHD) self-heating, stability, edge physics, and wave-particle interactions that is fundamental to fusion plasma behavior. This will require plasmas dominated by alpha heating (Q greater than or equal to 5) that are sustained for a duration comparable to characteristic plasma timescales (greater than or equal to 10) tau(subscript ''E''), approximately 4 tau(subscript ''He''), approximately 2 tau(subscript ''skin''). The work reported here has been undertaken with the objective of finding the minimum size (cost) device to achieve these physics goals

Annual report of Naka Fusion Research Establishment from April 1, 1994 to March 31, 1995

Energy Technology Data Exchange (ETDEWEB)

Nagashima, Takashi; Naito, Osamu; Ogiwara, Norio; Saigusa, Mikio; Seki, Masahiro; Murasawa, Michihiko; Uehara, Yusuke [eds.; Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

1995-11-01

Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1994 to March 31, 1995. The main objectives of the JT-60 experiments are: confinement improvement, impurity control and divertor studies, steady-state studies, and energetic particle physics. JFT-2M experiments progressed in the momentum transport study by applying an external helical field and toroidal momentum input with NBI, and also, the boundary plasma study through the introduction of an electric field in the scrape-off layer (SOL) by the divertor biasing. Progress in the DIII-D experiments was obtained in the studies of divertor radiation, advanced tokamak and VH-mode plasma. As for the fusion technology research, activities are focused on the Research and Development (R and D) for ITER EDA: superconducting magnets, neutral beam heating, radio frequency heating, plasma facing components, reactor structure, remote maintenance, shielding blanket, tritium processing, tritium safety and fusion safety. Based on the Outline Design approved in March 1994 by the ITER Council a sensitivity study was conducted by the new director and JCT in close collaboration with four Home Teams in order to determine the optimum way to achieve a reduction in the cost of ITER while minimizing the impacts regarding its performance margins. Japanese Home Team carried out a part of the ITER design based on task agreements, mainly in the field of vacuum vessel, first wall and blanket, initial assembly, etc. The DREAM tokamak reactor concept was improved focusing on the reactor internals and safety. (J.P.N.).

Annual report of Naka Fusion Research Establishment from April 1, 1994 to March 31, 1995

International Nuclear Information System (INIS)

Nagashima, Takashi; Naito, Osamu; Ogiwara, Norio; Saigusa, Mikio; Seki, Masahiro; Murasawa, Michihiko; Uehara, Yusuke

1995-11-01

Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1994 to March 31, 1995. The main objectives of the JT-60 experiments are: confinement improvement, impurity control and divertor studies, steady-state studies, and energetic particle physics. JFT-2M experiments progressed in the momentum transport study by applying an external helical field and toroidal momentum input with NBI, and also, the boundary plasma study through the introduction of an electric field in the scrape-off layer (SOL) by the divertor biasing. Progress in the DIII-D experiments was obtained in the studies of divertor radiation, advanced tokamak and VH-mode plasma. As for the fusion technology research, activities are focused on the Research and Development (R and D) for ITER EDA: superconducting magnets, neutral beam heating, radio frequency heating, plasma facing components, reactor structure, remote maintenance, shielding blanket, tritium processing, tritium safety and fusion safety. Based on the Outline Design approved in March 1994 by the ITER Council a sensitivity study was conducted by the new director and JCT in close collaboration with four Home Teams in order to determine the optimum way to achieve a reduction in the cost of ITER while minimizing the impacts regarding its performance margins. Japanese Home Team carried out a part of the ITER design based on task agreements, mainly in the field of vacuum vessel, first wall and blanket, initial assembly, etc. The DREAM tokamak reactor concept was improved focusing on the reactor internals and safety. (J.P.N.)

LMFBR operational and experimental local-fault experience, primarily with oxide fuel elements

International Nuclear Information System (INIS)

Warinner, D.K.

1980-01-01

Case-by-case reviews of selective world experience with severe local faults, particularly fuel failure and fuel degradation, are reviewed for two sodium-cooled thermal reactors, several LMFBRs, and LMFBR-fuels experiments. The review summarizes fuel-failure frequency and illustrates the results of the most damaging LMFBR local-fault experiences of the last 20 years beginning with BR-5 and including DFR, BOR-60, BR2's MFBS- and Mol-loops experiments, Fermi, KNK, Rapsodie, EBR-II, and TREAT-D2. Local-fault accommodation is demonstrated and a need to more thoroughly investigate delayed-neutron and gaseous-fission-product signals is highlighted in view of uranate formation, observed blockages, and slow fuel-element failure-propagation

The Tokamak Fusion Core Experiment studies

International Nuclear Information System (INIS)

Schmidt, J.A.; Sheffield, G.V.; Bushnell, C.

1985-01-01

The basic objective of the next major step in the US fusion programme has been defined as the achievement of ignition and long pulse equilibrium burn of a fusion plasma in the Tokamak Fusion Core Experiment (TFCX) device. Preconceptual design studies have seen completion of four candidate versions to provide the comparative information needed to narrow down the range of TFCX options before proceeding to the conceptual design phase. All four designs share the same objective and conform to common physics, engineering and costing criteria. The four base options considered differed mainly in the toroidal field coil design, two employing superconducting coils and the other two copper coils. In each case (copper and superconducting), one relatively conventional version was carried as well as a version employing more exotic toroidal field coil design assumptions. Sizes range from R=2.6 m for the smaller of the two copper versions to R=4.08 m for the larger superconducting option. In all cases, the plasma current was about 10 MA and the toroidal field about 4 T. (author)

Magnet operating experience review for fusion applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1991-11-01

This report presents a review of magnet operating experiences for normal-conducting and superconducting magnets from fusion, particle accelerator, medical technology, and magnetohydrodynamics research areas. Safety relevant magnet operating experiences are presented to provide feedback on field performance of existing designs and to point out the operational safety concerns. Quantitative estimates of magnet component failure rates and accident event frequencies are also presented, based on field experience and on performance of similar components in other industries

Progress in heavy ion driven inertial fusion energy: From scaled experiments to the integrated research experiment

International Nuclear Information System (INIS)

Barnard, J.J.; Ahle, L.E.; Baca, D.; Bangerter, R.O.; Bieniosek, F.M.; Celata, C.M.; Chacon-Golcher, E.; Davidson, R.C.; Faltens, A.; Friedman, A.; Franks, R.M.; Grote, D.P.; Haber, I.; Henestroza, E.; Hoon, M.J.L. de; Kaganovich, I.; Karpenko, V.P.; Kishek, R.A.; Kwan, J.W.; Lee, E.P.; Logan, B.G.; Lund, S.M.; Meier, W.R.; Molvik, A.W.; Olson, C.; Prost, L.R.; Qin, H.; Rose, D.; Sabbi, G.-L.; Sangster, T.C.; Seidl, P.A.; Sharp, W.M.; Shuman, D.; Vay, J.-L.; Waldron, W.L.; Welch, D.; Yu, S.S.

2001-01-01

The promise of inertial fusion energy driven by heavy ion beams requires the development of accelerators that produce ion currents (∼100's Amperes/beam) and ion energies (∼1-10 GeV) that have not been achieved simultaneously in any existing accelerator. The high currents imply high generalized perveances, large tune depressions, and high space charge potentials of the beam center relative to the beam pipe. Many of the scientific issues associated with ion beams of high perveance and large tune depression have been addressed over the last two decades on scaled experiments at Lawrence Berkeley and Lawrence Livermore National Laboratories, the University of Maryland, and elsewhere. The additional requirement of high space charge potential (or equivalently high line charge density) gives rise to effects (particularly the role of electrons in beam transport) which must be understood before proceeding to a large scale accelerator. The first phase of a new series of experiments in Heavy Ion Fusion Virtual National Laboratory (HIF VNL), the High Current Experiments (HCX), is now being constructed at LBNL. The mission of the HCX will be to transport beams with driver line charge density so as to investigate the physics of this regime, including constraints on the maximum radial filling factor of the beam through the pipe. This factor is important for determining both cost and reliability of a driver scale accelerator. The HCX will provide data for design of the next steps in the sequence of experiments leading to an inertial fusion energy power plant. The focus of the program after the HCX will be on integration of all of the manipulations required for a driver. In the near term following HCX, an Integrated Beam Experiment (IBX) of the same general scale as the HCX is envisioned. The step which bridges the gap between the IBX and an engineering test facility for fusion has been designated the Integrated Research Experiment (IRE). The IRE (like the IBX) will provide an

Fusion-bonded fluidic interconnects

International Nuclear Information System (INIS)

Fazal, I; Elwenspoek, M C

2008-01-01

A new approach to realize fluidic interconnects based on the fusion bonding of glass tubes with silicon is presented. Fusion bond strength analyses have been carried out. Experiments with plain silicon wafers and coated with silicon oxide and silicon nitride are performed. The obtained results are discussed in terms of the homogeneity and strength of fusion bond. High pressure testing shows that the bond strength is large enough for most applications of fluidic interconnects. The bond strength for 525 µm thick silicon, with glass tubes having an outer diameter of 6 mm and with a wall thickness of 2 mm, is more than 60 bars after annealing at a temperature of 800 °C

Ventilation Systems Operating Experience Review for Fusion Applications

International Nuclear Information System (INIS)

Cadwallader, L.C.

1999-01-01

This report is a collection and review of system operation and failure experiences for air ventilation systems in nuclear facilities. These experiences are applicable for magnetic and inertial fusion facilities since air ventilation systems are support systems that can be considered generic to nuclear facilities. The report contains descriptions of ventilation system components, operating experiences with these systems, component failure rates, and component repair times. Since ventilation systems have a role in mitigating accident releases in nuclear facilities, these data are useful in safety analysis and risk assessment of public safety. An effort has also been given to identifying any safety issues with personnel operating or maintaining ventilation systems. Finally, the recommended failure data were compared to an independent data set to determine the accuracy of individual values. This comparison is useful for the International Energy Agency task on fusion component failure rate data collection

Diagnostics developments and applications for laser fusion experiments

International Nuclear Information System (INIS)

Coleman, L.W.

1977-01-01

Some diagnostics techniques applied to current laser fusion target experiments are reviewed. Specifically, holographic interferometry of target plasmas, coded aperture imaging of thermonuclear alpha-particles and neutron energy spectrum measurements are discussed

Progress of research and development of nuclear fusion and development of large nuclear fusion device technology

International Nuclear Information System (INIS)

1994-01-01

In the last several years, the results of tokamak experiments were conspicuous, and the progress of plasma confinement performance, transport mechanism, divertors and impurities, helium transport and exhaust, electric current drive, magnetic field ripple effect and high speed particle transport and DT experiment are reported. The other confinement methods than tokamak, the related theories and reactor technology are described. The conceptual design of ITER was carried out by the cooperation of Japan, USA, EC and the former USSR. The projects of developing nuclear fusion in various countries, the design and the required research and development of ITER, the reconstruction and the required research and development of JT-60, JET and TFTR, the design and the required research and development of large helical device, the state of research and development of laser nuclear fusion and inversion magnetic field pinch nuclear fusion, the activities and roles of industrial circles in large nuclear fusion device technology, and the long term perspective of the technical development of nuclear fusion are described. (K.I.)

High performance experiments in JT-60U reversed shear discharges

International Nuclear Information System (INIS)

Fujita, T.; Kamada, Y.; Ishida, S.

2001-01-01

The operation of JT-60U reversed shear discharges has been extended to a high plasma current, low-q regime keeping a large radius of the internal transport barrier (ITB) and the record value of equivalent fusion multiplication factor in JT-60U, Q DT eq =1.25, has been achieved at 2.6 MA. Operational schemes to reach the low-q regime with good reproducibility have been developed. The reduction of Z eff was obtained in the newly installed W-shaped pumped divertor. The beta limit in the low-q min regime, which limited the performance of L-mode edge discharges, has been improved in H-mode edge discharges with a broader pressure profile, which was obtained by power flow control with ITB degradation. Sustainment of ITB and improved confinement for 5.5 seconds has been demonstrated in an ELMy H reversed shear discharge. (author)

New approach to the reclamation of the old flotation tailings in Bor

Directory of Open Access Journals (Sweden)

Dožić Stevan

2010-01-01

Full Text Available The old flotation tailings of the Bor copper mine have not been reclaimed for several decades, although it is a serious threat to the environment, especially to some parts of the town. To date, there have been no efficacious attempts of solving the problem by indirect rehabilitation, only several cases of direct reclamation. This paper presents some results of the experiment established on a part of the tailings in the vicinity of the town, where various variants of meliorated and sterile substrates were applied in the biological reclamation with several tree and grass species. The analysis shows that, in the rehabilitation of sterile substrate of the copper mine, it is possible to grow several woody species. The best results were achieved by the species that were planted in the fertile soil layer on the sterile copper mine substrate, and on the mixture of soil and waste. Among the woody species, Robinia pseudoaccacia, Fraxinus excelsior and Acer pseudoplatanus showed the best survival percent, growth, and physiological vitality and the poorest were spruce and common oak.

Annual report of the Fusion Research and Development Center for the period of April 1, 1979 to March 31, 1980

International Nuclear Information System (INIS)

1981-03-01

Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1979 to March 1980 are described. In Plasma physics research two experiments both related to radio-frequency power injection into tokamak plasmas are to be noted. One is the demonstration of current drive by lower hybrid waves in JFT-2 and the other high efficiency ICRF heating at two-ion hybrid resonance in JFT-2a/DIVA. A multi-MW neutral beam injection system was installed and tested at JFT-2 with heating experiments expected to start shortly. JFT-2a/DIVA was shutdown to make space for the injector. A new ingredient in this area is the initiation of dee plasma experiments in Doublet III at San Diego, USA by JAERI team under US-Japan cooperation agreement. Progress was rapid achieving all experimental objective planned for this period. Construction of JT-60 is in progress as planned. A Mukoyama site where JT-60 and other new facilities will be located was procured in October 1979, which was followed by the construction starts of JT-60 buildings. The completion of JT-60 is expected in fall 1984. The progressive brief summaries are presented in following topics; development of neutral beam and radiofrequency heating system for JT-60, installation of the cluster testing facility with NbTi field coils, and design of tritium handling facility. (J.P.N.)

Fusion Technology 1996. Proceedings. Volume 1 and 2

International Nuclear Information System (INIS)

Varandas, C.; Serra, F.

1997-01-01

The objective of these proceedings was to provide a platform for the exchange of information on the design, construction and operation of fusion experiments. The technology which is being developed for the next step devices and fusion reactors was also covered. Sections in volume 1 concern (A) first wall, divertors and vacuum systems; (B) plasma heating and control; (C) plasma engineering and control; and (D) experimental systems. The sections in volume 2 deal with (E) magnet and related power supplies; (F) fuel cycle and tritium processing systems; (G) blanket technology/materials; (H) assembly, remote handling and waste management and storage; and (I) safety and environment, and reactor studies

Inertial fusion program, January 1-June 30, 1979

International Nuclear Information System (INIS)

Skoberne, F.

1981-06-01

Progress in the development of high-energy short-pulse carbon dioxide laser systems for fusion research is reported. Improvements are outlined for the Los Alamos National Laboratory's Gemini System, which permitted over 500 shots in support of 10 different target experiments; the transformation of our eight-beam system, Helios, from a developmental to an operational facility that is capable of irradiating targets on a routine basis is described; and progress made toward completion of Antares, our 100- to 200-TW target irradiation system, is detailed. Investigations of phenomena such as phase conjugation by degenerate four-wave mixing and its applicability to laser fusion systems, and frequency multiplexing as a means toward multipulse energy extraction are summarized. Also discussed are experiments with targets designed for adiabatic compression. Progress is reported in the development of accurate diagnostics, especially for the detection of expanding ions, of neutron yield, and of x-ray emission. Significant advances in our theoretical efforts are summarized, such as the adaptation of our target design codes for use with the CRAY-1 computer, and new results leading to a better understanding of implosion phenomena are reported. The results of various fusion reactor studies are summarized, including the development of an ICF reactor blanket that offers a promising alternative to the usual lithium blanket, and the formulation of a capital-cost data base for laser fusion reactors to permit meaningful comparisons with other technologies

Inertial fusion program, January 1-June 30, 1979

Energy Technology Data Exchange (ETDEWEB)

Skoberne, F. (comp.)

1981-06-01

Progress in the development of high-energy short-pulse carbon dioxide laser systems for fusion research is reported. Improvements are outlined for the Los Alamos National Laboratory's Gemini System, which permitted over 500 shots in support of 10 different target experiments; the transformation of our eight-beam system, Helios, from a developmental to an operational facility that is capable of irradiating targets on a routine basis is described; and progress made toward completion of Antares, our 100- to 200-TW target irradiation system, is detailed. Investigations of phenomena such as phase conjugation by degenerate four-wave mixing and its applicability to laser fusion systems, and frequency multiplexing as a means toward multipulse energy extraction are summarized. Also discussed are experiments with targets designed for adiabatic compression. Progress is reported in the development of accurate diagnostics, especially for the detection of expanding ions, of neutron yield, and of x-ray emission. Significant advances in our theoretical efforts are summarized, such as the adaptation of our target design codes for use with the CRAY-1 computer, and new results leading to a better understanding of implosion phenomena are reported. The results of various fusion reactor studies are summarized, including the development of an ICF reactor blanket that offers a promising alternative to the usual lithium blanket, and the formulation of a capital-cost data base for laser fusion reactors to permit meaningful comparisons with other technologies.

Trends in laser-plasma-instability experiments for laser fusion

International Nuclear Information System (INIS)

Drake, R.P.

1991-01-01

Laser-plasma instability experiments for laser fusion have followed three developments. These are advances in the technology and design of experiments, advances in diagnostics, and evolution of the design of high-gain targets. This paper traces the history of these three topics and discusses their present state. Today one is substantially able to produce controlled plasma conditions and to diagnose specific instabilities within such plasmas. Experiments today address issues that will matter for future laser facilities. Such facilities will irradiate targets with ∼1 MJ of visible or UV light pulses that are tens of nanoseconds in duration, very likely with a high degree of spatial and temporal incoherence. 58 refs., 4 figs

LMFBR operational and experimental in-core local-fault experience, primarily with oxide fuel elements

International Nuclear Information System (INIS)

Warinner, D.K.

Case-by-case reviews of selective world experience with severe local faults, particularly fuel failure and fuel degradation, are reviewed for two sodium-cooled thermal reactors, several LMFBRs, and LMFBR-fuels experiments. The review summarizes fuel-failure frequency and illustrates the results of the most damaging LMFBR local-fault experiences of the last 20 years beginning with BR-5 and including DFR, BOR-60, BR2's MFBS-and Mol-loops experiments, Fermi, KNK, Rapsodie, EBR-II, and TREAT-D2. Local-fault accommodation is demonstrated and a need to more thoroughly investigate delayed-neutron and gaseous-fission-product signals is highlighted in view of uranate formation, observed blockages, and slow fuel-element failure-propagation

Multi-criteria Analysis of Air Pollution with SO(2) and PM(10) in Urban Area Around the Copper Smelter in Bor, Serbia.

Science.gov (United States)

Nikolić, Djordje; Milošević, Novica; Mihajlović, Ivan; Zivković, Zivan; Tasić, Viša; Kovačević, Renata; Petrović, Nevenka

2010-02-01

This work presents the results of 4 years long monitoring of concentrations of SO(2) gas and PM(10) in the urban area around the copper smelter in Bor. The contents of heavy metals Pb, Cd, Cu, Ni, and As in PM(10) were determined and obtained values were compared to the limit values provided in EU Directives. Manifold excess concentrations of all the components in the atmosphere of the urban area of the townsite Bor were registered. Through application of a multi-criteria analysis by using PROMETHEE/GAIA method, the zones were ranked according to the level of pollution.

Welding for fusion grade neutral beam components - requirements, challenges, experiences and learnings

International Nuclear Information System (INIS)

Joshi, Jaydeep; Patel, Hitesh; Yadav, Ashish; Rotti, Chandramouli; Bandyopadhyay, Mainak; Chakraborty, Arun

2016-01-01

Negative ion based Neutral Beam Injectors (NBI) are the integral part of large size fusion devices where Neutral Beams of Hydrogen/Deuterium atoms are injected into the fusion reactor to heat the plasma, drive a plasma current, provide fuel to the plasma and also help to diagnose the plasma through spectroscopic measurements. The presentation shares the experiences of handling, some of special welding activities applicable for fusion prototypes developments, experiments, methodology developed for the inspection/tests, criteria considered with the appropriate justifications. This also shares the view point of authors code should further be supplement and incorporate the fusion specific applications considering future needs. In addition, explorations to meet our future needs of welding with specific attention to indigenous developments have been described

Heavy ion fusion experiments at LLNL

International Nuclear Information System (INIS)

Barnard, J.J.; Cable, M.D.; Callahan, D.A.

1996-01-01

We review the status of the experimental campaign being carried out at Lawrence Livermore National Laboratory, involving scaled investigations of the acceleration and transport of space-charge dominated heavy ion beams. The ultimate goal of these experiments is to help lay the groundwork for a larger scale ion driven inertial fusion reactor, the purpose of which is to produce inexpensive and clean electric power

Annual report of Naka Fusion Research Establishment from April 1, 1998 to March 31, 1999

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-09-01

This report provides an overview of research and development activities at the Naka Fusion Research Establishment, JAERI, during the period from April 1, 1998 to March 31, 1999. The activities in the Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M as well as DIII-D (US-Japan collaboration), and progress in ITER EDA, including ITER technology R and D. (J.P.N.)

FINESSE: study of the issues, experiments and facilities for fusion nuclear technology research and development. Interim report. Volume IV

International Nuclear Information System (INIS)

Abdou, M.

1984-10-01

This volume contains the following chapters (1) neutronics tests, (2) fluence considerations, (3) instrumentation and test matrix, (4) non-neutron test stands, (5) accelerator-based point neutron sources, (6) utilization of fission reactors, (7) tandem mirror test facilities, (8) tokamak fusion test facilities, (9) reliability development testing impacts on fusion reactor availability, and (10) fusion development scenarios. In addition, the following appendices are included: (1) evaluation of experience from fast breeder reactors, (2) observations of experts from the fission field, (3) evaluation of experience from the aerospace industry, (4) characterization of fusion nuclear systems operating environment, (5) modelling of MFTF-α+T high gamma mode performance, and (6) small-scale, multiple effects testing at US/DOE breeder reactor in-pile facilities

Fusion energy 1998. Proceedings. V. 1-4

International Nuclear Information System (INIS)

1999-01-01

The 17-th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology

Fusion energy 1998. Proceedings. V. 1-4

Energy Technology Data Exchange (ETDEWEB)

NONE

1999-12-01

The 17-th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology.

Prospect for inertial fusion energy

International Nuclear Information System (INIS)

Yamanaka, C.

1994-01-01

This paper presents recent inertial fusion experiments at Osaka. The inertial fusion energy reactor used for these experiments was designed according to some principles based on environmental, social and safety considerations. (TEC). 1 fig., 1 ref

Annual report of the Fusion Research and Development Center for the period of April 1, 1981 to March 31, 1982

International Nuclear Information System (INIS)

1982-11-01

Research and development activities of the Fusion Research and Development Center (Division of Thermonuclear Fusion Research and Division of Large Tokamak Development) from April 1981 to March 1982 are described. Emphasis in the JFT-2 and Doublet III Tokamak programs was placed on high-power heating experiments. JFT-2M, which is to replace JFT-2, is in fabrication and will be operational in early 1983. Construction of JT-60 progressed as planned with its completion targeted in March 1985. In fusion technology programs development of the prototype NBI unit and klystrons for JT-60 made satisfactory progress; particularly rewarding was the demonstration of full capability of the NBI prototype unit in March 1982. The Japanese coil for the IEA Large Coil Task was completed and passed the cooldown test in the domestic test facility. Activities in the design of the near-term FER and INTOR and the power reactor were continued. (author)

Advanced neutron diagnostics for ITER fusion experiments

International Nuclear Information System (INIS)

Kaellne, J.; Giacomelli, L.; Hjalmarsson, A.; Conroy, S.; Ericsson, G.; Johnson, M.G.; Glasser, W.; Henriksson, H.; Ronchi, E.; Sjoestrand, H.; Andersson, E.S.; Thun, J.; Weiszflog, M.; Gorini, G.; Tardocchi, M.; Popovichev, S.; Sousa, J.

2005-01-01

Results are presented from the neutron emission spectroscopy (NES) diagnosis of JET plasma performed with the MPR during the DTE1 campaign of 1997 and the recent TTE of 2003. The NES diagnostic capabilities at JET are presently being drastically enhanced by an upgrade of the MPR (MPRu) and a new 2.5-MeV TOF neutron spectrometer (TOFOR). The principles of MPRu and TOFOR are described and illustrated with the diagnostic role they will play in the high performance fusion experiments in the forward program of JET largely aimed at supporting ITER. The importance for the JET NES effort for ITER is discussed. (author)

Fusion virtual laboratory: The experiments' collaboration platform in Japan

Energy Technology Data Exchange (ETDEWEB)

Nakanishi, H., E-mail: nakanisi@nifs.ac.jp [National Institute for Fusion Science, Toki, Gifu 509-5292 (Japan); Kojima, M.; Takahashi, C.; Ohsuna, M.; Imazu, S.; Nonomura, M. [National Institute for Fusion Science, Toki, Gifu 509-5292 (Japan); Hasegawa, M. [RIAM, Kyushu University, Kasuga, Fukuoka 816-8560 (Japan); Yoshikawa, M. [PRC, University of Tsukuba, Tsukuba, Ibaraki 305-8577 (Japan); Nagayama, Y.; Kawahata, K. [National Institute for Fusion Science, Toki, Gifu 509-5292 (Japan)

2012-12-15

'Fusion virtual laboratory (FVL)' is the experiments' collaboration platform covering multiple fusion projects in Japan. Major Japanese fusion laboratories and universities are mutually connected through the dedicated virtual private network, named SNET, on SINET4. It has 3 different categories; (i) LHD remote participation, (ii) bilateral experiments' collaboration, and (iii) remote use of supercomputer. By extending the LABCOM data system developed at LHD, FVL supports (i) and (ii) so that it can deal with not only LHD data but also the data of two remote experiments: QUEST at Kyushu University and GAMMA10 at University of Tsukuba. FVL has applied the latest 'cloud' technology for both data acquisition and storage architecture. It can provide us high availability and performance scalability of the whole system. With a well optimized TCP data transferring method, the unified data access platform for both experimental data and numerical computation results could become realistic on FVL. The FVL project will continue demonstrating the ITER-era international collaboration schemes and the necessary technology.

Intercellular adhesion molecule-1 augments myoblast adhesion and fusion through homophilic trans-interactions.

Science.gov (United States)

Pizza, Francis X; Martin, Ryan A; Springer, Evan M; Leffler, Maxwell S; Woelmer, Bryce R; Recker, Isaac J; Leaman, Douglas W

2017-07-11

The overall objective of the study was to identify mechanisms through which intercellular adhesion molecule-1 (ICAM-1) augments the adhesive and fusogenic properties of myogenic cells. Hypotheses were tested using cultured myoblasts and fibroblasts, which do not constitutively express ICAM-1, and myoblasts and fibroblasts forced to express full length ICAM-1 or a truncated form lacking the cytoplasmic domain of ICAM-1. ICAM-1 mediated myoblast adhesion and fusion were quantified using novel assays and cell mixing experiments. We report that ICAM-1 augments myoblast adhesion to myoblasts and myotubes through homophilic trans-interactions. Such adhesive interactions enhanced levels of active Rac in adherent and fusing myoblasts, as well as triggered lamellipodia, spreading, and fusion of myoblasts through the signaling function of the cytoplasmic domain of ICAM-1. Rac inhibition negated ICAM-1 mediated lamellipodia, spreading, and fusion of myoblasts. The fusogenic property of ICAM-1-ICAM-1 interactions was restricted to myogenic cells, as forced expression of ICAM-1 by fibroblasts did not augment their fusion to ICAM-1+ myoblasts/myotubes. We conclude that ICAM-1 augments myoblast adhesion and fusion through its ability to self-associate and initiate Rac-mediated remodeling of the actin cytoskeleton.

The yeast cell fusion protein Prm1p requires covalent dimerization to promote membrane fusion.

Directory of Open Access Journals (Sweden)

Alex Engel

2010-05-01

Full Text Available Prm1p is a multipass membrane protein that promotes plasma membrane fusion during yeast mating. The mechanism by which Prm1p and other putative regulators of developmentally controlled cell-cell fusion events facilitate membrane fusion has remained largely elusive. Here, we report that Prm1p forms covalently linked homodimers. Covalent Prm1p dimer formation occurs via intermolecular disulfide bonds of two cysteines, Cys-120 and Cys-545. PRM1 mutants in which these cysteines have been substituted are fusion defective. These PRM1 mutants are normally expressed, retain homotypic interaction and can traffic to the fusion zone. Because prm1-C120S and prm1-C545S mutants can form covalent dimers when coexpressed with wild-type PRM1, an intermolecular C120-C545 disulfide linkage is inferred. Cys-120 is adjacent to a highly conserved hydrophobic domain. Mutation of a charged residue within this hydrophobic domain abrogates formation of covalent dimers, trafficking to the fusion zone, and fusion-promoting activity. The importance of intermolecular disulfide bonding informs models regarding the mechanism of Prm1-mediated cell-cell fusion.

Diagnostic technique for measuring fusion reaction rate for inertial confinement fusion experiments at Shen Guang-III prototype laser facility

International Nuclear Information System (INIS)

Wang Feng; Peng Xiao-Shi; Liu Shen-Ye; Xu Tao; Kang Dong-Guo

2013-01-01

A study is conducted using a two-dimensional simulation program (Lared-s) with the goal of developing a technique to evaluate the effect of Rayleigh-Taylor growth in a neutron fusion reaction region. Two peaks of fusion reaction rate are simulated by using a two-dimensional simulation program (Lared-s) and confirmed by the experimental results. A neutron temporal diagnostic (NTD) system is developed with a high temporal resolution of ∼ 30 ps at the Shen Guang-III (SG-III) prototype laser facility in China, to measure the fusion reaction rate history. With the shape of neutron reaction rate curve and the spherical harmonic function in this paper, the degree of Rayleigh-Taylor growth and the main source of the neutron yield in our experiment can be estimated qualitatively. This technique, including the diagnostic system and the simulation program, may provide important information for obtaining a higher neutron yield in implosion experiments of inertial confinement fusion

Development of target capsules for muon catalyzed fusion experiments

International Nuclear Information System (INIS)

Watts, K.D.; Jones, S.E.; Caffrey, A.J.

1983-01-01

A series of Muon Catalyzed Fusion experiments has been conducted at the Los Alamos Meson Physics Facility to determine how many fusion reactions one muon would catalyze under various temperature, pressure, contamination, and tritium concentration conditions. Target capsules to contain deuterium and tritium at elevated temperatures and pressures were engineered for a maximum temperature of 540 K (512 0 F) and a maximum pressure of 103 MPa (15,000 psig). Experimental data collected with these capsules indicated that the number of fusion reactions per muon continued to increase with temperature up to the 540-K design limit. Theory had indicated that the reaction rate should peak at approximately 540 K, but this was not confirmed during the experiments. A second generation of capsules which have a maximum design temperature of 800 K (980 0 F) and a maximum design pressure of 103 MPa (15,000 psig) has now been engineered. These new capsules will be used to further study the muon catalysis rate versus deuterium-tritium mixture temperature

Annual report of Naka Fusion Research Establishment from April 1, 2001 to March 31, 2002

Energy Technology Data Exchange (ETDEWEB)

Ando, Toshiro; Matsumoto, Hiroshi; Moriyama, Shinichi; Tanaka, Fumiya; Tuda, Takashi; Tsuji, Hiroshi (eds.) [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

2002-11-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, including those performed in collaboration with other research establishments of JAERI, during the period from April 1, 2001 to March 31, 2002. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, and completion of ITER Engineering Design Activities (EDA) in July 2001, including technology R and D. (J.P.N.)

Initial experiments with the FOM-Fusion-FEM

International Nuclear Information System (INIS)

Verhoeven, A.G.A.; Bongers, W.A.; Caplan, M.; Dijk, G. van; Elzendoorn, B.S.Q.

1995-01-01

A Free Electron Maser is being built for ECRH applications on future fusion research devices such as ITER. A unique feature of the Dutch FOM-Fusion-FEM is the possibility to tune the frequency over the entire range from 130 to 260 GHz while the output power exceeds 1 MW

Particle diagnostics for magnetic fusion experiments

International Nuclear Information System (INIS)

Post, D.E.

1983-01-01

This chapter summarizes the subset of diagnostics that relies primarily on the use of particles, and attempts to show how atomic and molecular data play a role in these diagnostics. Discusses passive charge-exchange ion temperature measurements; hydrogen beams for density, ion temperature, q and ZEFF measurements; impurity diagnostics using charge-exchange recombination; plasma electric and magnetic measurements using beams heavier than hydrogen; and alpha particle diagnostics. Points out that as fusion experiments become larger and hotter, most traditional particle diagnostics become difficult because large plasmas are difficult for neutral atoms to penetrate and the gyro-orbits of charged particles need to be larger than typically obtained with present beams to be comparable with the plasma size. Concludes that not only does the current profile affect the plasma stability, but there is a growing opinion that any serious fusion reactor will have to be steady state

Self-sustaining nuclear pumped laser-fusion reactor experiment

International Nuclear Information System (INIS)

Boody, F.P.; Choi, C.K.; Miley, G.H.

1977-01-01

The features of a neutron feedback nuclear pumped (NFNP) laser-fusion reactor equipment were studied with the intention of establishing the feasibility of the concept. The NFNP laser-fusion concept is compared schematically to electrically pumped laser fusion. The study showed that, once a method of energy storage has been demonstrated, a self-sustaining fusion-fission hybrid reactor with a ''blanket multiplication'' of two would be feasible using nuclear pumped Xe F* excimer lasers having efficiencies of 1 to 2 percent and D-D-T pellets with gains of 50 to 100

High current transport experiment for heavy ion inertial fusion

Directory of Open Access Journals (Sweden)

L. R. Prost

2005-02-01

Full Text Available The High Current Experiment at Lawrence Berkeley National Laboratory is part of the U.S. program to explore heavy-ion beam transport at a scale representative of the low-energy end of an induction linac driver for fusion energy production. The primary mission of this experiment is to investigate aperture fill factors acceptable for the transport of space-charge-dominated heavy-ion beams at high intensity (line charge density ∼0.2  μC/m over long pulse durations (4  μs in alternating gradient focusing lattices of electrostatic or magnetic quadrupoles. This experiment is testing transport issues resulting from nonlinear space-charge effects and collective modes, beam centroid alignment and steering, envelope matching, image charges and focusing field nonlinearities, halo, and electron and gas cloud effects. We present the results for a coasting 1 MeV K^{+} ion beam transported through ten electrostatic quadrupoles. The measurements cover two different fill factor studies (60% and 80% of the clear aperture radius for which the transverse phase space of the beam was characterized in detail, along with beam energy measurements and the first halo measurements. Electrostatic quadrupole transport at high beam fill factor (≈80% is achieved with acceptable emittance growth and beam loss, even though the initial beam distribution is not ideal (but the emittance is low nor in thermal equilibrium. We achieved good envelope control, and rematching may only be needed every ten lattice periods (at 80% fill factor in a longer lattice of similar design. We also show that understanding and controlling the time dependence of the envelope parameters is critical to achieving high fill factors, notably because of the injector and matching section dynamics.

Annual report of Naka Fusion Research Establishment. From April 1, 1996 to March 31, 1997

Energy Technology Data Exchange (ETDEWEB)

Shimizu, Masatsugu; Ide, Shunsuke; Matsukawa, Makoto; Kurihara, Ryoichi; Koizumi, Koichi; Takahashi, Ichiro [eds.] [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

1997-10-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 1996 to March 31, 1997. The activities in Naka Fusion Research Establishment are highlighted by high temperature plasma research in JT-60 and JFT-2M, and progress in ITER-EDA, including technology development. The objectives of the JT-60 project are to contribute to the ITER physics R and D and to establish the physics basis for a steady state tokamak fusion reactor like SSTR. Objectives of the JFT-2M program are (1) advanced and basic researches for the development of high-performance plasmas for nuclear fusion and (2) contribution to the physics R and D for ITER, with a merit of flexibility of a medium-size device. The Detailed Design Report (DDR) of ITER was issued by the Director in November 1996, as the basis of the Final Design Report (FDR). After the formal review by the Technical Advisory Committee (TAC), the DDR was officially accepted by the ITER Council at its 11th Meeting held in December 1996. The DDR is composed of various technical documents on the detailed design of plasma parameters, tokamak components, plant system and tokamak building. The major results of safety analyses described in the Non-site Specific Safety Report (NSSR)-1 was also included in the DDR. The FDR will be prepared by the end of 1997 for presentation at the ITER Council. (J.P.N.)

Demonstration of thermonuclear conditions in magnetized liner inertial fusion experiments

International Nuclear Information System (INIS)

Gomez, M. R.; Slutz, S. A.; Sefkow, A. B.; Hahn, K. D.; Hansen, S. B.; Knapp, P. F.; Schmit, P. F.; Ruiz, C. L.; Sinars, D. B.; Harding, E. C.; Jennings, C. A.; Awe, T. J.; Geissel, M.; Rovang, D. C.; Smith, I. C.; Chandler, G. A.; Cooper, G. W.; Cuneo, M. E.; Harvey-Thompson, A. J.; Hess, M. H.

2015-01-01

The magnetized liner inertial fusion concept [S. A. Slutz et al., Phys. Plasmas 17, 056303 (2010)] utilizes a magnetic field and laser heating to relax the pressure requirements of inertial confinement fusion. The first experiments to test the concept [M. R. Gomez et al., Phys. Rev. Lett. 113, 155003 (2014)] were conducted utilizing the 19 MA, 100 ns Z machine, the 2.5 kJ, 1 TW Z Beamlet laser, and the 10 T Applied B-field on Z system. Despite an estimated implosion velocity of only 70 km/s in these experiments, electron and ion temperatures at stagnation were as high as 3 keV, and thermonuclear deuterium-deuterium neutron yields up to 2 × 10 12 have been produced. X-ray emission from the fuel at stagnation had widths ranging from 50 to 110 μm over a roughly 80% of the axial extent of the target (6–8 mm) and lasted approximately 2 ns. X-ray yields from these experiments are consistent with a stagnation density of the hot fuel equal to 0.2–0.4 g/cm 3 . In these experiments, up to 5 × 10 10 secondary deuterium-tritium neutrons were produced. Given that the areal density of the plasma was approximately 1–2 mg/cm 2 , this indicates the stagnation plasma was significantly magnetized, which is consistent with the anisotropy observed in the deuterium-tritium neutron spectra. Control experiments where the laser and/or magnetic field were not utilized failed to produce stagnation temperatures greater than 1 keV and primary deuterium-deuterium yields greater than 10 10 . An additional control experiment where the fuel contained a sufficient dopant fraction to substantially increase radiative losses also failed to produce a relevant stagnation temperature. The results of these experiments are consistent with a thermonuclear neutron source

Paramyxovirus F1 protein has two fusion peptides: implications for the mechanism of membrane fusion.

Science.gov (United States)

Peisajovich, S G; Samuel, O; Shai, Y

2000-03-10

Viral fusion proteins contain a highly hydrophobic segment, named the fusion peptide, which is thought to be responsible for the merging of the cellular and viral membranes. Paramyxoviruses are believed to contain a single fusion peptide at the N terminus of the F1 protein. However, here we identified an additional internal segment in the Sendai virus F1 protein (amino acids 214-226) highly homologous to the fusion peptides of HIV-1 and RSV. A synthetic peptide, which includes this region, was found to induce membrane fusion of large unilamellar vesicles, at concentrations where the known N-terminal fusion peptide is not effective. A scrambled peptide as well as several peptides from other regions of the F1 protein, which strongly bind to membranes, are not fusogenic. The functional and structural characterization of this active segment suggest that the F1 protein has an additional internal fusion peptide that could participate in the actual fusion event. The presence of homologous regions in other members of the same family suggests that the concerted action of two fusion peptides, one N-terminal and the other internal, is a general feature of paramyxoviruses. Copyright 2000 Academic Press.

Experiments in order to reproduce cold fusion results

International Nuclear Information System (INIS)

Bimbot, R.; Blain, G.; Boureau, G.; Cieur, M.

1989-01-01

Three experiments have been performed in order to try and reproduce the cold fusion experiments reported by FLEISCHMANN and PONS (D 2 O electrolysis) and by the Frascati Group (D 2 absorption in Ti at liquid nitrogen temperature). In the two electrolysis experiments, a Pd cathode was used together with a Pt anode and a Pd (D 2 ) reference electrode, in acid and basic media. The electrolysis cell was surrounded by four neutron counters filled with an organic scintillator (NE213). The electronics made it possible to discriminate neutrons from gamma rays. The global efficiency for neutron detection was 20%, and the detection threshold was equal to 1 neutron/s/4π. A germanium detector (efficiency 70%) and a NaI crystal were used to record gamma ray spectra. In one of the experiments, tritium was measured in the solution before and after electrolysis. None of the two experiments showed neutron, gamma, or tritium production above background. In the third experiment, deuterium was absorbed in titanium by cooling at liquid nitrogen temperature, and desorbed by warming up at room temperature; both neutron and gamma emissions were recorded during these operations. The results of this experiment were also negative [fr

Technical requirement of experiments and facilities for fusion nuclear technology

International Nuclear Information System (INIS)

Abdou, M.; Tillak, M.; Gierszwski, P.; Grover, J.; Puigh, R.; Sze, D.K.; Berwald, D.

1986-06-01

The technical issues and requirements of experiments and facilities for fusion nuclear technology (FNT) have been investigated. The nuclear subsystems addressed are: a) blanket, b) radiation shield, c) tritium processing system, and d) plasma interactive components. Emphasis has been placed on the important and complex development problems of the blanket. A technical planning process for FNT has been developed and applied, including four major elements: 1) characterization of issues, 2) quantification of testing requirements, 3) evaluation of facilities, and 4) development of a test plan to identify the role, timing, characteristics and costs of major experiments and facilities

First wall thermomechanical stress analysis in a fusion ignition experiment

International Nuclear Information System (INIS)

Rodin, G.; Carrera, R.; Howell, J.; Hwang, Y.L.; Montalvo, E.; Ordonez, C.; Dong, J.Q.

1990-01-01

The fusion ignition experiment IGNITEX + has been proposed as a low cost means of producing and controlling fusion ignited plasmas for scientific study. A single-turn-coil tokamak plasmas for scientific study. A single-turn-coil tokamak cryogenically precooled at liquid nitrogen temperature is used to produce 20 T fields and 12 MA plasma currents so that high-density ohmic ignition is possible. The high-field, high-density operation should maintain the plasma relatively free of wall impurities. In order to minimize plasma cooling, a low-Z first wall is considered for IGNITEX. The IGNITEX design philosophy emphasizes simplicity and low cost. A limiterless, smooth first will without files and plates is proposed. A low-Z material is applied by plasma jet techniques over a resistive vacuum vessel. This design is thought to be adequate for a magnetic fusion ignition experiment. Maintenance and operation of the first wall system is significantly simplified when compared to conventional designs

SAR and LIDAR fusion: experiments and applications

Science.gov (United States)

Edwards, Matthew C.; Zaugg, Evan C.; Bradley, Joshua P.; Bowden, Ryan D.

2013-05-01

In recent years ARTEMIS, Inc. has developed a series of compact, versatile Synthetic Aperture Radar (SAR) systems which have been operated on a variety of small manned and unmanned aircraft. The multi-frequency-band SlimSAR has demonstrated a variety of capabilities including maritime and littoral target detection, ground moving target indication, polarimetry, interferometry, change detection, and foliage penetration. ARTEMIS also continues to build upon the radar's capabilities through fusion with other sensors, such as electro-optical and infrared camera gimbals and light detection and ranging (LIDAR) devices. In this paper we focus on experiments and applications employing SAR and LIDAR fusion. LIDAR is similar to radar in that it transmits a signal which, after being reflected or scattered by a target area, is recorded by the sensor. The differences are that a LIDAR uses a laser as a transmitter and optical sensors as a receiver, and the wavelengths used exhibit a very different scattering phenomenology than the microwaves used in radar, making SAR and LIDAR good complementary technologies. LIDAR is used in many applications including agriculture, archeology, geo-science, and surveying. Some typical data products include digital elevation maps of a target area and features and shapes extracted from the data. A set of experiments conducted to demonstrate the fusion of SAR and LIDAR data include a LIDAR DEM used in accurately processing the SAR data of a high relief area (mountainous, urban). Also, feature extraction is used in improving geolocation accuracy of the SAR and LIDAR data.

Monitoring the Effect of Internet Use on Students Behavior Case Study: Technical Faculty Bor, University of Belgrade

Science.gov (United States)

Niculovic, Milica; Zivkovic, Dragana; Manasijevic, Dragan; Strbac, Nada

2012-01-01

A large number of criteria for evaluating Internet addiction have been developed recently. The research of Internet addiction among students of the Technical faculty in Bor, University of Belgrade has been conducted and its results are presented in this paper. The study included 270 students using criteria of Young's Internet Addiction Test. In…

Japanese fusion research

International Nuclear Information System (INIS)

Uchida, T.

1987-01-01

The Japan experience during thirty years in nuclear fusion research is reported, after attending the 1st Geneva Conference in 1955, Osaka University, immedeately began linear pinch study using capacitor bank discharge. Subsequently to his trial several groups were organized to ward fusion R and D at universities in Tokyo, Nagoya, Kyoto, Sendai and son on. Based upon the recommendation of Japan Science Council, Institut of Plasma Physics (IPP) was established at Nagoya University in 1961 When the 1st International Conference on Plasma Physics and Controlled Nuclear Fusion Research was held in Saltzburg. The gloomy Bohm barrier had stood in front of many of experiments at that time. (author) [pt

Investigation of neutron emission in a cold fusion experiment in palladium

International Nuclear Information System (INIS)

Szustakowski, M.; Farny, J.; Muniak, M.; Nowak, A.; Parys, P.; Skrzeczanowski, W.; Socha, R.; Teter, J.; Wolski, J.; Wolowski, J.; Woryna, E.

1989-01-01

This paper reports on the experiments dealing with performance of nuclear fusion at room temperature actually which create a great sensation and are carried out in various laboratories. This interest arises from the results achieved by Fleischmann and Pons, and it results from their paper that there exists a possibility of obtaining an ignition owing to nuclear fusion reactions during usual electrochemical process--namely the electrolysis of D O with use of the system of Pd-Pt electrodes. From this reason the measurements of the yield and behavior of neutron emission give the information about processes of interest. At the IPPLM the cold fusion experiments have been conducted from the beginning of April 1989. In the first experiment the reliable evidence of neutron emission was obtained. A number of irregularly repeated neutron pulses of the level of 10 5 per pulse was recorded. The measurements of the neutron emission, in this experiment, were performed with the use of three independent methods employing the 2.5 MeV neutron spectrometer, the scintillation neutron detector as well as the nuclear track detector. neutron emission had been first recorded after 106 hours of the electrolysis process of D 2 O

Tritium depth profiling in carbon samples from fusion experiments

International Nuclear Information System (INIS)

Friedrich, M.; Pilz, W.; Sun, G.; Behrisch, R.; Garcia-Rosales, C.; Bekris, N.; Penzhorn, R.-D.

2000-01-01

Tritium depth profiling by accelerator mass spectrometry has been performed at the Rossendorf 3 MV Tandetron. Tritium particles are counted after the accelerator using a semiconductor detector, while deuterium and other light elements are simultaneously measured with the Faraday cup between the injection magnet and the accelerator. Depth profiles have been measured in carbon samples cut from the first wall tiles of the Garching fusion experiment ASDEX-Upgrade and of the European fusion experiment JET, Culham/UK. Tritium contents in the JET samples were up to six orders higher than in samples from ASDEX-Upgrade. Tritium beam currents from samples with high tritium content were measured partly in the Faraday cup before the accelerator. A dedicated tritium AMS facility with an air-insulated 100 kV tandem accelerator is under construction

Introduction of the EISA-PC into existing fusion experiments

International Nuclear Information System (INIS)

Tenten, W.; Bertschinger, G.; Mueller, K.D.; Reinhart, P.; Rongen, F.

1995-01-01

A general problem in the data acquisition field in fusion research is the lack of sufficient local memory for the storage of information acquired during a single discharge. While it is absolutely necessary to keep these data locally before transferring them to a central node, there has been a steadily increasing demand for more capacity. The introduction of an EISA-Personal-Computer with its vast and cheap memory resources is presenting a very interesting solution for the upgrade of existing installations and the design of new experiments. An innovative PC interface using Programmable Logic techniques was developed that allows easy and fast integration of a PC into an existing experimental setup. Several typical applications of this method are presented, that are of special interest for fusion experiments. (orig.)

Annual report of the Naka Fusion Research Establishment for the period of April 1, 1986 to March 31, 1987

International Nuclear Information System (INIS)

1988-03-01

Research and development activities of the Naka Fusion Research Establishment for the period of April 1986 to March 1987 are described. In JT-60 experiments, second phase experiments with Joule-heated plasma were performed in June and July 1986 and plasma discharge of n-barτ E = 3.1 x 10 -19 m -3 · sec with very low impurities was achieved in divertor configuration. Initial heating experiments in JT-60 were performed for August-November 1986 and January-March 1987. The highest central ion temperature in hydrogen discharge of 130 Million degrees, and plasma current drive by RF of 2 MA were achieved. The integrated performance tests of the NBI and RF heating systems of JT-60 were completed in July 1986, and the initial heating experiments were followed and finished in March 1987. The diagnostic system of JT-60 was successfully operated and produced large amount of valuable data. In Doublet III experiments, H-mode discharges with good confinement characteristics were achieved in divertor configurations. In JFT-2M non-circular plasma experiments remarkable results on H-mode discharge were achieved. As to studies on plasma-surface interaction, production of C 2 and C 3 compounds by chemical sputtering was confiremed and compared with the case of diamond-like surface. Data were accumurated for carbonization coating. A ceramic rotor driven by gas turbine was tested and successfully demonstrated continuous operation at 30,000 rpm in magnetic field. Development of 120 GHz Gyrotron was started focusing its objective to high power output. Experiments of IEA Large Coil Task were successfully carried out at ORNL. The demonstration poloidal coil program was progressed: Fablications of the coil and cryogenic system, and extention works of power supply from JT-60 proceeded. (author)

High Power Microwave Diagnostic for the Fusion Energy Experiment ITER

DEFF Research Database (Denmark)

Korsholm, Søren Bang; Leipold, Frank; Gonçalves, B.

2016-01-01

Microwave diagnostics will play an increasingly important role in burning plasma fusion energy experiments like ITER and beyond. The Collective Thomson Scattering (CTS) diagnostic to be installed at ITER is an example of such a diagnostic with great potential in present and future experiments...

National Fusion Collaboratory: Grid Computing for Simulations and Experiments

Science.gov (United States)

Greenwald, Martin

2004-05-01

The National Fusion Collaboratory Project is creating a computational grid designed to advance scientific understanding and innovation in magnetic fusion research by facilitating collaborations, enabling more effective integration of experiments, theory and modeling and allowing more efficient use of experimental facilities. The philosophy of FusionGrid is that data, codes, analysis routines, visualization tools, and communication tools should be thought of as network available services, easily used by the fusion scientist. In such an environment, access to services is stressed rather than portability. By building on a foundation of established computer science toolkits, deployment time can be minimized. These services all share the same basic infrastructure that allows for secure authentication and resource authorization which allows stakeholders to control their own resources such as computers, data and experiments. Code developers can control intellectual property, and fair use of shared resources can be demonstrated and controlled. A key goal is to shield scientific users from the implementation details such that transparency and ease-of-use are maximized. The first FusionGrid service deployed was the TRANSP code, a widely used tool for transport analysis. Tools for run preparation, submission, monitoring and management have been developed and shared among a wide user base. This approach saves user sites from the laborious effort of maintaining such a large and complex code while at the same time reducing the burden on the development team by avoiding the need to support a large number of heterogeneous installations. Shared visualization and A/V tools are being developed and deployed to enhance long-distance collaborations. These include desktop versions of the Access Grid, a highly capable multi-point remote conferencing tool and capabilities for sharing displays and analysis tools over local and wide-area networks.

Interpenetrated Uranyl-Organic Frameworks with bor and pts Topology: Structure, Spectroscopy, and Computation.

Science.gov (United States)

Liu, Chao; Chen, Fang-Yuan; Tian, Hong-Rui; Ai, Jing; Yang, Weiting; Pan, Qing-Jiang; Sun, Zhong-Ming

2017-11-20

Two novel three-dimensional interpenetrated uranyl-organic frameworks, (NH 4 ) 4 [(UO 2 ) 4 (L 1 ) 3 ]·6H 2 O (1) and [(UO 2 ) 2 (H 2 O) 2 L 2 ]·2H 2 O (2), where L 1 = tetrakis(3-carboxyphenyl)silicon and L 2 = tetrakis(4-carboxyphenyl)silicon, were synthesized by a combination of two isomeric tetrahedral silicon-centered ligands with 3-connected triangular [(UO 2 )(COO) 3 ] - and 4-connected dinuclear [(UO 2 ) 2 (COO) 4 ] units, respectively. Structural analyses indicate that 1 possesses a 2-fold interpenetrating anion bor network, while 2 exhibits a 3-fold interpenetrated 4,4-connected neutral network with pts topology. Both compounds were characterized by thermogravimetric analysis and IR, UV-vis, and photoluminescence spectroscopy. A relativistic density functional theory (DFT) investigation on 10 model compounds of 1 and 2 shows good agreement of the structural parameters, stretching vibrational frequencies, and absorption with experimental results; the time-dependent DFT calculations unravel that low-energy absorption bands originate from ligand-to-uranium charge transfer.

Implications of recent implantation-driven permeation experiments for fusion reactor safety

International Nuclear Information System (INIS)

Longhurst, G.R.; Anderl, R.A.; Struttmann, D.A.

1986-01-01

Metal structures exposed to the plasma in tritium-burning fusion reactors will be subject to implantation-driven permeation (IDP) of tritium. Permeation rates for IDP in fusion structural materials are usually high because the tritium atoms enter the material without having to go through the dissociation and solution steps required of tritium-bearing gas molecules. These surface processes, which may be rate limiting in PDP, actually enhance permeation in IDP by inhibiting the return of tritium to the plasma side of the structure. Experiments have been conducted at the Idaho National Engineering Laboratory (INEL) to investigate the nature of IDP by simulating conditions experienced by structures exposed to the plasma. These experiments have shown that surface conditions are important to tritium permeation in materials endothermic to hydrogen solution such as austenitic and ferritic steels. In reactive metals such as vanadium, surface processes appear to totally control the permeation. The purpose of this paper is to review the progress of those experiments and to discuss the implications that the results have regarding the tritium-related safety concerns of fusion reactors

Operation and Development on the Positive-Ion Based Neutral Beam Injection System for JT-60 and JT-60U

International Nuclear Information System (INIS)

Kuriyama, M.; Akino, N.; Ebisawa, N.; Honda, A.; Itoh, T.; Kawai, M.; Mogaki, K.; Ohga, T.; Oohara, H.; Umeda, N.; Usui, K.; Yamamoto, M.; Yamamoto, T.; Matsuoka, M.

2002-01-01

The positive-ion based neutral beam injection (NBI) system for JT-60, which consists of 14 beamline units and has a beam energy of 70 to 100 keV, started operation in 1986 with hydrogen beams and injected a neutral beam power of 27 MW at 75 keV into the JT-60 plasma. In 1991, the NBI system was modified to be able to handle deuterium beams as part of the JT-60 upgrade modification. After executing some research and developments, deuterium beams of 40 MW at 95 keV were injected in 1996. As a result, NBI has contributed to the achievement of the highest performance plasmas, a DT-equivalent fusion power gain of 1.25 and a fusion triple product of 1.55 x 10 21 keVs/m 3 , in the world on JT-60U

Characterization of leukemias with ETV6-ABL1 fusion

Science.gov (United States)

Zaliova, Marketa; Moorman, Anthony V.; Cazzaniga, Giovanni; Stanulla, Martin; Harvey, Richard C.; Roberts, Kathryn G.; Heatley, Sue L.; Loh, Mignon L.; Konopleva, Marina; Chen, I-Ming; Zimmermannova, Olga; Schwab, Claire; Smith, Owen; Mozziconacci, Marie-Joelle; Chabannon, Christian; Kim, Myungshin; Frederik Falkenburg, J. H.; Norton, Alice; Marshall, Karen; Haas, Oskar A.; Starkova, Julia; Stuchly, Jan; Hunger, Stephen P.; White, Deborah; Mullighan, Charles G.; Willman, Cheryl L.; Stary, Jan; Trka, Jan; Zuna, Jan

2016-01-01

To characterize the incidence, clinical features and genetics of ETV6-ABL1 leukemias, representing targetable kinase-activating lesions, we analyzed 44 new and published cases of ETV6-ABL1-positive hematologic malignancies [22 cases of acute lymphoblastic leukemia (13 children, 9 adults) and 22 myeloid malignancies (18 myeloproliferative neoplasms, 4 acute myeloid leukemias)]. The presence of the ETV6-ABL1 fusion was ascertained by cytogenetics, fluorescence in-situ hybridization, reverse transcriptase-polymerase chain reaction and RNA sequencing. Genomic and gene expression profiling was performed by single nucleotide polymorphism and expression arrays. Systematic screening of more than 4,500 cases revealed that in acute lymphoblastic leukemia ETV6-ABL1 is rare in childhood (0.17% cases) and slightly more common in adults (0.38%). There is no systematic screening of myeloproliferative neoplasms; however, the number of ETV6-ABL1-positive cases and the relative incidence of acute lymphoblastic leukemia and myeloproliferative neoplasms suggest that in adulthood ETV6-ABL1 is more common in BCR-ABL1-negative chronic myeloid leukemia-like myeloproliferations than in acute lymphoblastic leukemia. The genomic profile of ETV6-ABL1 acute lymphoblastic leukemia resembled that of BCR-ABL1 and BCR-ABL1-like cases with 80% of patients having concurrent CDKN2A/B and IKZF1 deletions. In the gene expression profiling all the ETV6-ABL1-positive samples clustered in close vicinity to BCR-ABL1 cases. All but one of the cases of ETV6-ABL1 acute lymphoblastic leukemia were classified as BCR-ABL1-like by a standardized assay. Over 60% of patients died, irrespectively of the disease or age subgroup examined. In conclusion, ETV6-ABL1 fusion occurs in both lymphoid and myeloid leukemias; the genomic profile and clinical behavior resemble BCR-ABL1-positive malignancies, including the unfavorable prognosis, particularly of acute leukemias. The poor outcome suggests that treatment with

Disassembly of JT-60 tokamak device and ancillary facilities for JT-60 tokamak

International Nuclear Information System (INIS)

Okano, Fuminori; Ichige, Hisashi; Miyo, Yasuhiko; Kaminaga, Atsushi; Sasajima, Tadayuki; Nishiyama, Tomokazu; Yagyu, Jun-ichi; Ishige, Youichi; Suzuki, Hiroaki; Komuro, Kenichi; Sakasai, Akira; Ikeda, Yoshitaka

2014-03-01

The disassembly of JT-60 tokamak device and its peripheral equipments, where the total weight was about 5400 tons, started in 2009 and accomplished in October 2012. This disassembly was required process for JT-60SA project, which is the Satellite Tokamak project under Japan-EU international corroboration to modify the JT-60 to the superconducting tokamak. This work was the first experience of disassembling a large radioactive fusion device based on Radiation Hazard Prevention Act in Japan. The cutting was one of the main problems in this disassembly, such as to cut the welded parts together with toroidal field coils, and to cut the vacuum vessel into two. After solving these problems, the disassembly completed without disaster and accident. This report presents the outline of the JT-60 disassembly, especially tokamak device and ancillary facilities for tokamak device. (author)

Controlled energy generation from nuclear fusion. 60th year atw

Energy Technology Data Exchange (ETDEWEB)

Weiss, Georg [Pintsch Bamag AG, Frankfurt am Main (Germany)

2015-02-15

Prospects increase, that with a controlled process of nuclear fusion one day an additional nuclear energy source will be commercially exploitable. In what follows, scientific principles according to the most recent research will be presented. Since approximately 30 years we are aware of the fact, that energy in form of light and heat provided by the sun and other fixed stars since over four billions years resulted from reactions of atomic nuclei. A series of such reactions became known which are considered for 'thermonuclear' processes, for example the carbon cycle by Bethe, where hydrogen is converted into helium. Most of the reflections and experiments dealt until 1938 with the reaction between nuclei of light elements. The possibility of splitting heavy nuclei was not anticipated. Its discovery by Hahn and Strassmann was a complete surprise - so to speak a rash reaction to release energy at the end of the element row. This 'way out' captured the interest of nuclear physicist for more than a decade. Only today, by starting to construct big nuclear power plants - only today, being able to assess the possibilities and limitations of this technology, the idea of energy generation through nuclear fusion steps into the foreground of nuclear research.

Fusion of {sup 60}Ni + {sup 100}Mo near and below the Coulomb barrier. Multi-phonon and transfer couplings down to the hindrance region

Energy Technology Data Exchange (ETDEWEB)

Stefanini, A.M.; Fioretto, E.; Corradi, L. [INFN, Laboratori Nazionali di Legnaro, Legnaro (Padova) (Italy); Montagnoli, G.; Scarlassara, F. [INFN, Sezione di Padova, Dipartimento di Fisica e Astronomia, Padova (Italy); Universita di Padova (Italy); Jiang, C.L.; Esbensen, H.; Back, B.B.; Di Giovine, B.; Greene, J.P.; Henderson, H.D.; Rehm, K.E.; Sewerinyak, D.; Zhu, S. [Argonne National Laboratory, Physics Division, Argonne, IL (United States); Deibel, C.M. [Argonne National Laboratory, Physics Division, Argonne, IL (United States); Louisiana State University, Department of Physics and Astronomy, Baton Rouge, LA (United States); Marley, S.T. [Argonne National Laboratory, Physics Division, Argonne, IL (United States); University of Notre Dame, Notre Dame, IN (United States); Notani, M. [University of Notre Dame, Notre Dame, IN (United States); Fermi National Accelerator Laboratory, Batavia, IL (United States); Patel, N. [Argonne National Laboratory, Physics Division, Argonne, IL (United States); Lawrence Livermore National Laboratory, Livemore, CA (United States); Tang, X.D. [University of Notre Dame, Notre Dame, IN (United States); Ugalde, C. [Argonne National Laboratory, Physics Division, Argonne, IL (United States); University of Chicago, Chicago, IL (United States)

2013-05-15

The fusion excitation function of {sup 60}Ni + {sup 100}Mo has been measured from above the Coulomb barrier down to a cross section around 2 {mu}b, looking for coupling and hindrance effects in this soft medium-mass system with positive Q-values for several neutron transfer channels. A comparison is made with previous results for {sup 64}Ni + {sup 100}Mo where no Q > 0 transfer channels exist and the hindrance effect is quite clear. The two excitation functions are very similar, as well as the corresponding logarithmic derivatives showing analogous saturations below the barrier. It appears that transfer couplings to Q > 0 channels seem to play a marginal role near and below the barrier for {sup 60}Ni + {sup 100}Mo, even if measurements of cross sections lower than 1 {mu}b would be needed also for this system. Coupled-channels calculations confirm these observations and indicate that multi-phonon excitations dominate the fusion dynamics in the whole measured energy range. (orig.)

The materials irradiation experiment for testing plasma facing materials at fusion relevant conditions

Energy Technology Data Exchange (ETDEWEB)

Garrison, L. M., E-mail: garrisonlm@ornl.gov; Egle, B. J. [Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, Tennessee 37831 (United States); Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States); Zenobia, S. J.; Kulcinski, G. L.; Santarius, J. F. [Fusion Technology Institute, University of Wisconsin-Madison, 1500 Engineering Drive, Madison, Wisconsin 53706 (United States)

2016-08-15

The Materials Irradiation Experiment (MITE-E) was constructed at the University of Wisconsin-Madison Inertial Electrostatic Confinement Laboratory to test materials for potential use as plasma-facing materials (PFMs) in fusion reactors. PFMs in fusion reactors will be bombarded with x-rays, neutrons, and ions of hydrogen and helium. More needs to be understood about the interactions between the plasma and the materials to validate their use for fusion reactors. The MITE-E simulates some of the fusion reactor conditions by holding samples at temperatures up to 1000 °C while irradiating them with helium or deuterium ions with energies from 10 to 150 keV. The ion gun can irradiate the samples with ion currents of 20 μA–500 μA; the typical current used is 72 μA, which is an average flux of 9 × 10{sup 14} ions/(cm{sup 2} s). The ion gun uses electrostatic lenses to extract and shape the ion beam. A variable power (1-20 W), steady-state, Nd:YAG laser provides additional heating to maintain a constant sample temperature during irradiations. The ion beam current reaching the sample is directly measured and monitored in real-time during irradiations. The ion beam profile has been investigated using a copper sample sputtering experiment. The MITE-E has successfully been used to irradiate polycrystalline and single crystal tungsten samples with helium ions and will continue to be a source of important data for plasma interactions with materials.

Operating procedures: Fusion Experiments Analysis Facility

Energy Technology Data Exchange (ETDEWEB)

Lerche, R.A.; Carey, R.W.

1984-03-20

The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility.

Operating procedures: Fusion Experiments Analysis Facility

International Nuclear Information System (INIS)

Lerche, R.A.; Carey, R.W.

1984-01-01

The Fusion Experiments Analysis Facility (FEAF) is a computer facility based on a DEC VAX 11/780 computer. It became operational in late 1982. At that time two manuals were written to aid users and staff in their interactions with the facility. This manual is designed as a reference to assist the FEAF staff in carrying out their responsibilities. It is meant to supplement equipment and software manuals supplied by the vendors. Also this manual provides the FEAF staff with a set of consistent, written guidelines for the daily operation of the facility

Identification of a novel EYA1 splice-site mutation in a Danish branchio-oto-renal syndrome family

DEFF Research Database (Denmark)

Henriksen, Ann Marie; Tümer, Zeynep; Tommerup, Niels

2004-01-01

Branchio-oto-renal (BOR) syndrome is an autosomal dominant disorder characterized by variable clinical manifestations including branchial fistulae, preauricular pits, ear malformations, hearing impairment, and renal anomalies. BOR is caused by mutations in the genes EYA1 and SIX1. A Danish BOR...

STUDI KONEKTIVITAS AKUIFER ANTARA SUMUR BOR DENGAN SUMBER DAYA AIR DI BAWAHNYA (Study on Aquifer Connectivity, between Boreholes with water resources underneath

Directory of Open Access Journals (Sweden)

Agus Budhie Wijatna

2013-11-01

Full Text Available ABSTRAK Untuk memenuhi kebutuhan air bersih bagi penduduk di daerah bekas bencana letusan Gunung Merapi, Kabupaten Sleman, DIY, telah dibuat 5 sumur bor di Dusun Srunen (BH1, Pagerjurang (BH2, Ngepring (BH3, Kuweron (BH4, dan di Dusun Bubur (BH5. Pembuatan sumur bor pada elevasi antara 544 sampai 846 m.dpl, dengan kedalaman antara 98-146 m dan debit pengambilan airtanah rerata 9-10 liter per detik tersebut dikawatirkan akan mempengaruhi kondisi muka airtanah sumur gali di Dusun Pendowoharjo (W7, Ngaglik (W8, Gebang (W9, Condong Catur (W10, sumur UGM (W11 dan mempengaruhi debit umbul (mataair Ngepas (S8, Umbul Jogopaten (S9, Umbul Pajangan (S10, Umbul Londo (S11, Umbul Permai (S12, dan Umbul Seturan (S13, yang berada pada elevasi 148-329 m.dpl. Secara teoritis, pengambilan airtanah di sumur bor akan berpengaruh jika terdapat interkoneksi hidraulik antara sumur bor dengan sumur gali dan mataair. Pada penelitian ini, interkoneksi hidraulik antara sumur bor dengan sumur gali dan mataair dilakukan menggunakan isotop lingkungan (D, 3H dan 18O. Penelitian diawali dengan menentukan lokasi pengambilan sampel airtanah berdasarkan peta topografi dan kondisi hidrologi; sampel airtanah diambil dari sumur bor, sumur gali dan mataair sebanyak 30 ml dan 1.000 ml; rasio isotop δD dan δ18O pada sampel airtanah diukur dengan liquid-water stable isotope analyzer LGR DLT-100, sedangkan kadar tritium diukur dengan Liquid Scientillation Counter (LSC Tri Carb 1900 TR. Genesis sampel airtanah ditentukan berdasarkan komposisi isotop (δ18O, δD dengan mengacu pada persamaan Merapi Meteoric Water Line (MMWL; sedangkan untuk memastikan adanya interkoneksi hidraulik, maka hasil pengukuran kadar tritium dianalisis dengan tritium dating method. Hasil penelitian menunjukkan bahwa genesis airtanah di BH1, BH2, BH3, dan BH4 berbeda dengan genesis airtanah sumur gali dan mataair di bawahnya. Sehingga dapat disimpulkan airtanah sumur bor di BH1, BH2, BH3, dan BH4 tidak memiliki

Development and verification of remote research environment based on 'Fusion research grid'

International Nuclear Information System (INIS)

Iba, Katsuyuki; Ozeki, Takahisa; Totsuka, Toshiyuki; Suzuki, Yoshio; Oshima, Takayuki; Sakata, Shinya; Sato, Minoru; Suzuki, Mitsuhiro; Hamamatsu, Kiyotaka; Kiyono, Kimihiro

2008-01-01

'Fusion research grid' is a concept that unites scientists and let them collaborate effectively against their difference in time zone and location in a nuclear fusion research. Fundamental technologies of 'Fusion research grid' have been developed at JAEA in the VizGrid project under the e-Japan project at the Ministry of Education, Culture, Sports, Science and Technology (MEXT). We are conscious of needs to create new systems that assist researchers with their research activities because remote collaborations have been increasing in international projects. Therefore we have developed prototype remote research environments for experiments, diagnostics, analyses and communications based on 'Fusion research grid'. All users can access these environments from anywhere because 'Fusion research grid' does not require a closed network like Super SINET to maintain security. The prototype systems were verified in experiments at JT-60U and their availability was confirmed

Fusion-Fission process and gamma spectroscopy of binary products in light heavy ion collisions (40 {<=} A{sub CN} {<=} 60); Processus de fusion-fission et spectroscopie gamma des produits binaires dans les collisions entre ions lourds legers (40 {<=} A{sub NC} {<=} 60)

Energy Technology Data Exchange (ETDEWEB)

Nouicer, Rachid [Institut de Recherche Subatomique, CNRS-IN2P3 - Universite Louis Pasteur, 67 - Strasbourg (France)

1997-11-21

During the work on which this Thesis is based, the significant role of the Fusion-Fission Asymmetric mechanism in light heavy ion collisions (A{sub NC} {<=} 60) has been emphasized. The Spin Dis-alignment in the oblate-oblate system has supplied evidence for the first time for the Butterfly mode in a resonant-like reaction. These two aspects, one macroscopic and the other more closely related to microscopic effects are certainly different from a conceptual point of view but are quite complementary for a global understanding of dinuclear systems. In the first part, inclusive and exclusive measurements of the {sup 35}Cl + {sup 12}C and {sup 35}Cl + {sup 24}Mg reaction have been performed at 8 MeV/nucleon in the Saclay experiment. These measurements have permitted us to verify the origin of products which have given rise of the asymmetric fusion-fission mechanism and which have demonstrated that the three-body process in this energy range is very weak. In the second part the {sup 28}Si + {sup 28}Si reaction has been performed at the resonance energy E{sub lab}> = 111.6 MeV at Strasbourg with the Eurogam phase II multi-detector array and VIVITRON accelerator. An angular momentum J{sup {pi}} 38{sup +} for inelastic and mutual channels of the {sup 28}Si + {sup 28}Si exit channel has been measured and has supplied evidence for a spin dis-alignment which has been interpreted in the framework of a molecular model by Butterfly motion. The spectroscopic study of {sup 32}S nucleus, has revealed the occurrence of a new {gamma}-ray transition 0{sup +}(8507.8 keV) {yields} 2{sub 1}{sup +}(2230.2 keV). (author) 105 refs., 116 figs., 26 tabs.

Measurement of solar proton-proton fusion neutrinos with a Soviet-American gallium experiment: Technical progress report

International Nuclear Information System (INIS)

Cherry, M.L.

1989-06-01

A gallium solar neutrino detector is sensitive to low-energy proton-proton fusion neutrinos. A flux of 70 SNU is expected in a gallium detector from the p-p reaction independent of solar model calculations. If, however, neutrino oscillations in the solar interior are responsible for the suppressed 8 B flux measured by the Homestake 37 Cl experiment, then a comparison of the gallium and chlorine results may make possible a determination of the neutrino mass difference and mixing angle. A 60-ton gallium detector is currently being constructed in the Baksan Laboratory in the Soviet Union, and should be taking data by the end of 1989

Cooperative Russian-French experiment on plutonium-enriched fuels for fast burner reactor

International Nuclear Information System (INIS)

Zabud'ko, L.M.; Kurina, I.A.; Men'shikova, T.S.; Rogozkin, B.D.; Maershin, A.A.; Langi, A.; Pillon, S.

2001-01-01

Various kinds of nuclear fuels with an increased plutonium content are under study according to the program including three stages: fabrication, irradiation in BOR-60 reactor, post-irradiation examination. Flowsheets for fabricating pelletized and vibrocompacted fuels of UPu 0.45 O 2 , UPu 0.45 N, UPu 0.6 N, PuN + ZrN, PuO 2 + MgO are presented along with basic fuel properties. The irradiation of oxide fuel is carried out in an individual irradiation device at rated maximum temperature of the fuel at the beginning of irradiation equal to 2100 deg C. The irradiation of nitride fuel and the fuel based on inert matrices is performed in the other device with the aim of limitation of maximum temperature by the value of 1550 deg C. The duration of irradiation for all fuel types constitutes 750 EFPD. Fuel element charge in Bor-60 reactor core was realized in 2000 [ru

Progress in direct-drive inertial confinement fusion research at the Laboratory for Laser Energetics

International Nuclear Information System (INIS)

McCrory, R.L.

2002-01-01

Significant theoretical and experimental progress towards the validation of direct-drive inertial confinement fusion (ICF) has been recently made at the Laboratory for Laser Energetics (LLE). Direct-drive ICF offers the potential for high-gain implosions and is a leading candidate for an inertial fusion energy power plant. LLE's base-line direct-drive ignition design for NIF is an 'all-DT' design that has a 1-D gain of ∼45. Recent calculations show that targets composed of foam shells, wicked with DT, can potentially achieve 1-D gains of ∼100. LLE experiments are conducted on the OMEGA 60-beam, 30-kJ, UV laser system. Beam smoothing of OMEGA includes 1-THz, 2-D SSD and polarization smoothing. Cryogenic D2 and plastic shell (warm) spherical targets and a comprehensive suite of x-ray, nuclear, charged particle and optical diagnostics are used in these experiments. Future experiments will use cryogenic DT targets. (author)

Tokamak fusion test reactor FELIX plate experiment

International Nuclear Information System (INIS)

Hua, T.O.; Nygren, R.E.; Turner, L.R.

1986-01-01

For a conducting material exposed to both a time-varying and a static magnetic field, such as a limiter blade in a tokamak, the induced eddy currents and the deflection arising from those eddy currents can be strongly coupled. The coupling effects reduce the currents and deflections markedly, sometimes an order of magnitude, from the values predicted if coupling is neglected. A series of experiments to study current-deflection coupling were performed using the Fusion Electromagnetic Inductance Experiment (FELIX) facility at Argonne National Laboratory. Magnetic damping and magnetic stiffness resulting from the coupling are discussed, and analytical expressions for induced eddy current and rigid body rotation in the FELIX plate experiment are compared with the experimental results. Predictions for the degree of coupling based on various parameters are made using the analytical model

Design and characterization of a neutralized-transport experiment for heavy-ion fusion

Directory of Open Access Journals (Sweden)

Enrique Henestroza

2004-08-01

Full Text Available In heavy-ion inertial-confinement fusion systems, intense beams of ions must be transported from the exit of the final-focus magnet system through the fusion chamber to hit spots on the target with radii of about 2 mm. For the heavy-ion-fusion power-plant scenarios presently favored in the U.S., a substantial fraction of the ion-beam space charge must be neutralized during this final transport. The most effective neutralization technique found in numerical simulations is to pass each beam through a low-density plasma after the final focusing. To provide quantitative comparisons of these theoretical predictions with experiment, the Virtual National Laboratory for Heavy Ion Fusion has completed the construction and has begun experimentation with the neutralized-transport experiment. The experiment consists of three main sections, each with its own physics issues. The injector is designed to generate a very high-brightness, space-charge-dominated potassium beam, while still allowing variable perveance by a beam aperturing technique. The magnetic-focusing section, consisting of four pulsed quadrupoles, permits the study of magnet tuning, as well as the effects of phase-space dilution due to higher-order nonlinear fields. In the final section, the converging ion beam exiting the magnetic section is transported through a drift region with plasma sources for beam neutralization, and the final spot size is measured under various conditions of neutralization. In this paper, we discuss the design and characterization of the three sections in detail and present initial results from the experiment.

Women's experiences of daily life after anterior cervical decompression and fusion surgery: A qualitative interview study.

Science.gov (United States)

Hermansen, Anna; Peolsson, Anneli; Kammerlind, Ann-Sofi; Hjelm, Katarina

2016-04-01

To explore and describe women's experiences of daily life after anterior cervical decompression and fusion surgery. Qualitative explorative design. Fourteen women aged 39-62 years (median 52 years) were included 1.5-3 years after anterior cervical decompression and fusion for cervical disc disease. Individual semi-structured interviews were analysed by qualitative content analysis with an inductive approach. The women described their experiences of daily life in 5 different ways: being recovered to various extents; impact of remaining symptoms on thoughts and feelings; making daily life work; receiving support from social and occupational networks; and physical and behavioural changes due to interventions and encounters with healthcare professionals. This interview study provides insight into women's daily life after anterior cervical decompression and fusion. Whilst the subjects improved after surgery, they also experienced remaining symptoms and limitations in daily life. A variety of mostly active coping strategies were used to manage daily life. Social support from family, friends, occupational networks and healthcare professionals positively influenced daily life. These findings provide knowledge about aspects of daily life that should be considered in individualized postoperative care and rehabilitation in an attempt to provide better outcomes in women after anterior cervical decompression and fusion.

High pressure deuterium-tritium gas target vessels for muon-catalyzed fusion experiments

International Nuclear Information System (INIS)

Caffrey, A.J.; Spaletta, H.W.; Ware, A.G.; Zabriskie, J.M.; Hardwick, D.A.; Maltrud, H.R.; Paciotti, M.A.

1989-01-01

In experimental studies of muon-catalyzed fusion, the density of the hydrogen gas mixture is an important parameter. Catalysis of up to 150 fusions per muon has been observed in deuterium-tritium gas mixtures at liquid hydrogen density; at room temperature, such densities require a target gas pressure of the order of 1000 atmospheres (100 MPa, 15,000 psi). We report here the design considerations for hydrogen gas target vessels for muon-catalyzed fusion experiments that operate at 1000 and 10,000 atmospheres. The 1000 atmosphere high pressure target vessels are fabricated of Type A-286 stainless steel and lined with oxygen-free, high-conductivity (OFHC) copper to provide a barrier to hydrogen permeation of the stainless steel. The 10,000 atmosphere ultrahigh pressure target vessels are made from 18Ni (200 grade) maraging steel and are lined with OFHC copper, again to prevent hydrogen permeation of the steel. In addition to target design features, operating requirements, fabrication procedures, and secondary containment are discussed. 13 refs., 3 figs., 1 tab

Modeling and experiments on tritium permeation in fusion reactor blankets

Science.gov (United States)

Holland, D. F.; Longhurst, G. R.

The determination of tritium loss from helium-cooled fusion breeding blankets are discussed. The issues are: (1) applicability of present models to permeation at low tritium pressures; (2) effectiveness of oxide layers in reducing permeation; (3) effectiveness of hydrogen addition as a means to lower tritium permeation; and (4) effectiveness of conversion to tritiated water and subsequent trapping to reduce permeation. Theoretical models applicable to these issues are discussed, and results of experiments in two areas are presented; permeation of mixtures of hydrogen isotopes and conversion to tritiated water.

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

Directory of Open Access Journals (Sweden)

Angelone M.

2017-01-01

Full Text Available A neutronics benchmark experiment on a pure Copper block (dimensions 60 × 70 × 70 cm3 aimed at testing and validating the recent nuclear data libraries for fusion applications was performed in the frame of the European Fusion Program at the 14 MeV ENEA Frascati Neutron Generator (FNG. Reaction rates, neutron flux spectra and doses were measured using different experimental techniques (e.g. activation foils techniques, NE213 scintillator and thermoluminescent detectors. This paper first summarizes the analyses of the experiment carried-out using the MCNP5 Monte Carlo code and the European JEFF-3.2 library. Large discrepancies between calculation (C and experiment (E were found for the reaction rates both in the high and low neutron energy range. The analysis was complemented by sensitivity/uncertainty analyses (S/U using the deterministic and Monte Carlo SUSD3D and MCSEN codes, respectively. The S/U analyses enabled to identify the cross sections and energy ranges which are mostly affecting the calculated responses. The largest discrepancy among the C/E values was observed for the thermal (capture reactions indicating severe deficiencies in the 63,65Cu capture and elastic cross sections at lower rather than at high energy. Deterministic and MC codes produced similar results. The 14 MeV copper experiment and its analysis thus calls for a revision of the JEFF-3.2 copper cross section and covariance data evaluation. A new analysis of the experiment was performed with the MCNP5 code using the revised JEFF-3.3-T2 library released by NEA and a new, not yet distributed, revised JEFF-3.2 Cu evaluation produced by KIT. A noticeable improvement of the C/E results was obtained with both new libraries.

Copper benchmark experiment for the testing of JEFF-3.2 nuclear data for fusion applications

Science.gov (United States)

Angelone, M.; Flammini, D.; Loreti, S.; Moro, F.; Pillon, M.; Villar, R.; Klix, A.; Fischer, U.; Kodeli, I.; Perel, R. L.; Pohorecky, W.

2017-09-01

A neutronics benchmark experiment on a pure Copper block (dimensions 60 × 70 × 70 cm3) aimed at testing and validating the recent nuclear data libraries for fusion applications was performed in the frame of the European Fusion Program at the 14 MeV ENEA Frascati Neutron Generator (FNG). Reaction rates, neutron flux spectra and doses were measured using different experimental techniques (e.g. activation foils techniques, NE213 scintillator and thermoluminescent detectors). This paper first summarizes the analyses of the experiment carried-out using the MCNP5 Monte Carlo code and the European JEFF-3.2 library. Large discrepancies between calculation (C) and experiment (E) were found for the reaction rates both in the high and low neutron energy range. The analysis was complemented by sensitivity/uncertainty analyses (S/U) using the deterministic and Monte Carlo SUSD3D and MCSEN codes, respectively. The S/U analyses enabled to identify the cross sections and energy ranges which are mostly affecting the calculated responses. The largest discrepancy among the C/E values was observed for the thermal (capture) reactions indicating severe deficiencies in the 63,65Cu capture and elastic cross sections at lower rather than at high energy. Deterministic and MC codes produced similar results. The 14 MeV copper experiment and its analysis thus calls for a revision of the JEFF-3.2 copper cross section and covariance data evaluation. A new analysis of the experiment was performed with the MCNP5 code using the revised JEFF-3.3-T2 library released by NEA and a new, not yet distributed, revised JEFF-3.2 Cu evaluation produced by KIT. A noticeable improvement of the C/E results was obtained with both new libraries.

EDITORIAL: Special issue: overview reports from the Fusion Energy Conference (FEC) (Daejeon, South Korea, 2010) Special issue: overview reports from the Fusion Energy Conference (FEC) (Daejeon, South Korea, 2010)

Science.gov (United States)

Thomas, Paul

2011-09-01

The group of 27 papers published in this special issue of Nuclear Fusion aims to monitor the worldwide progress made in the period 2008-2010 in the field of thermonuclear fusion. Of these papers, 22 are based on overview reports presented at the 23rd Fusion Energy Conference (FEC 2010) and five are summary reports. The conference was hosted by the Republic of Korea and organized by the IAEA in cooperation with the National Fusion Research Institute and the Daejeon Metropolitan City. It took place in Daejeon on 11-16 October 2010. The overviews presented at the conference have been rewritten and extended for the purpose of this special issue and submitted to the standard double-referee peer-review of Nuclear Fusion. The articles are placed in the following sequence: Conference summaries of the sessions devoted to: Tokamak and stellarator experiments, experimental divertor physics and plasma wall interaction experiments, stability experiments and waves and fast particles; ITER activities, fusion technology, safety and economics; Magnetic confinement theory and modelling; Inertial confinement fusion; Innovative confinement concepts, operational scenarios and confinement. Overview articles, presented in programme order, are as follows: Tokamaks Overview of KSTAR initial experiments; Recent progress in RF heating and long-pulse experiments on EAST; Overview of JET results; DIII-D contributions toward the scientific basis for sustained burning plasmas; Overview of JT-60U results toward the resolution of key physics and engineering issues in ITER and JT-60SA; Overview of physics results from NSTX; Overview of ASDEX Upgrade results; Overview of physics results from MAST; Contribution of Tore Supra in preparation of ITER; Overview of FTU results; Overview of experimental results on the HL-2A tokamak; Progress and scientific results in the TCV tokamak; Overview of the JT-60SA project; Recent results of the T-10 tokamak; The reconstruction and research progress of the TEXT

Development of a Cost-Effective Design for the Fusion Ignition Research Experiment

International Nuclear Information System (INIS)

Philip J. Heitzenroeder

1999-01-01

The Fusion Ignition Research Experiment (FIRE) is one of the components of a US Next Step Options (NSO) study which is considering what major experiments might be undertaken in a restructured US Fusion Sciences Program. FIRE is designed for a plasma current of ∼6.5 MA, a burn time of at least 10 s, and a Q in the range of 5 to 10. FIRE has a major radius of 2.0 m, a minor radius of 0.525 m, and a field on axis of 10T. All of the coils are inertially cooled by liquid nitrogen. FIRE will operate primarily in a double null configuration with an x-point triangularity of 0.8 and an x-point elongation of 2.2. In addition to these technical requirements, a major goal for the FIRE project is for a total project cost of approximately $1B (in FY 99 dollars). This paper describes the process and rationale for the engineering design chosen for FIRE, taking into account both the performance and cost goals

Preparations for deuterium--tritium experiments on the Tokamak Fusion Test Reactor*

International Nuclear Information System (INIS)

Hawryluk, R.J.; Adler, H.; Alling, P.; Ancher, C.; Anderson, H.; Anderson, J.L.; Anderson, J.W.; Arunasalam, V.; Ascione, G.; Aschroft, D.; Barnes, C.W.; Barnes, G.; Batchelor, D.B.; Bateman, G.; Batha, S.; Baylor, L.A.; Beer, M.; Bell, M.G.; Biglow, T.S.; Bitter, M.; Blanchard, W.; Bonoli, P.; Bretz, N.L.; Brunkhorst, C.; Budny, R.; Burgess, T.; Bush, H.; Bush, C.E.; Camp, R.; Caorlin, M.; Carnevale, H.; Chang, Z.; Chen, L.; Cheng, C.Z.; Chrzanowski, J.; Collazo, I.; Collins, J.; Coward, G.; Cowley, S.; Cropper, M.; Darrow, D.S.; Daugert, R.; DeLooper, J.; Duong, H.; Dudek, L.; Durst, R.; Efthimion, P.C.; Ernst, D.; Faunce, J.; Fonck, R.J.; Fredd, E.; Fredrickson, E.; Fromm, N.; Fu, G.Y.; Furth, H.P.; Garzotto, V.; Gentile, C.; Gettelfinger, G.; Gilbert, J.; Gioia, J.; Goldfinger, R.C.; Golian, T.; Gorelenkov, N.; Gouge, M.J.; Grek, B.; Grisham, L.R.; Hammett, G.; Hanson, G.R.; Heidbrink, W.; Hermann, H.W.; Hill, K.W.; Hirshman, S.; Hoffman, D.J.; Hosea, J.; Hulse, R.A.; Hsuan, H.; Jaeger, E.F.; Janos, A.; Jassby, D.L.; Jobes, F.C.; Johnson, D.W.; Johnson, L.C.; Kamperschroer, J.; Kesner, J.; Kugel, H.; Kwon, S.; Labik, G.; Lam, N.T.; LaMarche, P.H.; Laughlin, M.J.; Lawson, E.; LeBlanc, B.; Leonard, M.; Levine, J.; Levinton, F.M.; Loesser, D.; Long, D.; Machuzak, J.; Mansfield, D.E.; Marchlik, M.; Marmar, E.S.; Marsala, R.; Martin, A.; Martin, G.; Mastrocola, V.; Mazzucato, E.; McCarthy, M.P.; Majeski, R.; Mauel, M.; McCormack, B.; McCune, D.C.; McGuire, K.M.; Meade, D.M.; Medley, S.S.; Mikkelsen, D.R.; Milora, S.L.; Monticello, D.; Mueller, D.; Murakami, M.; Murphy, J.A.; Nagy, A.; Navratil, G.A.; Nazikian, R.; Newman, R.; Nishitani, T.; Norris, M.; O'Connor, T.; Oldaker, M.; Ongena, J.; Osakabe, M.; Owens, D.K.; Park, H.; Park, W.; Paul, S.F.; Pavlov, Y.I.; Pearson, G.; Perkins, F.; Perry, E.; Persing, R.; Petrov, M.; Phillips, C.K.; Pitcher, S.; Popovichev, S.; Qualls, A.L.; Raftopoulos, S.; Ramakrishnan, R.; Ramsey, A.; Rasmussen, D.A.; Redi, M.H.

1994-01-01

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR) [Fusion Technol. 21, 1324 (1992)]. These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinert TM system, modification of the vacuum system to handle tritium, preparation, and testing of the neutral beam system for tritium operation and a final deuterium--deuterium (D--D) run to simulate expected deuterium--tritium (D--T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D--T experiments using D--D have been performed. The physics objectives of D--T operation are production of ∼10 MW of fusion power, evaluation of confinement, and heating in deuterium--tritium plasmas, evaluation of α-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined α particles. Experimental results and theoretical modeling in support of the D--T experiments are reviewed

Inertial fusion program in Japan and ignition experiment facility by laser

International Nuclear Information System (INIS)

Nakai, S.

1989-01-01

The recent progress in laser fusion research is remarkable with respect to obtaining the high density and high temperature plasma which produces thermonuclear neutrons of 10 13 per shot (pellet gain of 0.2%) and to the understanding of implosion physics. Data bases for laser fusion have been accumulated and technologies for advanced experiments have been developed, both of which enable us to make the reserarch step toward the fusion ignition experiment and the achievement of the breakeven condition, which is estimated to be possible with a 100 kJ blue laser. The demonstration of high gain pellets requires laser energy in the range MJ in blue light. The design studies of the MJ laser are continue in the framework of the solid state laser at ILE. The design studies on the commercial reactor of ICF have proceeded and several conceptual designs have been proposed. These designs utilize a liquid metal first wall and blanket which enable long life for commercial use. As a consequence, the ICF reactor has technically a high feasibility for commercial application. (orig.)

A sensitive HIV-1 envelope induced fusion assay identifies fusion enhancement of thrombin

International Nuclear Information System (INIS)

Cheng, De-Chun; Zhong, Guo-Cai; Su, Ju-Xiang; Liu, Yan-Hong; Li, Yan; Wang, Jia-Ye; Hattori, Toshio; Ling, Hong; Zhang, Feng-Min

2010-01-01

To evaluate the interaction between HIV-1 envelope glycoprotein (Env) and target cell receptors, various cell-cell-fusion assays have been developed. In the present study, we established a novel fusion system. In this system, the expression of the sensitive reporter gene, firefly luciferase (FL) gene, in the target cells was used to evaluate cell fusion event. Simultaneously, constitutively expressed Renilla luciferase (RL) gene was used to monitor effector cell number and viability. FL gave a wider dynamic range than other known reporters and the introduction of RL made the assay accurate and reproducible. This system is especially beneficial for investigation of potential entry-influencing agents, for its power of ruling out the false inhibition or enhancement caused by the artificial cell-number variation. As a case study, we applied this fusion system to observe the effect of a serine protease, thrombin, on HIV Env-mediated cell-cell fusion and have found the fusion enhancement activity of thrombin over two R5-tropic HIV strains.

Fusion energy 1996. V. 1. Proceedings of the 16. international conference

International Nuclear Information System (INIS)

1997-01-01

The sixteenth International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Montreal, Canada, from 7 to 11 October 1996. The conference, which was attended by some 500 participants from over thirty countries and two international organizations, was organized by the IAEA in cooperation with the Centre canadien de fusion magnetique and the Canadian National Fusion Program. Some 270 papers were presented in 19 oral and 8 poster sessions on magnetic and inertial confinement systems, plasma theory, computer modelling, alternative confinement approaches, fusion technology and future experiments. Refs, figs, tabs

Summary of sensor evaluation for the Fusion ELectromagnetic Induction eXperiment (FELIX)

International Nuclear Information System (INIS)

Knott, M.J.

1982-08-01

As part of the First Wall/Blanket/Shield Engineering Test Program, a test bed called FELIX (Fusion ELectromagnetic Induction eXperiment) is now under construction at ANL. Its purpose will be to test, evaluate, and develop computer codes for the prediction of electromagnetically induced phenomenon in a magnetic environment modeling that of a fusion reaction. Crucial to this process is the sensing and recording of the various induced effects. Sensor evaluation for FELIX has reached the point where most sensor types have been evaluated and preliminary decisions are being made as to type and quantity for the initial FELIX experiments. These early experiments, the first, flat plate experiment in particular, will be aimed at testing the sensors as well as the pertinent theories involved. The reason for these evaluations, decisions, and proof tests is the harsh electrical and magnetic environment that FELIX presents

HIFSA: Heavy-Ion Fusion Systems Assessment Project: Volume 1, Executive summary

International Nuclear Information System (INIS)

Dudziak, D.J.; Herrmannsfeldt, W.B.; Saylor, W.W.

1987-12-01

The Heavy-Ion Fusion Systems Assessment (HIFSA) was conducted with the specific objective of evaluating the prospects of using induction-linac heavy-ion accelerators to generate economical electrical power from Inertial Confinement Fusion (ICF). Cost/performance models of the major fusion power plant systems were used to identify promising areas in parameter space. Resulting cost-of-electricity projections for a plant size of 1 GWe are comparable to those from other fusion system studies, some of which were for much larger power plants. These favorable projections maintain over an unusually large domain of parameter space but depend especially on making large cost savings for the accelerator by using higher charge-to-mass ratio ions than assumed previously. The feasibility of realizing such savings has been shown by (1) experiments demonstrating transport stability better than anticipated for space-charge-dominated beams, and (2) theoretical predictions that the final transport and pulse compression in reactor-chamber environments will be sufficiently resistant to streaming instabilities to allow successful propagation of neutralized beams to the target. Results of the HIFSA study already have had a significant impact on the heavy-ion induction accelerator R and D program, especially in selection of the charge-state objectives. Also, the study should enhance the credibility of induction linacs as ICF drivers

Determination of the enthalpy of fusion and thermal diffusivity for ternary Cu_6_0_−_xSn_xSb_4_0 alloys

International Nuclear Information System (INIS)

Zhai, W.; Zhou, K.; Hu, L.; Wei, B.

2016-01-01

Highlights: • The increasing Sn content reduces the liquidus temperature. • High Sn content results in lower enthalpy of fusion by polynomial functions. • The thermal diffusivity drops from the solid toward the semi-solid state. • Undercoolability of alloys with primary Cu_2Sb phase is stronger than others. - Abstract: The liquidus and solidus temperatures, enthalpy of fusion, and the temperature dependence of thermal diffusivity for ternary Cu_6_0_−_xSn_xSb_4_0 alloys were systematically measured by DSC and laser flash methods. It is found that both the liquidus temperature and the enthalpy of fusion decrease with the rise of Sn content, and their relationships with alloy composition were established by polynomial functions. The thermal diffusivity usually drops from the solid toward the semi-solid state. The undercoolability of those liquid Cu_6_0_−_xSn_xSb_4_0 alloys with primary Cu_2Sb solid phase is stronger than the others with primary β(SnSb) intermetallic compound, and the increase of cooling rate facilitates further undercooling. Microstructural observation indicates that both of the primary Cu_2Sb and β(SnSb) intermetallic compounds in ternary Cu_6_0_−_xSn_xSb_4_0 alloys grow in faceted mode, and develop into coarse flakes and polygonal blocks.

Experiences with remote collaborations in fusion research

International Nuclear Information System (INIS)

Wurden, G.A.; Davis, S.; Barnes, D.

1998-03-01

The magnetic fusion research community has considerable experience in placing remote collaboration tools in the hands of real user. The ability to remotely view operations and to control selected instrumentation and analysis tasks has been demonstrated. University of Wisconsin scientists making turbulence measurements on TFTR: (1) were provided with a remote control room from which they could operate their diagnostic, while keeping in close contact with their colleagues in Princeton. LLNL has assembled a remote control room in Livermore in support of a large, long term collaboration on the DIII-D tokamak in San Diego. (2) From the same control room, a joint team of MIT and LLNL scientists has conducted full functional operation of the Alcator C-Mod tokamak located 3,000 miles away in Cambridge Massachusetts. (3) These early efforts have been highly successful, but are only the first steps needed to demonstrate the technical feasibility of a complete facilities on line environment. These efforts have provided a proof of principle for the collaboratory concept and they have also pointed out shortcomings in current generation tools and approaches. Current experiences and future directions will be discussed

Fusion technology development. Annual report to the US Department of Energy, October 1, 1996--September 30, 1997

International Nuclear Information System (INIS)

1998-03-01

In FY97, the General Atomics (GA) Fusion Group made significant contributions to the technology needs of the magnetic fusion program. The work was supported by the Office of Fusion Energy Sciences, International and Technology Division, of the US Department of Energy. The work is reported in the following sections on Fusion Power Plant Studies (Section 2), Plasma Interactive Materials (Section 3), Magnetic Diagnostic Probes (Section 4) and RF Technology (Section 5). Meetings attended and publications are listed in their respective sections. The overall objective of GA's fusion technology research is to develop the technologies necessary for fusion to move successfully from present-day physics experiments to ITER and other next-generation fusion experiments, and ultimately to fusion power plants. To achieve this overall objective, we carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and we conduct research to develop basic knowledge about these technologies, including plasma technologies, fusion nuclear technologies, and fusion materials. We continue to be committed to the development of fusion power and its commercialization by US industry

Experiments at The Virtual National Laboratory for Heavy Ion Fusion

International Nuclear Information System (INIS)

Seidl, P.A.; Bieniosek, F.M.; Celata, C.M.; Faltens, A.; Kwan, J.W.; MacLaren, S.A.; Ponce, D.; Shuman, D.; Yu, S.; Ahle, L.; Lund, S.; Molvik, A.; Sangster, T.C.

2000-01-01

An overview of experiments is presented, in which the physical dimensions, emittance and perveance are scaled to explore driver-relevant beam dynamics. Among these are beam merging, focusing to a small spot, and bending and recirculating beams. The Virtual National Laboratory for Heavy Ion Fusion (VNL) is also developing two driver-scale beam experiments involving heavy-ion beams with I(sub beam) about 1 Ampere to provide guidance for the design of an Integrated Research Experiment (IRE) for driver system studies within the next 5 years. Multiple-beam sources and injectors are being designed and a one-beam module will be built and tested. Another experimental effort will be the transport of such a beam through about 100 magnetic quadrupoles. The experiment will determine transport limits at high aperture fill factors, beam halo formation, and the influence on beam properties of secondary electron Research into driver technology will be briefly presented, including the development of ferromagnetic core materials, induction core pulsers, multiple-beam quadrupole arrays and plasma channel formation experiments for pinched transport in reactor chambers

Heat transfer phenomena in the first wall of the RFX fusion experiment

International Nuclear Information System (INIS)

Oliveira Pauletti, R.M. de

1988-12-01

The thermal analysis of the first wall (FW) of the RFX machine is presented. RFX is a large fusion experiment under construction at Padua, Italy. The RFX FW is briefly described, together with the critical thermal conditions. The numerical analyses performed to predict the FW thermal behaviour are presented. 1-D and 2-D finite element models give accurate predictions of the FW temperatures and of the thermal exchanges in the machine environment. (author) [pt

Radioisotope production in fusion reactors

International Nuclear Information System (INIS)

Engholm, B.A.; Cheng, E.T.; Schultz, K.R.

1986-01-01

Radioisotope production in fusion reactors is being investigated as part of the Fusion Applications and Market Evaluation (FAME) study. /sup 60/Co is the most promising such product identified to date, since the /sup 60/Co demand for medical and food sterilization is strong and the potential output from a fusion reactor is high. Some of the other radioisotopes considered are /sup 99/Tc, /sup 131/l, several Eu isotopes, and /sup 210/Po. Among the stable isotopes of interest are /sup 197/Au, /sup 103/Rh and Os. In all cases, heat or electricity can be co-produced from the fusion reactor, with overall attractive economics

Oral cancer/endothelial cell fusion experiences nuclear fusion and acquisition of enhanced survival potential

International Nuclear Information System (INIS)

Song, Kai; Song, Yong; Zhao, Xiao-Ping; Shen, Hui; Wang, Meng; Yan, Ting-lin; Liu, Ke; Shang, Zheng-jun

2014-01-01

Most previous studies have linked cancer–macrophage fusion with tumor progression and metastasis. However, the characteristics of hybrid cells derived from oral cancer and endothelial cells and their involvement in cancer remained unknown. Double-immunofluorescent staining and fluorescent in situ hybridization (FISH) were performed to confirm spontaneous cell fusion between eGFP-labeled human umbilical vein endothelial cells (HUVECs) and RFP-labeled SCC9, and to detect the expression of vementin and cytokeratin 18 in the hybrids. The property of chemo-resistance of such hybrids was examined by TUNEL assay. The hybrid cells in xenografted tumor were identified by FISH and GFP/RFP dual-immunofluoresence staining. We showed that SCC9 cells spontaneously fused with cocultured endothelial cells, and the resultant hybrid cells maintained the division and proliferation activity after re-plating and thawing. Such hybrids expressed markers of both parental cells and became more resistant to chemotherapeutic drug cisplatin as compared to the parental SCC9 cells. Our in vivo data indicated that the hybrid cells contributed to tumor composition by using of immunostaining and FISH analysis, even though the hybrid cells and SCC9 cells were mixed with 1:10,000, according to the FACS data. Our study suggested that the fusion events between oral cancer and endothelial cells undergo nuclear fusion and acquire a new property of drug resistance and consequently enhanced survival potential. These experimental findings provide further supportive evidence for the theory that cell fusion is involved in cancer progression. - Highlights: • The fusion events between oral cancer and endothelial cells undergo nuclear fusion. • The resulting hybrid cells acquire a new property of drug resistance. • The resulting hybrid cells express the markers of both parental cells (i.e. vimentin and cytokeratin 18). • The hybrid cells contribute to tumor repopulation in vivo

Oral cancer/endothelial cell fusion experiences nuclear fusion and acquisition of enhanced survival potential

Energy Technology Data Exchange (ETDEWEB)

Song, Kai [Department of Oral and Maxillofacial Surgery, The Affiliated Hospital of Qingdao University, Shandong Province (China); The State Key Laboratory Breeding Base of Basic Science of Stomatology (Hubei-MOST) and Key Laboratory for Oral Biomedicine Ministry of Education, Wuhan University, Wuhan (China); Song, Yong [The State Key Laboratory Breeding Base of Basic Science of Stomatology (Hubei-MOST) and Key Laboratory for Oral Biomedicine Ministry of Education, Wuhan University, Wuhan (China); Department of Stomatology, Liu Zhou People' s Hospital, Guangxi (China); Zhao, Xiao-Ping; Shen, Hui; Wang, Meng; Yan, Ting-lin [The State Key Laboratory Breeding Base of Basic Science of Stomatology (Hubei-MOST) and Key Laboratory for Oral Biomedicine Ministry of Education, Wuhan University, Wuhan (China); Liu, Ke, E-mail: liuke.1999@aliyun.com [Department of Oral and Maxillofacial-Head and Neck oncology, School and Hospital of Stomatology, Wuhan University, 237 Luoyu Road, Wuhan 430079 (China); The State Key Laboratory Breeding Base of Basic Science of Stomatology (Hubei-MOST) and Key Laboratory for Oral Biomedicine Ministry of Education, Wuhan University, Wuhan (China); Shang, Zheng-jun, E-mail: shangzhengjun@hotmail.com [Department of Oral and Maxillofacial-Head and Neck oncology, School and Hospital of Stomatology, Wuhan University, 237 Luoyu Road, Wuhan 430079 (China); The State Key Laboratory Breeding Base of Basic Science of Stomatology (Hubei-MOST) and Key Laboratory for Oral Biomedicine Ministry of Education, Wuhan University, Wuhan (China)

2014-10-15

Most previous studies have linked cancer–macrophage fusion with tumor progression and metastasis. However, the characteristics of hybrid cells derived from oral cancer and endothelial cells and their involvement in cancer remained unknown. Double-immunofluorescent staining and fluorescent in situ hybridization (FISH) were performed to confirm spontaneous cell fusion between eGFP-labeled human umbilical vein endothelial cells (HUVECs) and RFP-labeled SCC9, and to detect the expression of vementin and cytokeratin 18 in the hybrids. The property of chemo-resistance of such hybrids was examined by TUNEL assay. The hybrid cells in xenografted tumor were identified by FISH and GFP/RFP dual-immunofluoresence staining. We showed that SCC9 cells spontaneously fused with cocultured endothelial cells, and the resultant hybrid cells maintained the division and proliferation activity after re-plating and thawing. Such hybrids expressed markers of both parental cells and became more resistant to chemotherapeutic drug cisplatin as compared to the parental SCC9 cells. Our in vivo data indicated that the hybrid cells contributed to tumor composition by using of immunostaining and FISH analysis, even though the hybrid cells and SCC9 cells were mixed with 1:10,000, according to the FACS data. Our study suggested that the fusion events between oral cancer and endothelial cells undergo nuclear fusion and acquire a new property of drug resistance and consequently enhanced survival potential. These experimental findings provide further supportive evidence for the theory that cell fusion is involved in cancer progression. - Highlights: • The fusion events between oral cancer and endothelial cells undergo nuclear fusion. • The resulting hybrid cells acquire a new property of drug resistance. • The resulting hybrid cells express the markers of both parental cells (i.e. vimentin and cytokeratin 18). • The hybrid cells contribute to tumor repopulation in vivo.

Accomplishment of JT-60U disassembly work dealing with radioactive components

International Nuclear Information System (INIS)

Ikeda, Yoshitaka

2015-01-01

The upgrade of the JT-60U to the superconducting tokamak 'JT-60SA' has been carried out to contribute the early realization of fusion energy by addressing key physics issues relevant for ITER and DEMO. Disassembly of the JT-60U tokamak was required so as to newly install the JT-60SA torus at the same position in the torus hall. The JT-60U tokamak was featured by the complicated and welded structure against the strong electromagnetic force, and by the radioactivation due to deuterium-deuterium (D-D) reactions of 1.5x10"2"0 (n) in total. Since this work was the first experience of disassembling a large radioactivated fusion device in Japan, careful preparations of disassembly activities, including treatment of the radioactivated materials and safety work, have been made. About 13,000 components with a total weight of more than 5,400 tonnes were removed from the torus hall and stored safely in storage facilities. All disassembly components were stored with recording the data such as dose rate, weight and kind of material, so as to apply the clearance level regulation in future. It was confirmed that the main radioactive material of the disassembly components was the stainless steel and that its dose rate was almost background level (∼0.1 μSv/h) at ∼10 m far from the vacuum vessel. It seems that the disassembly components with background dose level are in the clearance level. The assembly of JT-60SA tokamak has started in January 2013 after this disassembly of the JT-60U tokamak. (author)

Research and development of fusion grid infrastructure based on atomic energy grid infrastructure (AEGIS)

International Nuclear Information System (INIS)

Suzuki, Y.; Nakajima, K.; Kushida, N.; Kino, C.; Aoyagi, T.; Nakajima, N.; Iba, K.; Hayashi, N.; Ozeki, T.; Totsuka, T.; Nakanishi, H.; Nagayama, Y.

2008-01-01

In collaboration with the Naka Fusion Institute of Japan Atomic Energy Agency (NFI/JAEA) and the National Institute for Fusion Science of National Institute of Natural Science (NIFS/NINS), Center for Computational Science and E-systems of Japan Atomic Energy Agency (CCSE/JAEA) aims at establishing an integrated framework for experiments and analyses in nuclear fusion research based on the atomic energy grid infrastructure (AEGIS). AEGIS has been being developed by CCSE/JAEA aiming at providing the infrastructure that enables atomic energy researchers in remote locations to carry out R and D efficiently and collaboratively through the Internet. Toward establishing the integrated framework, we have been applying AEGIS to pre-existing three systems: experiment system, remote data acquisition system, and integrated analysis system. For the experiment system, the secure remote experiment system with JT-60 has been successfully accomplished. For the remote data acquisition system, it will be possible to equivalently operate experimental data obtained from LHD data acquisition and management system (LABCOM system) and JT-60 Data System. The integrated analysis system has been extended to the system executable in heterogeneous computers among institutes

Precision operation of the Nova laser for fusion experiments

International Nuclear Information System (INIS)

Caird, J.A.; Ehrlich, R.B.; Hermes, G.L.; Landen, O.L.; Laumann, C.W.; Lerche, R.A.; Miller, J.L.; Murray, J.E.; Nielsen, N.D.; Powell, H.T.; Rushford, M.C.; Saunders, R.L.; Thompson, C.E.; VanArsdall, P.J.; Vann, C.S.; Weiland, T.L.

1994-01-01

The operation of a Neodymium glass laser of a special design for fusion experiments is improved by a better pulse synchronization, the gain stabilization, and the laser diagnostics. We used sensor upgrading and antifriction coating of focusing lenses. The pointing accuracy of the Nova laser meets now our goal for precision operation. (AIP) copyright 1994 American Institute of Physics

Flunarizine Prevents Hepatitis C Virus Membrane Fusion in a Genotype-dependent Manner by Targeting the Potential Fusion Peptide within E1

Science.gov (United States)

Perin, Paula M.; Haid, Sibylle; Brown, Richard J. P.; Doerrbecker, Juliane; Schulze, Kai; Zeilinger, Carsten; von Schaewen, Markus; Heller, Brigitte; Vercauteren, Koen; Luxenburger, Eva; Baktash, Yasmine M.; Vondran, Florian W. R.; Speerstra, Sietkse; Awadh, Abdullah; Mukhtarov, Furkat; Schang, Luis M; Kirschning, Andreas; Müller, Rolf; Guzman, Carlos A.; Kaderali, Lars; Randall, Glenn; Meuleman, Philip; Ploss, Alexander; Pietschmann, Thomas

2015-01-01

To explore mechanisms of hepatitis C virus (HCV) replication we screened a compound library including licensed drugs. Flunarizine, a diphenylmethylpiperazine used to treat migraine, inhibited HCV cell entry in vitro and in vivo in a genotype-dependent fashion. Analysis of mosaic viruses between susceptible and resistant strains revealed that E1 and E2 glycoproteins confer susceptibility to flunarizine. Time of addition experiments and single particle tracking of HCV demonstrated that flunarizine specifically prevents membrane fusion. Related phenothiazines and pimozide also inhibited HCV infection and preferentially targeted HCV genotype 2 viruses. However, phenothiazines and pimozide exhibited improved genotype coverage including the difficult to treat genotype 3. Flunarizine-resistant HCV carried mutations within the alleged fusion peptide and displayed cross-resistance to these compounds, indicating that these drugs have a common mode of action. Conclusion: These observations reveal novel details about HCV membrane fusion. Moreover, flunarizine and related compounds represent first-in-class HCV fusion inhibitors that merit consideration for repurposing as cost-effective component of HCV combination therapies. PMID:26248546

BCL-x{sub L}/MCL-1 inhibition and RARγ antagonism work cooperatively in human HL60 leukemia cells

Energy Technology Data Exchange (ETDEWEB)

Perri, Mariarita; Yap, Jeremy L.; Yu, Jianshi [Department of Pharmaceutical Sciences, University of Maryland School of Pharmacy, 20 N Pine Street, Baltimore, MD 21201 (United States); Cione, Erika [Department of Pharmacy, Health and Nutritional Sciences, Ed. Polifunzionale, University of Calabria, 87036 Rende, CS (Italy); Fletcher, Steven [Department of Pharmaceutical Sciences, University of Maryland School of Pharmacy, 20 N Pine Street, Baltimore, MD 21201 (United States); Kane, Maureen A., E-mail: mkane@rx.umaryland.edu [Department of Pharmaceutical Sciences, University of Maryland School of Pharmacy, 20 N Pine Street, Baltimore, MD 21201 (United States)

2014-10-01

The acute promyelocytic leukemia (APL) subtype of acute myeloid leukemia (AML) is characterized by chromosomal translocations that result in fusion proteins, including the promyelocytic leukemia–retinoic acid receptor, alpha fusion protein (PML–RARα). All-trans retinoic acid (atRA) treatment is the standard drug treatment for APL yielding cure rates >80% by activating transcription and proteasomal degradation of retinoic acid receptor, alpha (RARα). Whereas combination therapy with As{sub 2}O{sub 3} has increased survival further, patients that experience relapse and are refractory to atRA and/or As{sub 2}O{sub 3} is a clinically significant problem. BCL-2 family proteins regulate apoptosis and over-expression of anti-apoptotic B-cell leukemia/lymphoma 2 (BCL-2) family proteins has been associated with chemotherapeutic resistance in APL including impairment of the ability of atRA to induce growth arrest and differentiation. Here we investigated the novel BH3 domain mimetic, JY-1-106, which antagonizes the anti-apoptotic BCL-2 family members B-cell lymphoma-extra large (BCL-x{sub L}) and myeloid cell leukemia-1 (MCL-1) alone and in combination with retinoids including atRA, AM580 (RARα agonist), and SR11253 (RARγ antagonist). JY-1-106 reduced cell viability in HL-60 cells alone and in combination with retinoids. The combination of JY-1-106 and SR11253 had the greatest impact on cell viability by stimulating apoptosis. These studies indicate that dual BCL-x{sub L}/MCL-1 inhibitors and retinoids could work cooperatively in leukemia treatment. - Highlights: • Novel Bcl-x{sub L}/Mcl-1 inhibitor JY-1-106 reduces HL60 cell viability. • JY-1-106 is investigated in combination with retinoic acid, AM580, and SR11253. • AM580 is an RARα agonist; SR11253 is an RARγ antagonist. • Combined use of JY-1-106/SR11253 exhibited the greatest cell viability reduction. • JY-1-106 alone or in combination with retinoids induces apoptosis.

Multimerized CHR-derived peptides as HIV-1 fusion inhibitors.

Science.gov (United States)

Nomura, Wataru; Hashimoto, Chie; Suzuki, Takaharu; Ohashi, Nami; Fujino, Masayuki; Murakami, Tsutomu; Yamamoto, Naoki; Tamamura, Hirokazu

2013-08-01

To date, several HIV-1 fusion inhibitors based on the carboxy-terminal leucine/isoleucine heptad repeat (CHR) region of an HIV-1 envelope protein gp41 have been discovered. We have shown that a synthetic peptide mimetic of a trimer form of the CHR-derived peptide C34 has potent inhibitory activity against the HIV-1 fusion mechanism, compared to a monomer C34 peptide. The present study revealed that a dimeric form of C34 is evidently structurally critical for fusion inhibitors, and that the activity of multimerized CHR-derived peptides in fusion inhibition is affected by the properties of the unit peptides C34, SC34EK, and T20. The fluorescence-based study suggested that the N36-interactive sites of the C34 trimer, including hydrophobic residues, are exposed outside the trimer and that trimerization of C34 caused a remarkable increase in fusion inhibitory activity. The present results could be useful in the design of fusion inhibitors against viral infections which proceed via membrane fusion with host cells. Copyright © 2013 The Authors. Published by Elsevier Ltd.. All rights reserved.

Particle beam fusion progress report January 1979 through June 1979

International Nuclear Information System (INIS)

1980-10-01

The following chapters are included: (1) fusion target studies, (2) target experiments, (3) particle beam source development, (4) particle beam experiments, (5) pulsed power research and development, (6) pulsed fusion applications, and (7) electron beam fusion accelerator project

New evidence for prehistoric copper metallurgy in the vicinity of Bor

Directory of Open Access Journals (Sweden)

Kapuran Aleksandar

2016-01-01

Full Text Available The last three years of archaeological investigations at the site Ru`ana in Banjsko Polje, in the immediate vicinity of Bor, have provided new evidence regarding the role of non-ferrous metallurgy in the economy of the prehistoric communities of north-eastern Serbia. The remains of metallurgical furnaces and a large amount of metallic slags at two neighbouring sites in the mentioned settlement reveal that locations with many installations for the thermal processing of copper ore existed in the Bronze Age. We believe, judging by the finds of material culture, that metallurgical activities in this area also continued into the Iron Age and, possibly, into the 4th century AD. [Projekat Ministarstva nauke Republike Srbije, br. 177020: Archaeology of Serbia: Cultural identity, integration factors, technological processes and the role of the central Balkans in the development of European prehistory

The timing system of the RFX Nuclear Fusion Experiment

International Nuclear Information System (INIS)

Schmidt, V.; Flor, G.; Manduchi, G.; Piacentini, I.

1992-01-01

The REX Nuclear Fusion Experiment [1] in Padova, Italy, employs a distributed system to produce precision trigger signals for the fast control of the experiment and for the experiment-wide synchronization of data acquisition channels. The hardware of the system is based on a set of CAMAC modules. The modules have been integrated into a hardware/software system which provides the following features: 1) generation of pre-programmed timing events, 2) distribution of asynchronous (not pre-programmed) timing events, 3) gating of timing event generation by Machine Protection System, 4) automatic stop of timing sequence in case of highway damage, 5) dual-speed time base for transient recorders, 6) system-wide precision of ≤ 3 μs, time resolution ≥ 10 μs. The operation of the timing system is fully integrated into the RFX data acquisition system software. The Timing System Software consists of three layers: the lowest one corresponds directly to the CAMAC modules, the intermediate one provides pseudo-devices which essentially correspond to specific features for the modules (e.g. a dual frequency clock source for transient recorders), the highest level provides system set-up support. The system is fully operational and was first used during the commissioning of the RFX Power Supplies in spring '91. (author)

Scaled beam merging experiment for heavy ion inertial fusion

Directory of Open Access Journals (Sweden)

P. A. Seidl

2003-09-01

Full Text Available Transverse beam combining is a cost-saving option employed in many designs for heavy ion fusion drivers. However, the resultant transverse phase space dilution must be minimized so as not to sacrifice focusability at the target. A prototype combining experiment has been completed employing four 3-mA Cs^{+} beams injected at 160 keV. The focusing elements upstream of the merge consist of four quadrupoles and a final combined-function element (quadrupole and dipole. Following the merge, the resultant single beam is transported in a single alternating gradient channel where the subsequent evolution of the distribution function is diagnosed. The results are in fair agreement with particle-in-cell simulations. They indicate that for some heavy ion fusion driver designs, the phase space dilution from merging is acceptable.

Laser fusion experiments at LLL

Energy Technology Data Exchange (ETDEWEB)

Ahlstrom, H.G.

1980-06-16

These notes present the experimental basis and status for laser fusion as developed at LLL. Two other chapters, one authored by K.A. Brueckner and the other by C. Max, present the theoretical implosion physics and laser plasma interaction physics. The notes consist of six sections. The first is an introductory section which provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future.

Laser fusion experiments at LLL

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1980-01-01

These notes present the experimental basis and status for laser fusion as developed at LLL. Two other chapters, one authored by K.A. Brueckner and the other by C. Max, present the theoretical implosion physics and laser plasma interaction physics. The notes consist of six sections. The first is an introductory section which provides some of the history of inertial fusion and a simple explanation of the concepts involved. The second section presents an extensive discussion of diagnostic instrumentation used in the LLL Laser Fusion Program. The third section is a presentation of laser facilities and capabilities at LLL. The purpose here is to define capability, not to derive how it was obtained. The fourth and fifth sections present the experimental data on laser-plasma interaction and implosion physics. The last chapter is a short projection of the future

Verification of cold nuclear fusion reaction, (1)

International Nuclear Information System (INIS)

Yoshida, Zenko; Aratono, Yasuyuki; Hirabayashi, Takakuni

1991-01-01

Can cold nuclear fusion reaction occur as is expected? If it occurs, what extent is its reaction probability? At present after 2 years elapsed since its beginning, the clear solution of these questions is not yet obtained. In many reaction systems employing different means, the experiments to confirm the cold nuclear fusion reaction have been attempted. In order to confirm that the nuclear fusion reaction of deuterium mutually has occurred, the neutrons, He-3, protons, tritium or generated heat, which were formed by the reaction and released from the system, are measured. Since it is considered that the frequency of the occurrence at normal temperature of the reaction is very low, it is necessary to select the most suitable method upon evaluating the limit of detection peculiar to the measuring methods. The methods of measuring neutrons, protons, gamma ray and generated heat, and the reaction systems by electrolytic process and dry process are explained. The detection of plural kinds of the reaction products and the confirmation of synchronism of signals are important. (K.I.)

Fusion Energy Division progress report, 1 January 1990--31 December 1991

International Nuclear Information System (INIS)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

1994-03-01

The Fusion Program of the Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, encompasses nearly all areas of magnetic fusion research. The program is directed toward the development of fusion as an economical and environmentally attractive energy source for the future. The program involves staff from ORNL, Martin Marietta Energy systems, Inc., private industry, the academic community, and other fusion laboratories, in the US and abroad. Achievements resulting from this collaboration are documented in this report, which is issued as the progress report of the ORNL Fusion Energy Division; it also contains information from components for the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices, including remote handling; development and testing of diagnostic tools and techniques in support of experiments; assembly and distribution to the fusion community of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; development and testing of superconducting magnets for containing fusion plasmas; development and testing of materials for fusion devices; and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas (about 15% of the Division's activities). Highlights from program activities during 1990 and 1991 are presented

Fusion Energy Division progress report, 1 January 1990--31 December 1991

Energy Technology Data Exchange (ETDEWEB)

Sheffield, J.; Baker, C.C.; Saltmarsh, M.J.

1994-03-01

The Fusion Program of the Oak Ridge National Laboratory (ORNL), a major part of the national fusion program, encompasses nearly all areas of magnetic fusion research. The program is directed toward the development of fusion as an economical and environmentally attractive energy source for the future. The program involves staff from ORNL, Martin Marietta Energy systems, Inc., private industry, the academic community, and other fusion laboratories, in the US and abroad. Achievements resulting from this collaboration are documented in this report, which is issued as the progress report of the ORNL Fusion Energy Division; it also contains information from components for the Fusion Program that are external to the division (about 15% of the program effort). The areas addressed by the Fusion Program include the following: experimental and theoretical research on magnetic confinement concepts; engineering and physics of existing and planned devices, including remote handling; development and testing of diagnostic tools and techniques in support of experiments; assembly and distribution to the fusion community of databases on atomic physics and radiation effects; development and testing of technologies for heating and fueling fusion plasmas; development and testing of superconducting magnets for containing fusion plasmas; development and testing of materials for fusion devices; and exploration of opportunities to apply the unique skills, technology, and techniques developed in the course of this work to other areas (about 15% of the Division`s activities). Highlights from program activities during 1990 and 1991 are presented.

Charge-exchange and fusion reaction measurements during compression experiments with neutral beam heating in the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Kaita, R.; Heidbrink, W.W.; Hammett, G.W.

1986-04-01

Adiabatic toroidal compression experiments were performed in conjunction with high power neutral beam injection in the Tokamak Fusion Test Reactor (TFTR). Acceleration of beam ions to energies nearly twice the injection energy was measured with a charge-exchange neutral particle analyzer. Measurements were also made of 2.5 MeV neutrons and 15 MeV protons produced in fusion reactions between the deuterium beam ions and the thermal deuterium and 3 He ions, respectively. When the plasma was compressed, the d(d,n) 3 He fusion reaction rate increased a factor of five, and the 3 He(d,p) 4 He rate by a factor of twenty. These data were simulated with a bounce-averaged Fokker-Planck program, which assumed conservation of angular momentum and magnetic moment during compression. The results indicate that the beam ion acceleration was consistent with adiabatic scaling

The Fusion Loops of the Initial Prefusion Conformation of Herpes Simplex Virus 1 Fusion Protein Point Toward the Membrane

Directory of Open Access Journals (Sweden)

Juan Fontana

2017-08-01

Full Text Available All enveloped viruses, including herpesviruses, must fuse their envelope with the host membrane to deliver their genomes into target cells, making this essential step subject to interference by antibodies and drugs. Viral fusion is mediated by a viral surface protein that transits from an initial prefusion conformation to a final postfusion conformation. Strikingly, the prefusion conformation of the herpesvirus fusion protein, gB, is poorly understood. Herpes simplex virus (HSV, a model system for herpesviruses, causes diseases ranging from mild skin lesions to serious encephalitis and neonatal infections. Using cryo-electron tomography and subtomogram averaging, we have characterized the structure of the prefusion conformation and fusion intermediates of HSV-1 gB. To this end, we have set up a system that generates microvesicles displaying full-length gB on their envelope. We confirmed proper folding of gB by nondenaturing electrophoresis-Western blotting with a panel of monoclonal antibodies (MAbs covering all gB domains. To elucidate the arrangement of gB domains, we labeled them by using (i mutagenesis to insert fluorescent proteins at specific positions, (ii coexpression of gB with Fabs for a neutralizing MAb with known binding sites, and (iii incubation of gB with an antibody directed against the fusion loops. Our results show that gB starts in a compact prefusion conformation with the fusion loops pointing toward the viral membrane and suggest, for the first time, a model for gB’s conformational rearrangements during fusion. These experiments further illustrate how neutralizing antibodies can interfere with the essential gB structural transitions that mediate viral entry and therefore infectivity.

Progress in direct-drive laser fusion using GEKKO XII/PW facility

International Nuclear Information System (INIS)

Yamanaka, T.

2002-01-01

Extensive studies have been carried out for the fast-ignitor laser fusion which can provide one of the most feasible short tracks in the fusion energy development. We have upgraded the heating laser up to 1 PW(500 J/500 fs) and have started comprehensive studies on the transport of high current relativistic electron beam in the dense plasma. Substantial heating of the core plasma up to 1 keV is expected with implosion plasma produced by the Gekko XII laser. We have experimentally obtained for the first time all parameters to decide the growth rate of Rayleigh-Taylor instability using the HIPER irradiation system which can generate ablation pressure up to 60 Mbar and newly developed advanced x-ray diagnostic tools. We have proposed the FIREX (Fast Ignitor Realization Experiment) program for demonstrating the proof-of-principle of fast ignitor scheme. By the irradiation of ∼10 kJ/2-10 ps laser onto a DT core plasma formed by the GEKKO-XII, we are aiming at temperature of >8 keV and the fusion gain near unity. (author)

The NA60 experiment readout architecture

CERN Document Server

Floris, M; Usai, G L; David, A; Rosinsky, P; Ohnishi, H

2004-01-01

The NA60 experiment was designed to identify signatures of a new state of matter, the Quark Gluon Plasma, in heavy-ion collisions at the CERN Super Proton Synchroton. The apparatus is composed of four main detectors: a muon spectrometer (MS), a zero degree calorimeter (ZDC), a silicon vertex telescope (VT), and a silicon microstrip beam tracker (BT). The readout of the whole experiment is based on a PCI architecture. The basic unit is a general purpose PCI card, interfaced to the different subdetectors via custom mezzanine cards. This allowed us to successfully implement several completely different readout protocols (from the VME like protocol of the MS to the custom protocol of the pixel telescope). The system was fully tested with proton and ion beams, and several million events were collected in 2002 and 2003. This paper presents the readout architecture of NA60, with particular emphasis on the PCI layer common to all the subdetectors. (16 refs).

World progress toward fusion energy

International Nuclear Information System (INIS)

Clarke, J.F.

1989-09-01

This paper will describe the progress in fusion science and technology from a world perspective. The paper will cover the current technical status, including the understanding of fusion's economic, environmental, and safety characteristics. Fusion experiments are approaching the energy breakeven condition. An energy gain (Q) of 30 percent has been achieved in magnetic confinement experiments. In addition, temperatures required for an ignited plasma (Ti = 32 KeV) and energy confinements about 75 percent of that required for ignition have been achieved in separate experiments. Two major facilities have started the experimental campaign to extend these results and achieve or exceed Q = 1 plasma conditions by 1990. Inertial confinement fusion experiments are also approaching thermonuclear conditions and have achieved a compression factor 100-200 times liquid D-T. Because of this progress, the emphasis in fusion research is turning toward questions of engineering feasibility. Leaders of the major fusion R and D programs in the European Community (EC), Japan, the United States, and the U.S.S.R. have agreed on the major steps that are needed to reach the point at which a practical fusion system can be designed. The United States is preparing for an experiment to address the last unexplored scientific issue, the physics of an ignited plasma, during the late 1990's. The EC, Japan, U.S.S.R., and the United States have joined together under the auspices of the International Atomic Energy Agency (IAEA) to jointly design and prepare the validating R and D for an international facility, the International Thermonuclear Experimental Reactor (ITER), to address all the remaining scientific issues and to explore the engineering technology of fusion around the turn of the century. In addition, a network of international agreements have been concluded between these major parties and a number of smaller fusion programs, to cooperate on resolving a complete spectrum of fusion science and

Thermonuclear fusion

International Nuclear Information System (INIS)

Weisse, J.

2000-01-01

This document takes stock of the two ways of thermonuclear fusion research explored today: magnetic confinement fusion and inertial confinement fusion. The basic physical principles are recalled first: fundamental nuclear reactions, high temperatures, elementary properties of plasmas, ignition criterion, magnetic confinement (charged particle in a uniform magnetic field, confinement and Tokamak principle, heating of magnetized plasmas (ohmic, neutral particles, high frequency waves, other heating means), results obtained so far (scale laws and extrapolation of performances, tritium experiments, ITER project), inertial fusion (hot spot ignition, instabilities, results (Centurion-Halite program, laser experiments). The second part presents the fusion reactor and its associated technologies: principle (tritium production, heat source, neutron protection, tritium generation, materials), magnetic fusion (superconducting magnets, divertor (role, principle, realization), inertial fusion (energy vector, laser adaptation, particle beams, reaction chamber, stresses, chamber concepts (dry and wet walls, liquid walls), targets (fabrication, injection and pointing)). The third chapter concerns the socio-economic aspects of thermonuclear fusion: safety (normal operation and accidents, wastes), costs (costs structure and elementary comparison, ecological impact and external costs). (J.S.)

US fusion community discussion on fusion strategies

International Nuclear Information System (INIS)

Marton, W.A.

1998-01-01

On April 26 - May 1, 1998, a US Fusion Community Forum for Major Next-Step Experiments was held at Madison, Wisconsin, USA. Both the Single Integrated Step strategy and the Multiple Machine strategy have substantial support from the about 180 scientists and engineers who participated

2. Interferometry and polarimetry. 2.3. Polarimetry on JT-60U

International Nuclear Information System (INIS)

Kawano, Yasunori

2000-01-01

In order to establish an electron density measurement method with high reliability and stability for magnetic-confinement fusion devices, studies on infrared polarimetry have been carried out in JT-60U. Electron density measurement based on tangential Faraday rotation has been verified using a CO 2 laser polarimeter developed for JT-60U. In this article, basic ideas of studies, results from polarimetry experiments, and suggestions for future devices are presented. (author)

Nitrogen implantation in tungsten and migration in the fusion experiment ASDEX upgrade

International Nuclear Information System (INIS)

Meisl, Gerd Korbinian

2015-01-01

The implantation of nitrogen ions into tungsten was studied in laboratory experiments to understand the interaction of nitrogen containing fusion plasmas with tungsten walls. The resulting model of W-N interaction was tested by experiments in the tokamak ASDEX Upgrade. Using the measurements from these experiments as boundary condition, nitrogen transport and re-distribution in the plasma were modeled by self-consistent WallDYN-DIVIMP simulations.

Review of fusion synfuels

International Nuclear Information System (INIS)

Fillo, J.A.

1980-01-01

Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high-temperature electrolysis of approx. 50 to 65% are projected for fusion reactors using high-temperatures blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long term, there could be a gradual transition to an inexhaustible energy system based solely on fusion

Review of JT-60 experiment (April-June, 1985)

International Nuclear Information System (INIS)

1986-11-01

Initial ohmic heating experiments in JT-60 were performed for a three month period of April-June 1985. A maximum plasma current of 1.6 MA was obtained for both divertor and limiter discharges. Low-q discharges of q eff = 2.5 and high density discharges of 4.8 x 10 19 m -3 were obtained in the divertor configuration. Typical divertor actions, i.e. particle exhaust, heat exhaust, impurity reduction and remote radiative cooling were demonstrated. (author)

Radiation risk in Finland due to the nuclear power plant at Sosnovyj Bor

International Nuclear Information System (INIS)

Ilvonen, M.; Rossi, J.; Salonoja, M.

1994-06-01

The present study is an application of the long range transport and dose model TRADOS developed jointly by the Finnish Meteorological Institute and Technical Research Centre of Finland. The aim of the study is to assess the radiation risk in Finland due to the nuclear power plant at Sosnovyj Bor near St. Petersburg in Russia. Probabilities of reaching different parts of the country, transport time and time spent over Finland by the trajectories are presented. Also breadth of the radioactive cloud and incidence of rain are estimated. The calculated radiation doses are based on one single hypothetical release, in which all noble gases are released, together with 10 % of easily vaporizing elements and 1 % of others. All results are based on the assumption that the probability of the release is 100 %. The dose pathways calculated are cloud gamma, fallout gamma, inhalation, and ingestion of milk, meat, green vegetables, grain and roots. External dose rates have been calculated. The necessity of countermeasures and the ratio of the avertable dose to the costs are also assessed. (13 refs., 156 figs., 12 tabs.)

Prospects for toroidal fusion reactors

International Nuclear Information System (INIS)

Sheffield, J.; Galambos, J.D.

1994-01-01

Work on the International Thermonuclear Experimental Reactor (ITER) tokamak has refined understanding of the realities of a deuterium-tritium (D-T) burning magnetic fusion reactor. An ITER-like tokamak reactor using ITER costs and performance would lead to a cost of electricity (COE) of about 130 mills/kWh. Advanced tokamak physics to be tested in the Toroidal Physics Experiment (TPX), coupled with moderate components in engineering, technology, and unit costs, should lead to a COE comparable with best existing fission systems around 60 mills/kWh. However, a larger unit size, ∼2000 MW(e), is favored for the fusion system. Alternative toroidal configurations to the conventional tokamak, such as the stellarator, reversed-field pinch, and field-reversed configuration, offer some potential advantage, but are less well developed, and have their own challenges

Progress of laser nuclear fusion research

International Nuclear Information System (INIS)

Shiraga, Hiroyuki

2017-01-01

This paper describes the principle and features of nuclear fusion using laser, as well as its basic concepts such as high-temperature / high-density implosion system and fast ignition of fuel. At present, researches aiming at nuclear fusion ignition have been developing. As the current state of researches, this paper reviews the situations of FIREX (Fast Ignition Realization Experiment) project of Japan focusing on direct irradiation implosion and fast ignition system, as well as NIF (National Ignition Facility) project of the U.S. aiming at ignition combustion based on indirect irradiation implosion and central ignition system. In collaboration with the National Institute for Fusion Science, Osaka University started FIREX-1 project in 2003. It built a heating laser LFEX of 10 kJ/1 to 10ps, and started an implosion/heating integration experiment in 2009. Currently, it is developing experiment to achieve heating to 5 keV. At NIF, the self-heating of central sparks via energy of α particles generated in the nuclear fusion reaction has been realized. This paper also overviews R and D issues surrounding the lasers for reactors for use in laser nuclear fusion power generators. (A.O.)

Shock-tube study of fusion plasma-wall interactions

International Nuclear Information System (INIS)

Gross, R.A.; Tien, J.K.; Jensen, B.; Panayotou, N.F.; Feinberg, B.

1977-01-01

Theoretical and experimental studies have been made of phenomena which occur when a hot (T 1 approximately equal to 6 x 10 6 0 K), dense (n approximately equal to 10 16 cm -3 ), deuterium plasma containing a transverse magnetic field is brought into sudden contact with a cold metal wall. These studies are motivated by the need to understand plasma and metallurgical conditions at the first-wall of a fusion reactor. Experiments were carried out in the Columbia high energy electromagnetic shock tube. Computational simulation was used to investigate the detailed physics of the fusion plasma boundary layer which develops at the wall. The rate of energy transfer from the plasma to the wall was calculated and conditions under which surface melting occurs are estimated. Experimental measurements of plasma-wall heat transfer rates up to 3 x 10 5 watts/cm 2 were obtained and agreement with computed values are good. Fusion reactor first-wall materials have been exposed to 6.0 x 10 21 eV cm -2 (1,000 shots) of deuterium plasma bombardment. Scanning electron micrograph photographs show preferential erosion at grain boundaries, formation of deuterium surface blisters, and evidence of local surface melting. Some cracking is observed along grain boundaries, and a decrease in tensile ductiity is measured

The IGNITEX fusion project

International Nuclear Information System (INIS)

Carrera, R.

1987-01-01

The author discusses the recently proposed fusion ignition experiment, IGNITEX. He emphasizes the basic ideas of this concept rather than the specific details of the physics and engineering aspects of the experiment. This concept is a good example of the importance of maintaining an adequate balance between the basic scientific progress in fusion physics and the new technologies that are becoming available in order to make fusion work. The objective of the IGNITEX project is to produce and control ignited plasmas for scientific study in the simplest and least expensive way possible. Being able to study this not-yet-produced regime of plasma operation is essential to fusion research. Two years after the fission nuclear reaction was discovered, a non-self-sustained fission reaction was produced in a laboratory, and in one more year a self-sustained reaction was achieved at the University of Chicago. However, after almost forty years of fusion research, a self-sustained fusion reaction has yet not been produced in a laboratory experiment. This fact indicates the greater difficulty of the fusion experiment. Because of the difficulty involved in the production of a self-sustained fusion reaction, it is necessary to propose such an experiment with maximum ignition margins, maximum simplicity, and minimum financial risk

Oral cancer/endothelial cell fusion experiences nuclear fusion and acquisition of enhanced survival potential.

Science.gov (United States)

Song, Kai; Song, Yong; Zhao, Xiao-Ping; Shen, Hui; Wang, Meng; Yan, Ting-Lin; Liu, Ke; Shang, Zheng-Jun

2014-10-15

Most previous studies have linked cancer-macrophage fusion with tumor progression and metastasis. However, the characteristics of hybrid cells derived from oral cancer and endothelial cells and their involvement in cancer remained unknown. Double-immunofluorescent staining and fluorescent in situ hybridization (FISH) were performed to confirm spontaneous cell fusion between eGFP-labeled human umbilical vein endothelial cells (HUVECs) and RFP-labeled SCC9, and to detect the expression of vementin and cytokeratin 18 in the hybrids. The property of chemo-resistance of such hybrids was examined by TUNEL assay. The hybrid cells in xenografted tumor were identified by FISH and GFP/RFP dual-immunofluoresence staining. We showed that SCC9 cells spontaneously fused with cocultured endothelial cells, and the resultant hybrid cells maintained the division and proliferation activity after re-plating and thawing. Such hybrids expressed markers of both parental cells and became more resistant to chemotherapeutic drug cisplatin as compared to the parental SCC9 cells. Our in vivo data indicated that the hybrid cells contributed to tumor composition by using of immunostaining and FISH analysis, even though the hybrid cells and SCC9 cells were mixed with 1:10,000, according to the FACS data. Our study suggested that the fusion events between oral cancer and endothelial cells undergo nuclear fusion and acquire a new property of drug resistance and consequently enhanced survival potential. These experimental findings provide further supportive evidence for the theory that cell fusion is involved in cancer progression. Copyright © 2014 Elsevier Inc. All rights reserved.

Branchio-Oto-Renal Syndrome: Detection of EYA1 and SIX1 mutations in five out of six Danish families by combining linkage, sequencing and MLPA analyses

DEFF Research Database (Denmark)

Sanggard, Kirsten Marie; Rendtorff, Nanna Dahl; Kjaer, Klaus Wilbrandt

2007-01-01

The branchio-oto-renal (BOR) syndrome is an autosomal-dominant disorder characterized by hearing loss, branchial and renal anomalies. BOR is genetically heterogeneous and caused by mutations in EYA1 (8q13.3), SIX1 (14q23.1), SIX5 (19q13.3) and in an unidentified gene on 1q31. We examined six Danish...

Annual report of Naka Fusion Research Establishment for the period from April 1, 1993 to March 31, 1994

International Nuclear Information System (INIS)

Matoba, Tohru; Nakamura, Yukiharu; Matsuzaki, Yoshimi; Araki, Masanori; Yamane, Yoshifumi

1995-01-01

Research and development activities at Naka Fusion Research Establishment, JAERI, are reported for the period from April 1, 1993 to March 31, 1994. The main objectives of JT-60U experiments in FY1993 were to achieve and sustain high confinement regime with current drive. The JFT-2M experiments progressed in the systematic study of the plasma responses by applying an external helical field and also in the study of the boundary plasma with electric field or current in the scrape off layer (SOL) introduced by the divertor bias system. The study in Plasma Theory and Computation focused on the ion temperature gradient instability, the linear toroidal particle simulation, the MHD stability and the analyses of burning plasma. The progresses on DIII-D experiments were obtained in the studies of divertor radiation, cryopumping and VH-mode plasma. As for the fusion engineering research, further developments of a ceramic vacuum pump and a high-resolution quadrupole mass spectrometer (QMS) were made. A high energy H - beam of 400keV and 0.18A was produced with a current density of 13mA/cm 2 for 1s. Many efforts were made in developing the long pulse gyrotron and the high efficiency collector potential depression (CPD) gyrotron in the radio-frequency (RF) technology area. The main progress in the Tritium Systems Test Assembly (under US/Japan collaboration) was to demonstrate the plasma exhaust stream under non-steady tokamak operation. Heating experiments of the development 1m long divertor module for ITER were performed at a heat flux of 15MW/m 2 for 30sec. The R and D of the reactor structure were focused on the major components such as non-circular bellows, fail-safe first wall, etc.. The R and D of the blanket technology were focussed on the box structure for ITER shielding blanket and the out-of-reactor testing of ITER breeding blanket. (J.P.N.)

Laser fusion experiments, facilities and diagnostics at Lawrence Livermore Laboratory

International Nuclear Information System (INIS)

Ahlstrom, H.G.

1980-02-01

The progress of the LLL Laser Fusion Program to achieve high gain thermonuclear micro-explosions is discussed. Many experiments have been successfully performed and diagnosed using the large complex, 10-beam, 30 TW Shiva laser system. A 400 kJ design of the 20-beam Nova laser has been completed. The construction of the first phase of this facility has begun. New diagnostic instruments are described which provide one with new and improved resolution, information on laser absorption and scattering, thermal energy flow, suprathermal electrons and their effects, and final fuel conditions. Measurements were made on the absorption and Brillouin scattering for target irradiations at both 1.064 μm and 532 nm. These measurements confirm the expected increased absorption and reduced scattering at the shorter wavelength. Implosion experiments have been performed which have produced final fuel densities over the range of 10x to 100x liquid DT density

Spherical Nanoindentation Stress-Strain Measurements of BOR-60 14YWT-NFA1 Irradiated Tubes

Energy Technology Data Exchange (ETDEWEB)

Weaver, Jordan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Carvajal Nunez, Ursula [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Krumwiede, David [Univ. of California, Berkeley, CA (United States); Saleh, Tarik A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Hosemann, Peter [Univ. of California, Berkeley, CA (United States); Nelson, Andrew Thomas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Maloy, Stuart Andrew [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Mara, Nathan Allan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2017-09-28

Spherical nanoindentation stress-strain protocols were applied to characterize unirradiated and fast neutron irradiated nanostructured ferritic alloy (NFA) 14YWT and compared against Berkovich nanohardness and available tensile data. The predicted uniaxial yield strength from spherical, 100 and 5 micron radii, indentation yield strength measurements was 1100-1400 MPa which compares well with the predictions from Berkovich nanohardness, 1200 MPa, and available tensile data, ~1100 MPa. However, spherical indentation measurements predict an increase in the uniaxial yield strength of ~1 GPa while Berkovich nanohardness measurements predict an increase of only ~250 MPa. No tensile data exists on the irradiated condition. It is believed the difference in the predicted uniaxial yield strength between spherical and Berkovich nanoindentation are due to a low number of tests on the irradiated sample combined with the significant heterogeneity in the microstructure, the differences in sensitivity to sample preparation on the irradiated sample between the two indentation protocols , and/or in how strain localizes under the indenter with the possibility of dislocation channeling under Berkovich hardness indents leading to strain softening. Nanoindentation capabilities to test neutron irradiated samples in a radiological area were realized.

Experiments in cold fusion

International Nuclear Information System (INIS)

Palmer, E.P.

1986-01-01

The work of Steve Jones and others in muon-catalyzed cold fusion of deuterium and hydrogen suggests the possibility of such fusion catalyzed by ions, or combinations of atoms, or more-or-less free electrons in solid and liquid materials. A hint that this might occur naturally comes from the heat generated in volcanic action in subduction zones on the earth. It is questionable whether the potential energy of material raised to the height of a midocean ridge and falling to the depth of an ocean trench can produce the geothermal effects seen in the volcanoes of subduction zones. If the ridge, the trench, the plates, and the asthenosphere are merely visible effects of deeper density-gradient driven circulations, it is still uncertain that observed energy-concentration effects fit the models

Fusion research principles

CERN Document Server

Dolan, Thomas James

2013-01-01

Fusion Research, Volume I: Principles provides a general description of the methods and problems of fusion research. The book contains three main parts: Principles, Experiments, and Technology. The Principles part describes the conditions necessary for a fusion reaction, as well as the fundamentals of plasma confinement, heating, and diagnostics. The Experiments part details about forty plasma confinement schemes and experiments. The last part explores various engineering problems associated with reactor design, vacuum and magnet systems, materials, plasma purity, fueling, blankets, neutronics

FELIX experiments and computational needs for eddy current analysis of fusion reactors

International Nuclear Information System (INIS)

Turner, L.R.

1984-01-01

In a fusion reactor, changing magnetic fields are closely coupled to the electrically-conducting metal structure. This coupling is particularly pronounced in a tokamak reactor in which magnetic fields are used to confine, stabilize, drive, and heat the plasma. Electromagnetic effects in future fusion reactors will have far-reaching implications in the configuration, operation, and maintenance of the reactors. This paper describes the impact of eddy-current effects on future reactors, the requirements of computer codes for analyzing those effects, and the FELIX experiments which will provide needed data for code validation

Integral activation experiment of fusion reactor materials with d-Li neutrons up to 55 MeV

Energy Technology Data Exchange (ETDEWEB)

Maekawa, Fujio; Ikeda, Yujiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Moellendorff, Ulrich von [Forschungszentrum Karlsruhe, Karlsruhe (Germany); Wada, Masayuki [Business Automation Co., Ltd., Tokyo (Japan)

2000-03-01

An integral activation experiment of fusion reactor materials with a deuteron-lithium neutron source was performed. Since the maximum energy of neutrons produced was 55 MeV, the experiment with associated analysis was one of the first attempts for extending the energy range beyond 20 MeV. The following keywords represent the present study: d-Li neutrons, 55 MeV, dosimetry, SAND-II, spectrum adjustment, LA-150, MCNP, McDeLi, IFMIF, fusion reactor materials, integral activation experiment, low-activation, F82H, vanadium-alloy, IEAF, ALARA, and sequential charged particle reaction. (author)

Biochemistry and biophysics of HIV-1 gp41 - membrane interactions and implications for HIV-1 envelope protein mediated viral-cell fusion and fusion inhibitor design.

Science.gov (United States)

Cai, Lifeng; Gochin, Miriam; Liu, Keliang

2011-12-01

Human immunodeficiency virus type 1 (HIV-1), the pathogen of acquired immunodeficiency syndrome (AIDS), causes ~2 millions death every year and still defies an effective vaccine. HIV-1 infects host cells through envelope protein - mediated virus-cell fusion. The transmembrane subunit of envelope protein, gp41, is the molecular machinery which facilitates fusion. Its ectodomain contains several distinguishing functional domains, fusion peptide (FP), Nterminal heptad repeat (NHR), C-terminal heptad repeat (CHR) and membrane proximal extracellular region (MPER). During the fusion process, FP inserts into the host cell membrane, and an extended gp41 prehairpin conformation bridges the viral and cell membranes through MPER and FP respectively. Subsequent conformational change of the unstable prehairpin results in a coiled-coil 6-helix bundle (6HB) structure formed between NHR and CHR. The energetics of 6HB formation drives membrane apposition and fusion. Drugs targeting gp41 functional domains to prevent 6HB formation inhibit HIV-1 infection. T20 (enfuvirtide, Fuzeon) was approved by the US FDA in 2003 as the first fusion inhibitor. It is a 36-residue peptide from the gp41 CHR, and it inhibits 6HB formation by targeting NHR and lipids. Development of new fusion inhibitors, especially small molecule drugs, is encouraged to overcome the shortcomings of T20 as a peptide drug. Hydrophobic characteristics and membrane association are critical for gp41 function and mechanism of action. Research in gp41-membrane interactions, using peptides corresponding to specific functional domains, or constructs including several interactive domains, are reviewed here to get a better understanding of gp41 mediated virus-cell fusion that can inform or guide the design of new HIV-1 fusion inhibitors.

H-1NF: Australian national fusion plasma research facility

International Nuclear Information System (INIS)

Blackwell, B.D.; Borg, G.G.; Dewar, R.L.; Howard, J.; Gardner, H.J.; Rudakov, D.L.; Sharp, L.E.; Shats, M.G.; Warr, G.B.

1997-01-01

The H-1 heliac is a helical axis stellarator of moderate size and novel, flexible configuration. Since commissioning, H-1 has operated in quasi-continuous mode at low magnetic field. For higher fields ≤1T an ECRH heating system (28GHz, 200kW) has been installed under a collaborative agreement between ANU and NIFS. H-1 has recently been promoted to national facility status (H-1NF), which will include upgrades of the rf and ech heating systems to megawatt powers, and power supply and diagnostic and data system enhancements. This facilitates collaborative research locally (through the Australian Fusion Research Group consortium) and internationally. Results of a number of basic experiments in quasi-continuous mode are presented. (author)

Fusion: introduction

International Nuclear Information System (INIS)

Decreton, M.

2006-01-01

The article gives an overview and introduction to the activities of SCK-CEN's research programme on fusion. The decision to construct the ITER international nuclear fusion experiment in Cadarache is highlighted. A summary of the Belgian contributions to fusion research is given with particular emphasis on studies of radiation effects on diagnostics systems, radiation effects on remote handling sensing systems, fusion waste management and socio-economic studies

Highlights from e-EPS: Fusion experiment nears completion, nominations open for prize, and technology transfer group launched

CERN Multimedia

e-EPS News

2012-01-01

e-EPS News is a monthly addition to the CERN Bulletin line-up, showcasing articles from e-EPS – the European Physical Society newsletter – as part of a collaboration between the two publications.   Core of fusion experiment completed The last major part of the Wendelstein 7-X fusion experiment was installed on 21 December last year. The addition of the 14 tonne final part of the device – the lid of the thermally insulating outer shell – sees the completion of the ring-like base machine at the Greifswald branch of the Max Planck Institute of Plasma Physics, which will begin operation in 2014. Fusion research aims to draw energy from the fusion of atomic nuclei. To achieve this, hydrogen plasma must be superheated to temperatures above 100 million degrees, within the confines of a restricting magnetic field. The Wendelstein 7-X – which will be the largest fusion device of its type – will investigate the feasibility of such a power pl...

Antares facility for inertial-fusion experiments: status and plans

International Nuclear Information System (INIS)

Goldstone, P.D.; Allen, G.; Jansen, H.; Saxman, A.; Singer, S.; Thuot, M.

1982-01-01

Antares is a large, 30 to 40 kJ CO 2 laser system which will provide a base for experiments to determine the efficiency with which 10 μm light can be used to drive target implosions while maintaining an acceptable level of preheat. Construction of the facility is in the final stages and diagnostics for initial experiments are being designed and constructed with operations scheduled to begin early in FY-84. After an initial shakedown period, we expect to perform a series of measurements to determine the energy scaling of hot electron temperature and target coupling efficiency in selected set of targets including simple spheres. We also expect to continue experiments, now planned for Helios, to determine whether CO 2 -produced ions are appropriate for driving inertial fusion targets with acceptable efficiency (Helios experiments have demonstrated that as much as 40% of the incident light can be converted to fast ions). Details of these experiments, as well as plans for further experiments, are still being defined

Automated characterization of glass microspheres used for laser fusion experiments

International Nuclear Information System (INIS)

Tajima, Tsuyoshi; Norimatsu, Takayoshi; Izawa, Yasukazu; Yamanaka, Chiyoe.

1985-01-01

In laser fusion experiments glass microspheres of 100 to 1000 μm in diameter and 1 to 20 μm in wall thickness are most commonly used as fuel containers. The glass microspheres should be characterized precisely to meet stringent experimental requirements. Much time is consumed to characterize and select good quality spheres among thousands of spheres. We have developed an automated system to characterize and select glass microspheres. The system consists of charger, quadrupole rail, image processing and X-Y stage control with micro-computer. Total processing time primarily depends on the time required for image analysis, which should be compromised with the accuracy of characterization. The time for simple characterization requires about 10 sec. at present. (author)

Tritium depth profiling by AMS in carbon samples from fusion experiments

International Nuclear Information System (INIS)

Friedrich, M.; Pilz, W.; Sun, G.; Behrisch, R.; Garcia-Rosales, C.

2001-01-01

Tritium depth profiling measurements by accelerator mass spectrometry have been performed at a facility installed at the Rossendorf 3 MV Tandetron. In order to achieve an uniform erosion at the target surface inside of a commercial Cs ion sputtering source and to avoid edge effects, the samples were mechanically scanned inside of a commercial Cs sputter ion source. The sputtered negative ions were mass analysed by the injection magnet of the Tandetron. The tritium ions are counted after the acceleration with semiconductor detectors. Depth profiles have been measured for carbon samples which had been exposed to the plasma at the first wall of the Garching fusion experiment ASDEX-Upgrade and from the European fusion experiment JET, Culham/UK. A dedicated AMS facility with an air-insulated 100 kV tandem accelerator for depth profiling measurements at samples with high tritium concentration is under construction. First results of test operation are presented. (orig.)

Next-Step Spherical Torus Experiment and Spherical Torus Strategy in the Fusion Energy Development Path

International Nuclear Information System (INIS)

Ono, M.; Peng, M.; Kessel, C.; Neumeyer, C.; Schmidt, J.; Chrzanowski, J.; Darrow, D.; Grisham, L.; Heitzenroeder, P.; Jarboe, T.; Jun, C.; Kaye, S.; Menard, J.; Raman, R.; Stevenson, T.; Viola, M.; Wilson, J.; Woolley, R.; Zatz, I.

2003-01-01

A spherical torus (ST) fusion energy development path which is complementary to proposed tokamak burning plasma experiments such as ITER is described. The ST strategy focuses on a compact Component Test Facility (CTF) and higher performance advanced regimes leading to more attractive DEMO and Power Plant scale reactors. To provide the physics basis for the CTF an intermediate step needs to be taken which we refer to as the ''Next Step Spherical Torus'' (NSST) device and examine in some detail herein. NSST is a ''performance extension'' (PE) stage ST with the plasma current of 5-10 MA, R = 1.5 m, and Beta(sub)T less than or equal to 2.7 T with flexible physics capability. The mission of NSST is to: (1) provide a sufficient physics basis for the design of CTF, (2) explore advanced operating scenarios with high bootstrap current fraction/high performance regimes, which can then be utilized by CTF, DEMO, and Power Plants, and (3) contribute to the general plasma/fusion science of high beta toroidal plasmas. The NSST facility is designed to utilize the Tokamak Fusion Test Reactor (or similar) site to minimize the cost and time required for the design and construction

Recent progress in fusion gyrotron development

International Nuclear Information System (INIS)

Shively, J.F.; Stone, D.S.

1981-01-01

The gyrotron, a microwave tube capable of producing high power output at millimeter wavelengths, has recently found applications for electron cyclotron resonance heating of plasmas in controlled thermonuclear fusion reactor experiments. This paper describes work in progress to develop a gyrotron oscillator to deliver 200 kW CW at 60 GHz (/lambda/sub //. 5 mm). A pulsed oscillator is described which produced over 200 kw peak power. A CW oscillator is under construction. The latest experimental results are presented

Effect of Radiation Dosage on Efficiency of Chloroplast Transfer by Protoplast Fusion in Nicotiana

OpenAIRE

Menczel, László; Galiba, Gábor; Nagy, Ferenc; Maliga, Pál

1982-01-01

Chloroplasts of Nicotiana tabacum SR1 were transferred into Nicotiana plumbaginifolia by protoplast fusion. The protoplasts of the organelle donor were irradiated with different lethal doses using a 60Co source, to facilitate the elimination of their nuclei from the fusion products. After fusion induction, clones derived from fusion products and containing streptomycin-resistant N. tabacum SR1 chloroplasts were selected by their ability to green on a selective medium. When N. tabacum protopla...

Fusion measurements in light and medium mass heavy-ion reactions. Progress report, June 1, 1980-May 31, 1981

International Nuclear Information System (INIS)

Prosser, F.W.

1981-01-01

The data obtained for fusion residues from the 16 18 O + 24 26 Mg systems have been analyzed and are being compared to each other and to predictions from the fusion-evaporation code CASCADE. Analysis of data obtained for a small step excitation curve for the 16 O + 24 Mg system has been started to determine the possible presence of structure in the fusion cross section. Additional data for the fusion cross sections of these systems have been obtained at energies from 100 to 140 MeV at the ATLAS facility and are being analyzed. Initial measurements of the fusion-fission cross sections for 58 Ni beams, at energies up to 320 MeV on targets from 116 Sn to 170 Yb have been made. Analysis is in progress and additional experiments are planned. A collaboration is planned at Notre Dame for experiments to determine the entry line for fusion in the 12 C + 16 O system, both for the interest in this system and for preparation for additional experiments at higher energies at Michigan State when the new facility there becomes available. These experiments should lead to information about the importance of incomplete fusion in this system. Experiments to test the limitation on fusion cross sections predicted by the rotating liquid drop model are planned as higher energies become available at ATLAS and MSU

Some experiments on cold fusion by deuterium hydrogen gas infusion in titanium metal alloy

International Nuclear Information System (INIS)

Mestnik Filho, J.; Geraldo, L.P.; Pugliese, R.; Saxena, R.N.; Morato, S.P.; Fulfaro, R.

1990-05-01

New results on cold fusion are reported where three different experimental situations have been tried: a) deuterium gas loaded titanium; b) deuterium gas loaded Ti 0.8 Zr 0.2 CrMn alloy and c) titanium and the Ti 0.8 Zr 0.2 CrMn alloy loaded with a mixture of deuterium and hydrogen gases. With these experiments, new thermodynamical non equilibrium conditions were achieved and the possibility of cold fusion between protons and deuterons was also tested. Three independent neutron detectors and one NaI(Tl) were utilized. Despite some large values reported in the literature for the fusion rate, an upper limit of only 8 x 10 -24 fusions/sper deuterium pair or per deuterium-hydrogen pair was determined within the attained accuracy. (author) [pt

Flow cytometric chemosensitivity assay using JC‑1, a sensor of mitochondrial transmembrane potential, in acute leukemia.

Science.gov (United States)

Yokosuka, Tomoko; Goto, Hiroaki; Fujii, Hisaki; Naruto, Takuya; Takeuchi, Masanobu; Tanoshima, Reo; Kato, Hiromi; Yanagimachi, Masakatsu; Kajiwara, Ryosuke; Yokota, Shumpei

2013-12-01

The purpose of the study is to establish a simple and relatively inexpensive flow cytometric chemosensitivity assay (FCCA) for leukemia to distinguish leukemic blasts from normal leukocytes in clinical samples. We first examined whether the FCCA with the mitochondrial membrane depolarization sensor, 5, 50, 6, 60-tetrachloro-1, 10, 3, 30 tetraethyl benzimidazolo carbocyanine iodide (JC-1), could detect drug-induced apoptosis as the conventional FCCA by annexin V/7-AAD detection did and whether it was applicable in the clinical samples. Second, we compared the results of the FCCA for prednisolone (PSL) with clinical PSL response in 18 acute lymphoblastic leukemia (ALL) patients to evaluate the reliability of the JC-1 FCCA. Finally, we performed the JC-1 FCCA for bortezomib (Bor) in 25 ALL or 11 acute myeloid leukemia (AML) samples as the example of the clinical application of the FCCA. In ALL cells, the results of the JC-1 FCCA for nine anticancer drugs were well correlated with those of the conventional FCCA using anti-annexin V antibody (P < 0.001). In the clinical samples from 18 children with ALL, the results of the JC-1 FCCA for PSL were significantly correlated with the clinical PSL response (P = 0.005). In ALL samples, the sensitivity for Bor was found to be significantly correlated with the sensitivity for PSL (P = 0.005). In AML samples, the Bor sensitivity was strongly correlated with the cytarabine sensitivity (P = 0.0003). This study showed the reliability of a relatively simple and the FCCA using JC-1, and the possibility for the further clinical application.

Once more about cold nuclear fusion

International Nuclear Information System (INIS)

Brudanin, V.B.; Bystritsky, V.M.; Egorov, V.G.

1989-01-01

The results of the experiments on the search for cold nuclear d-d fusion in chemically pure titanium are given both for electrolysis of heavy water D 2 O and for titanium saturation with gaseous deuterium. The saturation took place at the temperature of 77K and pressure of 50 and 150 atm. A round of experiments with temperature varying from 1 to 600 atm was carried out. The limiting values of the partial rate of the nuclear reaction of d-d fusion with neutron production were obtained per deuteron (at the 95% confidence level): λ f ≤4x10 -25 s -1 (experiment with electrolysis), λ f ≤7x10 -28 s -1 (experiment with gaseous deuterium). 7 refs.; 5 figs.; 2 tabs

Annual report on major results and progress of Naka Fusion Research Establishment of JAERI from April 1 to September 30, 2005 and Fusion Research and Development Directorate of JAEA from October 1, 2005 to March 31, 2006

International Nuclear Information System (INIS)

Yoshida, Hidetoshi; Oasa, Kazumi; Hayashi, Takao; Nakamura, Hiroo; Ogawa, Hiroaki

2006-09-01

This annual report provides an overview of major results and progress on research and development (R and D) activities at Naka Fusion Research Establishment of Japan Atomic Energy Research Institute (JAERI) during the period from April 1 to September 30, 2005 and at Fusion Research and Development Directorate of Japan Atomic Energy Agency (JAEA) from October 1, 2005 to March 31, 2006, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In JT-60, ferritic steel tiles (FSTs) were installed inside the vacuum vessel of JT-60U to reduce the toroidal field ripple. After the installation of FSTs, a high normalized beta plasma at β N ∼2.3 was sustained for 28.6s with ELMy H-mode confinement as required for an ITER hybrid operation scenario. National Centralized Tokamak was placed as the ITER satellite tokamak in collaboration with the EU fusion community, and the facility design was modified strongly in support of ITER. In theoretical and analytical researches, studies on H-mode confinement, ITB in reversed shear plasmas, aspect ratio effects on external MHD modes and magnetic island evolution in a rotating plasma were progressed. Progress was also made in the NEXT project in which the behaviors of collisionless MHD modes and the dynamics of zonal flows were simulated. In fusion reactor technologies, R and Ds for ITER and fusion DEMO plants have been carried out. For ITER, a steady state operation of the 170GHz gyrotron up to 1000 s with 0.2 MW was demonstrated. Also current density of the neutral beam injector has been extended to 134A/m 2 at 0.75MeV. In the ITER Test Blanket Module (TBM), designs of Water and Helium Cooled Solid Breeder TBMs and R and Ds of tritium breeder/multiplier materials were progressed. Tritium processing technology for breeding blankets was also progressed. For the DEMO reactors, high temperature superconductor such as Bi2212 has been examined. In plasma facing

Third year progress report on the co-ordinated research programme on signal processing techniques for sodium boiling noise detection

International Nuclear Information System (INIS)

Singh, O.P.; Prabhakar, R.; Reddy, C.P.; Vyjayanthi, R.K.; Srinivasan, G.S.

1989-01-01

The present paper deals with investigations of acoustic signals from a boiling experiment performed on the BOR 60 reactor in the USSR. Signals have been analysed in frequency as well as in time domain. Signal characteristics successfully used to detect the boiling process have been found in time domain. A proposal for in-service boiling monitoring by acoustic means is described. (author). 1 ref., 13 figs, 4 tabs

Present status of fusion researches in USA, 4

International Nuclear Information System (INIS)

Yoshikawa, Shoichi; Okabayashi, Michio

1983-01-01

25 years have elapsed since nuclear fusion was published at the second Geneva conference in 1958. During this period, the Plasma Physics Laboratory of Princeton University has achieved the central role in the research on toroidal system nuclear fusion devices. Also the experiment of the large tokamak TFTR started from December, 1982, recorded the longest containment time of 200 ms as the initial data, and toroidal devices look to approach one step close to the scientific verification experiment (Q = 1) of reactors. In the PPPL, in order to perfect the basis required for the realization of nuclear fusion reactors, the experimental and theoretical developments have been carried out. Plasma containment experiment has been advanced successively from stellarater through internal conductor type to tokamak, and in plasma heating, ion cyclotron heating, fast neutral particle injection heating and low region hybrid heating were successfully carried out. As the experimental apparatuses, that for poloidal divertor experiment, Princeton large torus, tokamak fusion test reactor (TFTR) and S-1 spheromak are described. From the theories developed recently, bean type tokamak, heliac-stellarator and nuclear fusion reaction utilizing μ-mesons and nuclear spin are explained. (Kako, I.)

Exploring dissipative processes at high angular momentum in 58Ni+60Ni reactions

Directory of Open Access Journals (Sweden)

Williams E.

2016-01-01

Full Text Available Current coupled channels (CC models treat fusion as a coherent quantum-mechanical process, in which coupling between the collective states of the colliding nuclei influences the probability of fusion in near-barrier reactions. While CC models have been used to successfully describe many experimental fusion barrier distribution (BD measurements, the CC approach has failed in the notable case of 16O+208Pb. The reason for this is poorly understood; however, it has been postulated that dissipative processes may play a role. Traditional BD experiments can only probe the physics of fusion for collisions at the top of the Coulomb barrier (L = 0ħ. In this work, we will present results using a novel method of probing dissipative processes inside the Coulomb barrier. The method exploits the predicted sharp onset of fission at L ~ 60ħ for reactions forming compound nuclei with A < 160. Using the ANU’s 14UD tandem accelerator and CUBE spectrometer, reaction outcomes have been measured for the 58Ni+60Ni reaction at a range of energies, in order to explore dissipative processes at high angular momentum. In this reaction, deep inelastic processes have been found to set in before the onset fission at high angular momentum following fusion. The results will be discussed in relation to the need for a dynamical model of fusion.

Power system for tokamak fusion experiments. Motor generator with flywheel effect

International Nuclear Information System (INIS)

Miyachi, Kengo

1997-01-01

JT-60 requires an enormous electric power pulse about 1,300 MVA periodically for its plasma initiation, containment and heating. JT-60 could not receive all electric power from a commercial line for plasma experiment except about 160 MVA because the 275 kV commercial line has some limitations. Therefore JT-60 needs huge electric power sources. The power supply system of JT-60 has 3 motor generators (MG). The total capacity of MG is 1,115 MVA that consists of a toroidal MG (TMG), poloidal MG (PMG) and Heating power supply MG (HMG), and each MG has a huge flywheel effect. For example, TMG has a 4.02 GJ energy yield that consists of 6 disk flywheel. The total weight of flywheel of TMG is 650 ton. This report describes the structure, operating system, and maintenance history of 3 types of MG. (author)

Experience on Russian military origin plutonium conversion into fast reactor nuclear fuel

International Nuclear Information System (INIS)

Grachev, A.F.; Skiba, O.V.; Bychkov, A.V.; Mayorshin, A.A.; Kisly, V.A.; Bobrov, D.A.; Osipenko, A.G.; Babikov, L.G.; Mishinev, V.B.

2001-01-01

According to the Concept of Russian Minatom on military plutonium excess utilization, the State Scientific Center of Russian Federation ''Research Institute of Atomic Reactors'' (Dimitrovgrad) has begun study on possibility of technological processing of the metal military plutonium into MOX fuel. The Program and the stages of its realization are submitted in the paper. During 1998-2000 the first stage of the Program was fulfilled and 50 kg of military origin metallic plutonium was converted to MOX fuel for the BOR-60 and BN-600 reactor. The plutonium conversion into MOX fuel is carried out under the original technology developed by SSC RIAR. It includes pyro-electrochemical process for production of fuel on the domestic equipment with the subsequent fuel pins manufacturing for the fast reactors by the vibro-packing method. The produced MOX fuel is purified from alloy additives (Ga) and corresponds to the vibro-packed fuel standard for fast reactors. The fuel pins manufacturing for BOR-60 and BN-600 reactors are carried out by the vibro-packing method on a standard procedure, which is used in SSC RIAR more than 20 years. (author)

Numerical analysis of gas puff modulation experiment on JT-60U

International Nuclear Information System (INIS)

Nagashima, Keisuke; Sakasai, Akira

1992-03-01

In tokamak transport physics, source modulation experiments are one of the most effective methods. For an analysis of these modulation experiments, a simple numerical method was developed to solve the general transport equations. This method was applied to gas puff modulation experiments on JT-60U. From the comparison between the measured and calculated density perturbations, it was found that the particle diffusion coefficient is about 0.8 m 2 /sec in the edge region and 0.1-0.2 m 2 /sec in the central region. (author)

Membrane fusion and exocytosis.

Science.gov (United States)

Jahn, R; Südhof, T C

1999-01-01

Membrane fusion involves the merger of two phospholipid bilayers in an aqueous environment. In artificial lipid bilayers, fusion proceeds by means of defined transition states, including hourglass-shaped intermediates in which the proximal leaflets of the fusing membranes are merged whereas the distal leaflets are separate (fusion stalk), followed by the reversible opening of small aqueous fusion pores. Fusion of biological membranes requires the action of specific fusion proteins. Best understood are the viral fusion proteins that are responsible for merging the viral with the host cell membrane during infection. These proteins undergo spontaneous and dramatic conformational changes upon activation. In the case of the paradigmatic fusion proteins of the influenza virus and of the human immunodeficiency virus, an amphiphilic fusion peptide is inserted into the target membrane. The protein then reorients itself, thus forcing the fusing membranes together and inducing lipid mixing. Fusion of intracellular membranes in eukaryotic cells involves several protein families including SNAREs, Rab proteins, and Sec1/Munc-18 related proteins (SM-proteins). SNAREs form a novel superfamily of small and mostly membrane-anchored proteins that share a common motif of about 60 amino acids (SNARE motif). SNAREs reversibly assemble into tightly packed helical bundles, the core complexes. Assembly is thought to pull the fusing membranes closely together, thus inducing fusion. SM-proteins comprise a family of soluble proteins that bind to certain types of SNAREs and prevent the formation of core complexes. Rab proteins are GTPases that undergo highly regulated GTP-GDP cycles. In their GTP form, they interact with specific proteins, the effector proteins. Recent evidence suggests that Rab proteins function in the initial membrane contact connecting the fusing membranes but are not involved in the fusion reaction itself.

Mitochondrial fusion is increased by the nuclear coactivator PGC-1beta.

Directory of Open Access Journals (Sweden)

Marc Liesa

Full Text Available There is no evidence to date on whether transcriptional regulators are able to shift the balance between mitochondrial fusion and fission events through selective control of gene expression.Here, we demonstrate that reduced mitochondrial size observed in knock-out mice for the transcriptional regulator PGC-1beta is associated with a selective reduction in Mitofusin 2 (Mfn2 expression, a mitochondrial fusion protein. This decrease in Mfn2 is specific since expression of the remaining components of mitochondrial fusion and fission machinery were not affected. Furthermore, PGC-1beta increases mitochondrial fusion and elongates mitochondrial tubules. This PGC-1beta-induced elongation specifically requires Mfn2 as this process is absent in Mfn2-ablated cells. Finally, we show that PGC-1beta increases Mfn2 promoter activity and transcription by coactivating the nuclear receptor Estrogen Related Receptor alpha (ERRalpha.Taken together, our data reveal a novel mechanism by which mammalian cells control mitochondrial fusion. In addition, we describe a novel role of PGC-1beta in mitochondrial physiology, namely the control of mitochondrial fusion mainly through Mfn2.

Analysis of copper losses throughout weak acid effluent flows generated during off-gas treatment in the New Copper Smelter RTB Bor

Directory of Open Access Journals (Sweden)

Dragana Ivšić-Bajčeta

2013-09-01

Full Text Available The previous inadequate treatment of off-gas in RTB Bor in Serbia has resulted in serious pollution of the environment and the possibly high losses of copper through the effluent flows. The project of New Copper Smelter RTB Bor, besides the new flash smelting furnace (FSF and the reconstruction of Pierce-Smith converter (PSC, includes more effective effluent treatment. Paper presents an analysis of the new FSF and PSC off-gas treatment, determination of copper losses throughout generated wastewaters and discussion of its possible valorization. Assumptions about the solubility of metals phases present in the FSF and PSC off-gas, obtained by the treatment process simulation, were compared with the leaching results of flue dusts. Determined wastewaters characteristics indicate that the PSC flow is significantly richer in copper, mostly present in insoluble metallic/sulfide form, while the FSF flow has low concentration of copper in the form of completely soluble oxide/sulfate. The possible scenario for the copper valorization, considering arsenic and lead as limiting factors, is the separation of the FSF and PSC flows, return of the metallic/sulfide solid phase to the smelting process and recovery from the sulfate/oxide liquid phase.

Fusion, magnetic confinement

International Nuclear Information System (INIS)

Berk, H.L.

1992-01-01

An overview is presented of the principles of magnetic confinement of plasmas for the purpose of achieving controlled fusion conditions. Sec. 1 discusses the different nuclear fusion reactions which can be exploited in prospective fusion reactors and explains why special technologies need to be developed for the supply of tritium or 3 He, the probable fuels. In Sec. 2 the Lawson condition, a criterion that is a measure of the quality of confinement relative to achieving fusion conditions, is explained. In Sec. 3 fluid equations are used to describe plasma confinement. Specific confinement configurations are considered. In Sec. 4 the orbits of particle sin magneti and electric fields are discussed. In Sec. 5 stability considerations are discussed. It is noted that confinement systems usually need to satisfy stability constraints imposed by ideal magnetohydrodynamic (MHD) theory. The paper culminates with a summary of experimental progress in magnetic confinement. Present experiments in tokamaks have reached the point that the conditions necessary to achieve fusion are being satisfied

Lateral Transpsoas Fusion: Indications and Outcomes

Directory of Open Access Journals (Sweden)

Vishal C. Patel

2012-01-01

Full Text Available Spinal fusion historically has been used extensively, and, recently, the lateral transpsoas approach to the thoracic and lumbar spine has become an increasingly common method to achieve fusion. Recent literature on this approach has elucidated its advantage over more traditional anterior and posterior approaches, which include a smaller tissue dissection, potentially lower blood loss, no need for an access surgeon, and a shorter hospital stay. Indications for the procedure have now expanded to include degenerative disc disease, spinal stenosis, degenerative scoliosis, nonunion, trauma, infection, and low-grade spondylolisthesis. Lateral interbody fusion has a similar if not lower rate of complications compared to traditional anterior and posterior approaches to interbody fusion. However, lateral interbody fusion has unique complications that include transient neurologic symptoms, motor deficits, and neural injuries that range from 1 to 60% in the literature. Additional studies are required to further evaluate and monitor the short- and long-term safety, efficacy, outcomes, and complications of lateral transpsoas procedures.

International bulletin on atomic and molecular data for fusion. No. 60

International Nuclear Information System (INIS)

Stephens, J.A.; Bannister, M.E.; Delcroix, J.L.; Fuhr, J.

2001-06-01

This bulletin comprises updated atomic and molecular data for fusion. It includes the Atomic and Molecular Data Information System (AMDIS) of the IAEA. It contains two parts: a bibliographic database for atomic and molecular data for fusion research, and numerical databases of recommended and evaluated atomic, molecular and plasma-surface interaction data. The indexed papers are also listed separately for structure and spectra, atomic and molecular collisions, and surface interactions

Decay heat experiment and validation of calculation code systems for fusion reactor

Energy Technology Data Exchange (ETDEWEB)

Maekawa, Fujio; Ikeda, Yujiro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment; Wada, Masayuki

1999-10-01

Although accurate estimation of decay heat value is essential for safety analyses of fusion reactors against loss of coolant accidents and so on, no experimental work has been devoted to validating the estimation. Hence, a decay heat measurement experiment was performed as a task (T-339) of ITER/EDA. A new detector, the Whole Energy Absorption Spectrometer (WEAS), was developed for accurate and efficient measurements of decay heat. Decay heat produced in the thirty-two sample materials which were irradiated by 14-MeV neutrons at FNS/JAERI were measured with WEAS for a wide cooling time period from 1 min to 400 days. The data presently obtained were the first experimental decay heat data in the field of fusion. Validity of decay heat calculation codes of ACT4 and CINAC-V4, activation cross section libraries of FENDL/A-2.0 and JENDL Activation File, and decay data was investigated through analyses of the experiment. As a result, several points that should be modified were found in the codes and data. After solving the problems, it was demonstrated that decay heat valued calculated for most of samples were in good agreement with the experimental data. Especially for stainless steel 316 and copper, which were important materials for ITER, decay heat could be predicted with accuracy of {+-}10%. (author)

Decay heat experiment and validation of calculation code systems for fusion reactor

International Nuclear Information System (INIS)

Maekawa, Fujio; Ikeda, Yujiro; Wada, Masayuki

1999-10-01

Although accurate estimation of decay heat value is essential for safety analyses of fusion reactors against loss of coolant accidents and so on, no experimental work has been devoted to validating the estimation. Hence, a decay heat measurement experiment was performed as a task (T-339) of ITER/EDA. A new detector, the Whole Energy Absorption Spectrometer (WEAS), was developed for accurate and efficient measurements of decay heat. Decay heat produced in the thirty-two sample materials which were irradiated by 14-MeV neutrons at FNS/JAERI were measured with WEAS for a wide cooling time period from 1 min to 400 days. The data presently obtained were the first experimental decay heat data in the field of fusion. Validity of decay heat calculation codes of ACT4 and CINAC-V4, activation cross section libraries of FENDL/A-2.0 and JENDL Activation File, and decay data was investigated through analyses of the experiment. As a result, several points that should be modified were found in the codes and data. After solving the problems, it was demonstrated that decay heat valued calculated for most of samples were in good agreement with the experimental data. Especially for stainless steel 316 and copper, which were important materials for ITER, decay heat could be predicted with accuracy of ±10%. (author)

Particle beam fusion progress report, January-June 1980

International Nuclear Information System (INIS)

1981-05-01

An overview and technical summaries are given for research progress in each of the following general areas: (1) fusion target studies; (2) target experiments; (3) particle beam source theory; (4) diagnostics development; (5) particle beam experiments; (6) pulsed power research and development; (7) pulse power application; and (8) Electron Beam Fusion Accelerator project

Technology of mirror machines: LLL facilities for magnetic mirror fusion experiments

International Nuclear Information System (INIS)

Batzer, T.H.

1977-01-01

Significant progress in plasma confinement and temperature has been achieved in the 2XIIB facility at Livermore. These encouraging results, and their theoretical corroboration, have provided a firm basis for the design of a new generation of magnetic mirror experiments, adding support to the mirror concept of a fusion reactor. Two new mirror experiments have been proposed to succeed the currently operating 2XIIB facility. The first of these called TMX (Tandem Mirror Experiment) has been approved and is currently under construction. TMX is designed to utilize the intrinsic positive plasma potential of two strong, and relatively small, minimum B mirror cells to enhance the confinement of a much larger, magnetically weaker, centrally-located mirror cell. The second facility, MFTF (Mirror Fusion Test Facility), is currently in preliminary design with line item approval anticipated for FY 78. MFTF is designed primarily to exploit the experimental and theoretical results derived from 2XIIB. Beyond that, MFTF will develop the technology for the transition from the present small mirror experiments to large steady-state devices such as the mirror FERF/FTR. The sheer magnitude of the plasma volume, magnetic field, neutral beam power, and vacuum pumping capacity, particularly in the case of MFTF, has placed new and exciting demands on engineering technology. An engineering overview of MFTF, TMX, and associated MFE activities at Livermore will be presented

Neutronic analysis of fusion tokamak devices by PHITS

International Nuclear Information System (INIS)

Sukegawa, Atsuhiko M.; Takiyoshi, Kouji; Amano, Toshio; Kawasaki, Hiromitsu; Okuno, Koichi

2011-01-01

A complete 3D neutronic analysis by PHITS (Particle and Heavy Ion Transport code System) has been performed for fusion tokamak devices such as JT-60U device and JT-60 Superconducting tokamak device (JT-60 Super Advanced). The mono-energetic neutrons (E n =2.45 MeV) of the DD fusion devices are used for the neutron source in the analysis. The visual neutron flux distribution for the estimation of the port streaming and the dose rate around the fusion tokamak devices has been calculated by the PHITS. The PHITS analysis makes it clear that the effect of the port streaming of superconducting fusion tokamak device with the cryostat is crucial and the calculated neutron spectrum results by PHITS agree with the MCNP-4C2 results. (author)

Phase-IIC experiments of the JAERI/USDOE collaborative program on fusion blanket neutronics

International Nuclear Information System (INIS)

Oyama, Yukio

1992-12-01

Neutronics experiments on two types of heterogeneous blankets have been performed as the Phase-IIC experiment of JAERI/USDOE collaborative program on fusion blanket neutronics. The experimental system was used in the same geometry as the previous Phase-IIA series which was a closed geometry using neutron source enclosure of lithium carbonate. The heterogeneous blankets selected here are the beryllium edge-on and the water coolant channel assemblies. In the former the beryllium and lithium-oxide layers are piled up alternately in the front part of test blanket. In the latter, the three simulated water cooling channels are settled in the Li 2 O blanket. These are producing steep gradient of neutron flux around material boundary. The calculation accuracy and measurement method for these features is a key of interest in the experiments. The measurements were performed for tritium production rate and the other nuclear parameters as well as the previous experiments. This report describes the experimental detail and the results enough to use for the benchmark data for testing the data and method of design calculation of fusion reactors. (author)

(Fusion energy research)

Energy Technology Data Exchange (ETDEWEB)

Phillips, C.A. (ed.)

1988-01-01

This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer.

[Fusion energy research

International Nuclear Information System (INIS)

Phillips, C.A.

1988-01-01

This report discusses the following topics: principal parameters achieved in experimental devices (FY88); tokamak fusion test reactor; Princeton beta Experiment-Modification; S-1 Spheromak; current drive experiment; x-ray laser studies; spacecraft glow experiment; plasma deposition and etching of thin films; theoretical plasma; tokamak modeling; compact ignition tokamak; international thermonuclear experimental reactor; Engineering Department; Project Planning and Safety Office; quality assurance and reliability; and technology transfer

Present status of the EPFL (Swiss) fusion-fission experiment 'LOTUS'

International Nuclear Information System (INIS)

Haldy, P.A.; Frueh, R.; Ligou, J.; Schneeberger, J.P.; Kumar, A.

1984-01-01

The present status of the LOTUS project - a fusion-fission hybrid research facility under construction at the Ecole Polytechnique Federale de Lausanne (EPFL) Switzerland - is presented. Emphasis is places on the description of the facility and on the design studies of an initial blanket of the ''fission-suppressed'' type. The LOTUS facility consists of a parallelepiped-shaped blanket, occupying roughly a volume of 1 m 3 , driven by a sealed 14 MeV (D,T) neutron generator with a rated source strength of 5x10 12 n/s. The experiment is housed in a massive concrete shielding of 220 cm thick walls, which leaves an experimental test chamber of 360 cm by 240 cm lateral dimensions and a height of 300 cm. (orig.) [de

Operation of the tokamak fusion test reactor tritium systems during initial tritium experiments

International Nuclear Information System (INIS)

Anderson, J.L.; Gentile, C.; Kalish, M.; Kamperschroer, J.; Kozub, T.; LaMarche, P.; Murray, H.; Nagy, A.; Raftopoulos, S.; Rossmassler, R.; Sissingh, R.; Swanson, J.; Tulipano, F.; Viola, M.; Voorhees, D.; Walters, R.T.

1995-01-01

The high power D-T experiments on the tokamak fusion test reactor (TFTR) at the Princeton Plasma Physics Laboratory commenced in November 1993. During initial operation of the tritium systems a number of start-up problems surfaced and had to be corrected. These were corrected through a series of system modifications and upgrades and by repair of failed or inadequate components. Even as these operational concerns were being addressed, the tritium systems continued to support D-T operations on the tokamak. During the first six months of D-T operations more than 107kCi of tritium were processed successfully by the tritium systems. D-T experiments conducted at TFTR during this period provided significant new data. Fusion power in excess of 9MW was achieved in May 1994. This paper describes some of the early start-up issues, and reports on the operation of the tritium system and the tritium tracking and accounting system during the early phase of TFTR D-T experiments. (orig.)

Knockdown of MAP4 and DNAL1 produces a post-fusion and pre-nuclear translocation impairment in HIV-1 replication

International Nuclear Information System (INIS)

Gallo, Daniel E.; Hope, Thomas J.

2012-01-01

DNAL1 and MAP4 are both microtubule-associated proteins. These proteins were identified as HIV-1 dependency factors in a screen with wild-type HIV-1. In this study we demonstrate that knockdown using DNAL1 and MAP4 siRNAs and shRNAs inhibits HIV-1 infection regardless of envelope. Using a fusion assay, we show that DNAL1 and MAP4 do not impact fusion. By assaying for late reverse transcripts and 2-LTR circles, we show that DNAL1 and MAP4 inhibit both by approximately 50%. These results demonstrate that DNAL1 and MAP4 impact reverse transcription but not nuclear translocation. DNAL1 and MAP4 knockdown cells do not display cytoskeletal defects. Together these experiments indicate that DNAL1 and MAP4 may exert their functions in the HIV life cycle at reverse transcription, prior to nuclear translocation.

Tokamak Fusion Core Experiment maintenance study

International Nuclear Information System (INIS)

Snyder, A.M.; Watts, K.D.

1985-01-01

The recently completed Tokamak Fusion Core Experiment (TFCX) design project was carried out to investigate potential next generation tokamak concepts. An important aspect of this project was the early development and incorporation of remote maintainability throughout the design process. This early coordination and incorporation of maintenance aspects to the design of the device and facilities would assure that the machine could ultimately be maintained and repaired in an efficient and cost effective manner. To meet this end, a rigorously formatted engineering trade study was performed to determine the preferred configuration for the TFCX reactor based primarily on maintenance requirements. The study indicated that the preferred design was one with an external vacuum vessel and torrodial field coils that could be removed via a simple radial motion. The trade study is presented and the preferred TFCX configuration is described

Safety analysis and evaluation methodology for fusion systems

International Nuclear Information System (INIS)

Fujii-e, Y.; Kozawa, Y.; Namba, C.

1987-03-01

Fusion systems which are under development as future energy systems have reached a stage that the break even is expected to be realized in the near future. It is desirable to demonstrate that fusion systems are well acceptable to the societal environment. There are three crucial viewpoints to measure the acceptability, that is, technological feasibility, economy and safety. These three points have close interrelation. The safety problem is more important since three large scale tokamaks, JET, TFTR and JT-60, start experiment, and tritium will be introduced into some of them as the fusion fuel. It is desirable to establish a methodology to resolve the safety-related issues in harmony with the technological evolution. The promising fusion system toward reactors is not yet settled. This study has the objective to develop and adequate methodology which promotes the safety design of general fusion systems and to present a basis for proposing the R and D themes and establishing the data base. A framework of the methodology, the understanding and modeling of fusion systems, the principle of ensuring safety, the safety analysis based on the function and the application of the methodology are discussed. As the result of this study, the methodology for the safety analysis and evaluation of fusion systems was developed. New idea and approach were presented in the course of the methodology development. (Kako, I.)

Modelling third harmonic ion cyclotron acceleration of deuterium beams for JET fusion product studies experiments

DEFF Research Database (Denmark)

Schneider, M.; Johnson, T.; Dumont, R.

2016-01-01

Recent JET experiments have been dedicated to the studies of fusion reactions between deuterium (D) and Helium-3 (3He) ions using neutral beam injection (NBI) in synergy with third harmonic ion cyclotron radio-frequency heating (ICRH) of the beam. This scenario generates a fast ion deuterium tail...... enhancing DD and D3He fusion reactions. Modelling and measuring the fast deuterium tail accurately is essential for quantifying the fusion products. This paper presents the modelling of the D distribution function resulting from the NBI+ICRF heating scheme, reinforced by a comparison with dedicated JET fast...

HIV-1 gp41 Fusion Intermediate: A Target for HIV Therapeutics

Directory of Open Access Journals (Sweden)

Chungen Pan

2010-02-01

Full Text Available Human immunodeficiency virus (HIV-1 infection is initiated by the binding of gp120 envelope glyco-protein to its cell receptor (CD4 and a coreceptor (CXCR4 or CCR5, followed by a series of conformational changes in the gp41 transmembrane subunit. These changes include insertion of fusion peptide into the target cell membrane and association of C-heptad repeat (CHR peptide with the N-heptad repeat (NHR trimer, a pre-hairpin fusion intermediate. A stable six-helix bundle core is then formed, bringing the viral envelope and target cell membrane into close proximity for fusion. Peptides derived from the CHR region, such as T20 and C34, inhibit HIV-1 fusion by interacting with the gp41 fusion intermediate. A number of anti-HIV-1 peptides and small molecule compounds targeting the gp41 NHR-trimer have been identified. By combining HIV fusion/entry inhibitors targeting different sites in the gp41 fusion intermediate, a potent synergistic effect takes place, resulting in a potential new therapeutic strategy for the HIV infection/AIDS. Here, we present an overview of the current development of anti-HIV drugs, particularly those targeting the gp41 fusion intermediate.

Preparations for deuterium tritium experiments on the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Hawryluk, R.J.; Adler, H.; Alling, P.; Ancher, C.; Anderson, H.; Anderson, J.W.; Arunasalam, V.; Ascione, G.; Ashcroft, D.; Barnes, G.

1994-04-01

The final hardware modifications for tritium operation have been completed for the Tokamak Fusion Test Reactor (TFTR). These activities include preparation of the tritium gas handling system, installation of additional neutron shielding, conversion of the toroidal field coil cooling system from water to a Fluorinet trademark system, modification of the vacuum system to handle tritium, preparation and testing of the neutral beam system for tritium operation and a final deuterium-deuterium (D-D) run to simulate expected deuterium-tritium (D-T) operation. Testing of the tritium system with low concentration tritium has successfully begun. Simulation of trace and high power D-T experiments using D-D have been performed. The physics objectives of D-T operation are production of ∼ 10 megawatts (MW) of fusion power, evaluation of confinement and heating in deuterium-tritium plasmas, evaluation of α-particle heating of electrons, and collective effects driven by alpha particles and testing of diagnostics for confined α-particles. Experimental results and theoretical modeling in support of the D-T experiments are reviewed

A spheromak ignition experiment reusing Mirror Fusion Test Facility (MFTF) equipment

International Nuclear Information System (INIS)

Fowler, T.K.

1993-01-01

Based on available experimental results and theory, a scenario is presented to achieve ohmic ignition in a spheromak by slow (∼ 10 sec.) helicity injection using power from the Mirror Fusion Test Facility (MFTF) substation. Some of the other parts needed (vacuum vessel, coils, power supplies, pumps, shielded building space) might also be obtained from MFTF or other salvage, as well as some components needed for intermediate experiments for additional verification of the concept (especially confinement scaling). The proposed ignition experiment would serve as proof-of-principle for the spheromak DT fusion reactor design published by Hagenson and Krakowski, with a nuclear island cost about ten times less than a tokamak of comparable power. Designs at even higher power density and lower cost might be possible using Christofilos' concept of a liquid lithium blanket. Since all structures would be protected from neutrons by the lithium blanket and the tritium inventory can be reduced by continuous removal from the liquid blanket, environmental and safety characteristics appear to be favorable

Triton burnup study using scintillating fiber detector on JT-60U

Energy Technology Data Exchange (ETDEWEB)

Harano, Hideki [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

1997-09-01

The DT fusion reactor cannot be realized without knowing how the fusion-produced 3.5 MeV {alpha} particles behave. The {alpha} particles` behavior can be simulated using the 1 MeV triton. To investigate the 1 MeV triton`s behavior, a new type of directional 14 MeV neutron detector, scintillating fiber (Sci-Fi) detector has been developed and installed on JT-60U in the cooperation with LANL as part of a US-Japan collaboration. The most remarkable feature of the Sci-Fi detector is that the plastic scintillating fibers are employed for the neutron sensor head. The Sci-Fi detector measures and extracts the DT neutrons from the fusion radiation field in high time resolution (10 ms) and wide dynamic range (3 decades). Triton burnup analysis code TBURN has been made in order to analyze the time evolution of DT neutron emission rate obtained by the Sci-Fi detector. The TBURN calculations reproduced the measurements fairly well, and the validity of the calculation model that the slowing down of the 1 MeV triton was classical was confirmed. The Sci-Fi detector`s directionality indicated the tendency that the DT neutron emission profile became more and more peaked with the time progress. In this study, in order to examine the effect of the toroidal field ripple on the triton burnup, R{sub p}-scan and n{sub e}-scan experiments have been performed. The R{sub p}-scan experiment indicates that the triton`s transport was increased as the ripple amplitude over the triton became larger. In the n{sub e}-scan experiment, the DT neutron emission showed the characteristic changes after the gas puffing injection. It was theoretically confirmed that the gas puffing was effective for the collisionality scan. (J.P.N.) 127 refs.

Triton burnup study using scintillating fiber detector on JT-60U

International Nuclear Information System (INIS)

Harano, Hideki

1997-09-01

The DT fusion reactor cannot be realized without knowing how the fusion-produced 3.5 MeV α particles behave. The α particles' behavior can be simulated using the 1 MeV triton. To investigate the 1 MeV triton's behavior, a new type of directional 14 MeV neutron detector, scintillating fiber (Sci-Fi) detector has been developed and installed on JT-60U in the cooperation with LANL as part of a US-Japan collaboration. The most remarkable feature of the Sci-Fi detector is that the plastic scintillating fibers are employed for the neutron sensor head. The Sci-Fi detector measures and extracts the DT neutrons from the fusion radiation field in high time resolution (10 ms) and wide dynamic range (3 decades). Triton burnup analysis code TBURN has been made in order to analyze the time evolution of DT neutron emission rate obtained by the Sci-Fi detector. The TBURN calculations reproduced the measurements fairly well, and the validity of the calculation model that the slowing down of the 1 MeV triton was classical was confirmed. The Sci-Fi detector's directionality indicated the tendency that the DT neutron emission profile became more and more peaked with the time progress. In this study, in order to examine the effect of the toroidal field ripple on the triton burnup, R p -scan and n e -scan experiments have been performed. The R p -scan experiment indicates that the triton's transport was increased as the ripple amplitude over the triton became larger. In the n e -scan experiment, the DT neutron emission showed the characteristic changes after the gas puffing injection. It was theoretically confirmed that the gas puffing was effective for the collisionality scan. (J.P.N.) 127 refs

Conceptual design study of quasi-steady state fusion experimental reactor (FEQ-Q), part 1

International Nuclear Information System (INIS)

1985-12-01

Since 1980 the design study has been conducted at JAERI for the Fusion Experimental Reactor (FER) which has been proposed to be the next machine to JT-60 in the Japanese long term program of fusion reactor development. Starting from 1984 JER design is being reviewed and redesigned. This report is a part of the interim report which describes the results obtained in the review and redesign activities in FY 1984. The results of the following design items are included; core plasma, reactor structure, reactor core components, magnets. (author)

Prediction of new tightly bound-states of H2+(d2+) and ''cold fusion''-experiments

International Nuclear Information System (INIS)

Barut, A.O.

1989-06-01

It is suggested that in the ''cold-fusion'' experiments of Fleischmann and Pons new tightly-bound molecular states of D 2 + are formed with binding energies predicted to be of the order of 50 keV accounting for the heat released without appreciable fusion. Other tests of the suggested mechanism are proposed and the derivation of the new energy levels is given. (author). 3 refs

Particle-beam-fusion progress report, July 1979 through December 1979

International Nuclear Information System (INIS)

1981-01-01

The following chapters are included in this semi-annual progress report: (1) fusion target studies, (2) target experiments, (3) particle-beam source developments, (4) particle beam experiments, (5) pulsed power, (6) pulsed power applications, and (7) electron beam fusion accelerator project

Ch. 37, Inertial Fusion Energy Technology

International Nuclear Information System (INIS)

Moses, E.

2010-01-01

Nuclear fission, nuclear fusion, and renewable energy (including biofuels) are the only energy sources capable of satisfying the Earth's need for power for the next century and beyond without the negative environmental impacts of fossil fuels. Substantially increasing the use of nuclear fission and renewable energy now could help reduce dependency on fossil fuels, but nuclear fusion has the potential of becoming the ultimate base-load energy source. Fusion is an attractive fuel source because it is virtually inexhaustible, widely available, and lacks proliferation concerns. It also has a greatly reduced waste impact, and no danger of runaway reactions or meltdowns. The substantial environmental, commercial, and security benefits of fusion continue to motivate the research needed to make fusion power a reality. Replicating the fusion reactions that power the sun and stars to meet Earth's energy needs has been a long-sought scientific and engineering challenge. In fact, this technological challenge is arguably the most difficult ever undertaken. Even after roughly 60 years of worldwide research, much more remains to be learned. the magnitude of the task has caused some to declare that fusion is 20 years away, and always will be. This glib criticism ignores the enormous progress that has occurred during those decades, progress inboth scientific understanding and essential technologies that has enabled experiments producing significant amounts of fusion energy. For example, more than 15 megawatts of fusion power was produced in a pulse of about half a second. Practical fusion power plants will need to produce higher powers averaged over much longer periods of time. In addition, the most efficient experiments to date have required using about 50% more energy than the resulting fusion reaction generated. That is, there was no net energy gain, which is essential if fusion energy is to be a viable source of electricity. The simplest fusion fuels, the heavy isotopes of

Tokamak Fusion Core Experiment (TFCX) special-purpose remote maintenance systems

International Nuclear Information System (INIS)

Masson, L.S.; Welland, H.J.

1985-01-01

A key element in the preconceptual design of the Tokamak Fusion Core Experiment (TFCX) was the development of design concepts for special-purpose remote maintenance systems. Included were systems for shield sector replacement, vacuum vessel sector and toroidal field coil replacement, limiter blade replacement, protective tile replacement, and general-purpose maintenance. This paper addresses these systems as they apply to the copper toroidal field (TF) coil version of the TFCX

Tyrosine kinase fusion genes in pediatric BCR-ABL1-like acute lymphoblastic leukemia

Science.gov (United States)

Boer, Judith M.; Steeghs, Elisabeth M.P.; Marchante, João R.M.; Boeree, Aurélie; Beaudoin, James J.; Berna Beverloo, H.; Kuiper, Roland P.; Escherich, Gabriele; van der Velden, Vincent H.J.; van der Schoot, C. Ellen; de Groot-Kruseman, Hester A.; Pieters, Rob; den Boer, Monique L.

2017-01-01

Approximately 15% of pediatric B cell precursor acute lymphoblastic leukemia (BCP-ALL) is characterized by gene expression similar to that of BCR-ABL1-positive disease and unfavorable prognosis. This BCR-ABL1-like subtype shows a high frequency of B-cell development gene aberrations and tyrosine kinase-activating lesions. To evaluate the clinical significance of tyrosine kinase gene fusions in children with BCP-ALL, we studied the frequency of recently identified tyrosine kinase fusions, associated genetic features, and prognosis in a representative Dutch/German cohort. We identified 14 tyrosine kinase fusions among 77 BCR-ABL1-like cases (18%) and none among 76 non-BCR-ABL1-like B-other cases. Novel exon fusions were identified for RCSD1-ABL2 and TERF2-JAK2. JAK2 mutation was mutually exclusive with tyrosine kinase fusions and only occurred in cases with high CRLF2 expression. The non/late response rate and levels of minimal residual disease in the fusion-positive BCR-ABL1-like group were higher than in the non-BCR-ABL1-like B-others (p<0.01), and also higher, albeit not statistically significant, compared with the fusion-negative BCR-ABL1-like group. The 8-year cumulative incidence of relapse in the fusion-positive BCR-ABL1-like group (35%) was comparable with that in the fusion-negative BCR-ABL1-like group (35%), and worse than in the non-BCR-ABL1-like B-other group (17%, p=0.07). IKZF1 deletions, predominantly other than the dominant-negative isoform and full deletion, co-occurred with tyrosine kinase fusions. This study shows that tyrosine kinase fusion-positive cases are a high-risk subtype of BCP-ALL, which warrants further studies with specific kinase inhibitors to improve outcome. PMID:27894077

Experience with titanium cages in anterior cervical discectomy and fusion

International Nuclear Information System (INIS)

Junaid, M.; Afsheen, A.; Bukhari, S.S.; Rashid, M.U.; Kalsoom, A.

2016-01-01

Background: Anterior cervical discectomy is a common procedure for treating patients for cervical disc prolapse. This study was conducted to study the surgical outcome and demographic characteristics of patients who were treated for anterior cervical disc prolapse. Methods: Study was conducted in the combined military hospital (CMH) Peshawar. Study interval was 3 years from 1st September, 2011 to 31st August, 2014. Total number of patients were 84. Males were 54 (64.28 percentage) and females were 30 (35.71 percentage). All the patients had undergone the procedure of anterior cervical discectomy and fusion with titanium cages (ACDF). All the patients had plain MRI cervical spine done for diagnosis of anterior cervical disc prolapse. Results: Total 84 patients were operated. In the patients who complained of brachialgia, 100 percentage improvement was seen after the operation. Three (3.5 percentage) of the patients, who presented with axial neck pain, continued to complain of pain and 2 (2.5 percentage) of the patients complained of pain at the donor site after the operation. One of the patient had dural tear which resulted in subcutaneous cerebrospinal fluid (CSF) accumulation and was treated conservatively with repeated aspiration. Fusion rate was 100 percentage with titanium cages used for fusion after anterior cervical discectomy. No complications were noted after the surgery at 1 year of interval. Conclusion: Results with titanium cages are expectedly good. Symptoms resolved and fusion rate was 100 percentage at 1 year follow up. (author)

Annual report of the Brookhaven National Laboratory Heavy Ion Fusion Project, 1 October 1977--1 October 1978

International Nuclear Information System (INIS)

1979-02-01

This report is divided into three parts. The first deals with the results of an analysis of the fusion problem in general, and heavy ion inertial fusion in particular. The second portion deals with the progress being made in the design and development of high current, high brightness pre-injectors and linear accelerators. The third deals with some experiments with space charge neutralization, bunching, etc

History of controlled nuclear fusion in Japan

International Nuclear Information System (INIS)

Uematsu, Eisui; Nishio, Shigeko; Takeda, Tatsuoki

2001-01-01

A research development of nuclear fusion was divided four periods: the first period as prehistory (until about 1955), the second period as begin of research (1955 to 1969), the third as the growth period (1970 to 1985) and the forth as the large tokamak age. In this paper I explained the second period, because general physicists and young plasma and controlled nuclear fusion researcher did not know about this period. The controlled nuclear fusion research was begun by the experiment of hydrogen bomb by USA and USSR in 1952 and 1953. In Japan, on the basis of many societies, 'The Controlled Nuclear Fusion Meeting' was established as an independent system and KAKEA (Journal of Fusion Research) was published in 1958. Japan government began to make the system by the Nuclear Commission in 1957. The main research devices in 1962 were linear pinch, mirror device, toroidal pinch, helical system, plasma gun and plasma measurement. USSR showed the excellent results of tokamak device in 1968. Ookawa spoke the effect of the average minimum-B, the best report in this period, at the second IAEA meeting, 1965. JAERI constructed JFT-1 and JFT-2, the latter was the first class device in the world and made the first step of Japanese research into the world, for examples, to attain the equilibrium of divertor plasma and to control impurity. Many research centers of controlled fusion were established in many universities in Japan from 1966 to 1980. Cooperation researchs between Japan and USA, USSR and many countries has been carried out after 1978: JIFT (Joint Institute for Fusion Theory) and FPPC (Fusion Power Coordinating Committee). The important results increased in this period. After 1985, the research activities are processing and data increased very fast depend on the larger devices and system, good measurement system and development of information system. JT-60 in JAERI opened to the large tokamak period. It led controlled fusion researchs in the world the same as TFTR (US

Tertiary proton diagnostics in future inertial confinement fusion experiments

International Nuclear Information System (INIS)

Cremer, S.; Verdon, C.P.; Petrasso, R.D.

1998-01-01

Recently, it was proposed to use energetic (up to 31 MeV) tertiary protons produced during the final stage of inertial confinement fusion implosions to measure the fuel areal density of compressed deuterium endash tritium (DT). The method is based on seeding the fuel with 3 He. The reaction of 3 He ions with the energetic knock-on deuterons, produced via the elastic scattering of 14.1 MeV neutrons, is a source of very energetic protons capable of escaping from very large areal density targets. This work presents results of detailed time-dependent Monte Carlo simulations of the nuclear processes involved in producing and transporting these protons through imploding targets proposed for direct-drive experiments on OMEGA [D. K. Bradley et al., Phys. Plasmas 5, 1870 (1998)] and the National Ignition Facility [S. W. Haan et al., Phys. Plasmas 2, 2480 (1995)]. copyright 1998 American Institute of Physics

The Novo Okno copper deposit of olistostrome origin (Bor, Eastern Serbia

Directory of Open Access Journals (Sweden)

Antonijević Ivan

2011-01-01

Full Text Available The copper deposit Novo Okno, uncovered at present, with non-ore and ore clasts of massive sulphides (from 0.5 to 50 m3 in size, has many distinctive features that indicate its olistostrome origin. The deposit is chaotic in structure, unstratified, with the lower surface unconformable over the underlying parent rock of the basin. It is a lens-like body, with the longer axis directed east and west, variable in thickness from 15 to 28 metres, about 335 metres long and less than 140 metres wide. These and other characteristics of the body indicate a unified, reworked, olistostrome copper deposit formed from primary ore bodies of the Bor mineral deposit and vulcanite, destroyed by volcanic explosion into blocks and rocks of Turonian age and extrusion and concurrent deposition on the land surface. Gravitational massive sliding of the consolidated rocks down the slopes of the volcanic relief and chaotic accumulation of ore and non-ore clasts (olistoliths in a marine basin evolved in the Upper Turonian and the Lower Senonian.

Liquid jet experiments: relevance to inertial confinement fusion reactors

International Nuclear Information System (INIS)

Hoffman, M.A.

1981-01-01

In order to try to find a reactor design which offered protection against neutron damage, studies were undertaken at LLNL (the Lawrence Livermore National Laboratory) of self-healing, renewable liquid-wall reactor concepts. In conjuction with these studies, were done a seris of small-scale aer jet experiments were done over the past several years at UCD (University of California, Davis Campus) to simulate the behavior of liquid lithium (or lithium-lead) jets in these liquid-wall fusion reactor concepts. Extropolating the results of these small-scale experiments to the large-scale lithium jets, tentatively concluded that the lithium jet can be re-established after the microexplosion, and with careful design the jets should not breakup due to instabilities during the relatively quiscent period between MICROEXPLOSIONS

Cloning, Expression and Purification of the Recombinant HIV-1 Tat-Nef Fusion Protein in Prokaryotic Expression System

OpenAIRE

Somayeh Kadkhodayan; Shiva Irani; Seyed Mehdi Sadat; Fatemeh Fotouhi; Azam Bolhassani

2016-01-01

Abstract Background: Nef is one of the HIV-1 critical proteins, because it is essential for viral replication and AIDS disease progression and induction of immune response against it can partially inhibit viral infection. Moreover, a domain of the HIV-1 Trans-Activator of Transcription (Tat, 48-60 aa) could act as a cell penetrating peptide (CPP). In current study, cloning and expression of Tat-Nef fusion protein was performed in E. coli for the first time. The protein expression was confi...

Cesium Hydroxide Fusion Dissolution of Analytical Reference Glass-1 in Both Powder and Shard Form

International Nuclear Information System (INIS)

Coleman, C.J.; Spencer, W.A.

1998-04-01

CsOH has been shown to be an effective and convenient dissolution reagent for Analytical Reference Glass-1 (ARG-1). This glass standard was prepared from nonradioactive DWPF Start-up Glass. Therefore, its composition is similar to DWPF product glass and many of the glass matrices prepared at SRTC.The principal advantage of the CsOH fusion dissolution is that the reagent does not add the alkali metals Li, Na, and K usually needed by SRS customers. Commercially available CsOH is quite pure so that alkali metals can be measured accurately, often without blank corrections. CsOH fusions provide a single dissolution method for applicable glass to replace multiple dissolution schemes used by most laboratories. For example, SRTC glass samples are most commonly dissolved with a Na 2 O 2 -NaOH fusion (ref.1) and a microwave- assisted acid dissolution with HNO 3 -HF-H 3 BO 3 -HCl (ref.2). Othe laboratories use fusion methods based on KOH, LiBO 2 , and Na 2 CO 3 CsOH fusion approach reduces by half not only the work in the dissolution laboratory, but also in the spectroscopy laboratories that must analyze each solution.Experiments also revealed that glass shards or pellets are rapidly attacked if the flux temperature is raised considerably above the glass softening point. The softening point of ARG-1 glass is near 650 degrees C. Fusions performed at 750 degrees C provided complete dissolutions and accurate elemental analyses of shards. Successful dissolution of glass shards was demonstrated with CsOH, Na 2 O 2 , NaOH, KOH, and RbOH. Ability to dissolve glass shards is of considerable practical importance. Crushing glass to a fine powder is a slow and tedious task, especially for radioactive glasses dissolved in shielded cells. CsOH fusion of glass powder or shards is a convenient, cost-effective dissolution scheme applicable in SRTC, the DWPF, and the commercial glass industry

Optimal preprocessing of serum and urine metabolomic data fusion for staging prostate cancer through design of experiment

International Nuclear Information System (INIS)

Zheng, Hong; Cai, Aimin; Zhou, Qi; Xu, Pengtao; Zhao, Liangcai; Li, Chen; Dong, Baijun; Gao, Hongchang

2017-01-01

Accurate classification of cancer stages will achieve precision treatment for cancer. Metabolomics presents biological phenotypes at the metabolite level and holds a great potential for cancer classification. Since metabolomic data can be obtained from different samples or analytical techniques, data fusion has been applied to improve classification accuracy. Data preprocessing is an essential step during metabolomic data analysis. Therefore, we developed an innovative optimization method to select a proper data preprocessing strategy for metabolomic data fusion using a design of experiment approach for improving the classification of prostate cancer (PCa) stages. In this study, urine and serum samples were collected from participants at five phases of PCa and analyzed using a 1 H NMR-based metabolomic approach. Partial least squares-discriminant analysis (PLS-DA) was used as a classification model and its performance was assessed by goodness of fit (R 2 ) and predictive ability (Q 2 ). Results show that data preprocessing significantly affect classification performance and depends on data properties. Using the fused metabolomic data from urine and serum, PLS-DA model with the optimal data preprocessing (R 2  = 0.729, Q 2  = 0.504, P < 0.0001) can effectively improve model performance and achieve a better classification result for PCa stages as compared with that without data preprocessing (R 2  = 0.139, Q 2  = 0.006, P = 0.450). Therefore, we propose that metabolomic data fusion integrated with an optimal data preprocessing strategy can significantly improve the classification of cancer stages for precision treatment. - Highlights: • NMR metabolomic analysis of body fluids can be used for staging prostate cancer. • Data preprocessing is an essential step for metabolomic analysis. • Data fusion improves information recovery for cancer classification. • Design of experiment achieves optimal preprocessing of metabolomic data fusion.

Osteoclast Fusion

DEFF Research Database (Denmark)

Marie Julie Møller, Anaïs; Delaissé, Jean-Marie; Søe, Kent

2017-01-01

on the nuclearity of fusion partners. While CD47 promotes cell fusions involving mono-nucleated pre-osteoclasts, syncytin-1 promotes fusion of two multi-nucleated osteoclasts, but also reduces the number of fusions between mono-nucleated pre-osteoclasts. Furthermore, CD47 seems to mediate fusion mostly through...... individual fusion events using time-lapse and antagonists of CD47 and syncytin-1. All time-lapse recordings have been studied by two independent observers. A total of 1808 fusion events were analyzed. The present study shows that CD47 and syncytin-1 have different roles in osteoclast fusion depending...... broad contact surfaces between the partners' cell membrane while syncytin-1 mediate fusion through phagocytic-cup like structure. J. Cell. Physiol. 9999: 1-8, 2016. © 2016 Wiley Periodicals, Inc....

Review of JT-60 experiment (March 1986)

International Nuclear Information System (INIS)

1986-11-01

Results of JT-60 experiment with ohmic heating in March 1986 are summarized. A maximum plasma current of 2 MA, an average plasma density of 5.7 x 10 19 m -3 and energy confinement time of 0.4 - 0.5 sec were obtained. Detailed characteristics of ohmic plasmas are discussed. (author)

Engineering Status of the Fusion Ignition Research Experiment (FIRE)

International Nuclear Information System (INIS)

Heitzenroeder, Philip J.; Meade, Dale; Thome, Richard J.

2000-01-01

FIRE is a compact, high field tokamak being studied as an option for the next step in the US magnetic fusion energy program. FIRE's programmatic mission is to attain, explore, understand, and optimize alpha-dominated plasmas to provide the knowledge necessary for the design of attractive magnetic fusion energy systems. This study began in 1999 with broad participation of the US fusion community, including several industrial participants. The design under development has a major radius of 2 m, a minor radius of 0.525 m, a field on axis of 10T and capability to operate at 12T with upgrades to power supplies. Toroidal and poloidal field magnets are inertially cooled with liquid nitrogen. An important goal for FIRE is a total project cost in the $1B range. This paper presents an overview of the engineering details which were developed during the FIRE preconceptual design study in FY99 and 00

Fusion events

International Nuclear Information System (INIS)

Aboufirassi, M; Angelique, J.C.; Bizard, G.; Bougault, R.; Brou, R.; Buta, A.; Colin, J.; Cussol, D.; Durand, D.; Genoux-Lubain, A.; Horn, D.; Kerambrun, A.; Laville, J.L.; Le Brun, C.; Lecolley, J.F.; Lefebvres, F.; Lopez, O.; Louvel, M.; Meslin, C.; Metivier, V.; Nakagawa, T.; Peter, J.; Popescu, R.; Regimbart, R.; Steckmeyer, J.C.; Tamain, B.; Vient, E.; Wieloch, A.; Yuasa-Nakagawa, K.

1998-01-01

The fusion reactions between low energy heavy ions have a very high cross section. First measurements at energies around 30-40 MeV/nucleon indicated no residue of either complete or incomplete fusion, thus demonstrating the disappearance of this process. This is explained as being due to the high amount o energies transferred to the nucleus, what leads to its total dislocation in light fragments and particles. Exclusive analyses have permitted to mark clearly the presence of fusion processes in heavy systems at energies above 30-40 MeV/nucleon. Among the complete events of the Kr + Au reaction at 60 MeV/nucleon the majority correspond to binary collisions. Nevertheless, for the most considerable energy losses, a class of events do occur for which the detected fragments appears to be emitted from a unique source. These events correspond to an incomplete projectile-target fusion followed by a multifragmentation. Such events were singled out also in the reaction Xe + Sn at 50 MeV/nucleon. For the events in which the energy dissipation was maximal it was possible to isolate an isotropic group of events showing all the characteristics of fusion nuclei. The fusion is said to be incomplete as pre-equilibrium Z = 1 and Z = 2 particles are emitted. The cross section is of the order of 25 mb. Similar conclusions were drown for the systems 36 Ar + 27 Al and 64 Zn + nat Ti. A cross section value of ∼ 20 mb was determined at 55 MeV/nucleon in the first case, while the measurement of evaporation light residues in the last system gave an upper limit of 20-30 mb for the cross section at 50 MeV/nucleon

60Co, 63Ni and 94Nb soil-to-plant transfer in pot experiments

International Nuclear Information System (INIS)

Gerzabek, M.H.; Mohamad, S.A.; Mueck, K.; Horak, O.

1995-01-01

Soil-to-plant transfer factors for 60 Co, 63 Ni and 94 Nb were obtained via pot experiments with a Dystric Cambisol and a Calcic Chernozem, both from Lower Austria. Investigated plants were greenrape (Brassica napus oleifera L.), bean (Phaseolus vulgaris L.) and winter wheat (Triticum aestivum L.). The soil-to-plant transfer factors decreased from 63 Ni to 60 Co and 94 Nb. Mean values from all experiments ranged from 1.12 ( 63 Ni) to 0.0045 ( 94 Nb). The transfer values obtained for 60 Co and 63 Ni are comparable to literature values, but 94 Nb-transfer seems to be lower than previous estimates. All radionuclides showed differences between plant species and plant organs. Transfer values were also dependent on the soil type. (author)

Cloning, Expression and Purification of the Recombinant HIV-1 Tat-Nef Fusion Protein in Prokaryotic Expression System

Directory of Open Access Journals (Sweden)

Somayeh Kadkhodayan

2016-07-01

Full Text Available Abstract Background: Nef is one of the HIV-1 critical proteins, because it is essential for viral replication and AIDS disease progression and induction of immune response against it can partially inhibit viral infection. Moreover, a domain of the HIV-1 Trans-Activator of Transcription (Tat, 48-60 aa could act as a cell penetrating peptide (CPP. In current study, cloning and expression of Tat-Nef fusion protein was performed in E. coli for the first time. The protein expression was confirmed by western blot analysis and was purified using reverse staining method. Materials and Methods: In this experimental study, primarily, cloning of Tat-Nef fusion gene was done in pGEX6p2 expression vector. Then, the expression of Tat-Nef recombinat protein in E.coli BL21 (DE3 strain was performed by using IPTG inducer. The protein expression was confirmed by SDS-PAGE and western blotting using anti-Nef monoclonal antibody. Then, the recombinant fusion protein was purified from gel using reverse staining method. Results: The results of PCR analysis and enzyme digestion showed a clear band of ~ 726 bp in agarose gel indicating the correct Tat-Nef fusion cloning in pGEX6p2 prokaryotic expression vector. In addition, a 54 kDa band of Tat-Nef on SDS-PAGE revealed Tat-Nef protein expression that western blot analysis using anti-Nef monoclonal antibody confirmed it. Conclusion: The purified Tat-Nef recombinant fusion protein will be used as an antigen for protein vaccine design against HIV infection.

Influence of transmutation and high neutron exposure on materials used in fission-fusion correlation experiments

International Nuclear Information System (INIS)

Garner, F.A.

1990-07-01

This paper explores the response of three different materials to high fluence irradiation as observed in recent fusion-related experiments. While helium at fusion-relevant levels influences the details of the microstructure of Fe--Cr--Ni alloys somewhat, the resultant changes in swelling and tensile behavior are relatively small. Under conditions where substantially greater-than-fusion levels of helium are generated, however, an extensive refinement of microstructure can occur, leading to depression of swelling at lower temperatures and increased strengthening at all temperatures studied. The behavior of these alloys is dominated by their tendency to converge to saturation microstructures which encourage swelling. Irradiations of nickel are dominated by its tendency to develop a different type of saturation microstructure that discourages further void growth. Swelling approaches saturation levels that are remarkably insensitive to starting microstructure and irradiation temperature. The rate of approach to saturation is very sensitive to variables such as helium, impurities, dislocation density and displacement rate, however. Copper exhibits a rather divergent response depending on the property measured. Transmutation of copper to nickel and zinc plays a large role in determining electrical conductivity but almost no role in void swelling. Each of these three materials offers different challenges in the interpretation of fission-fusion correlation experiments

Fusion energy 2000. Fusion energy 1998 (2001 Edition). Proceedings

International Nuclear Information System (INIS)

2001-01-01

This CD-ROM contains the Proceedings of 18th International Conference on Fusion Energy. It also contains an updated version of the Fusion Energy Conference 1998 Proceedings (38 additional papers included) as well as information on how to use this CD-ROM. The 18th International Atomic Energy Agency Fusion Energy Conference (FEC-2000) was held in Sorrento, Italy, 4-10 October 2000. 573 participants from over thirty countries and three international organizations took part in this Conference. The Conference was organized by the IAEA in co-operation with the Italian National Agency for New Technology, Energy and Environment (ENEA). Around 400 papers were presented in 22 oral and 8 poster sessions on magnetic confinement experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts, fusion technology, and safety and environment aspects. The 17th International Atomic Energy Agency (IAEA) Fusion Energy Conference was held in Yokohama, Japan, 19-24 October 1999. This 6-day conference, which was attended by 835 participants from over 30 countries and two international organizations, was organized by the IAEA in co-operation with the Japan Atomic Energy Research Institute (JAERI). More than 360 papers plus 5 summary talks were presented in 23 oral and 8 poster sessions on magnetic confinement and experiments, inertial fusion energy, plasma heating and current drive, ITER engineering design activities, magnetic confinement theory, innovative concepts and fusion technology

Fast reactor steam generators with sodium on the tube side. Design and operational parameters

International Nuclear Information System (INIS)

1994-01-01

A comparison of design and operational characteristics as well as analysis of experience gained during the long terms operation of the Micro Module Inverse Steam Generator and Module Inverse Steam Generator at BOR 60 reactor are main aims of this technical report. 20 refs, 47 figs, 14 tabs

Induction Linac Systems Experiments for heavy ion fusion

International Nuclear Information System (INIS)

Herrmannsfeldt, W.B.; Bangerter, R.O.

1994-06-01

The Lawrence Berkeley Laboratory and the Lawrence Livermore National Laboratory propose to build at LBL the Induction Linac Systems Experiments (ILSE), the next logical step toward the eventual goal of a heavy ion induction accelerator powerful enough to implode or drive inertial confinement fusion targets. Though much smaller than a driver, ILSE will be at full driver scale in several important parameters. Nearly all accelerator components and beam manipulations required for a driver will be tested. It is expected that ILSE will be built in stages as funds and technical progress allow. The first stage, called Elise will include all of the electrostatic quadrupole focused parts of ILSE

Synthetic fuels and fusion

Energy Technology Data Exchange (ETDEWEB)

Fillo, J A; Powell, J; Steinberg, M [Brookhaven National Lab., Upton, NY (USA)

1981-03-01

The decreasing availability of fossil fuels emphasizes the need to develop systems which will produce synthetic fuel to substitute for and supplement the natural supply. An important first step in the synthesis of liquid and gaseous fuels is the production of hydrogen. Thermonuclear fusion offers an inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. equal to 40-60% and hydrogen production efficiencies by high temperature electrolysis of approx. equal to 50-70% are projected for fusion reactors using high temperature blankets. Fusion/coal symbiotic systems appear economically promising for the first generation of commercial fusion synfuels plants. Coal production requirements and the environmental effects of large-scale coal usage would be greatly reduced by a fusion/coal system. In the long-term, there could be a gradual transition to an inexhaustible energy system based solely on fusion.

Fusion energy

International Nuclear Information System (INIS)

Anon.

1979-01-01

The efforts of the Chemical Technology Division in fusion energy include the areas of fuel handling, processing, and containment. Current studies are concerned largely with the development of vacuum pumps for fusion reactors and experiments and with development and evaluation of techniques for recovering tritium from solid or liquid breeding blankets. In addition, a small effort is devoted to support of the ORNL design of a major Tokamak experiment, The Next Step (TNS)

15 CFR 60.1 - Public information.

Science.gov (United States)

2010-01-01

... 15 Commerce and Foreign Trade 1 2010-01-01 2010-01-01 false Public information. 60.1 Section 60.1 Commerce and Foreign Trade Regulations Relating to Commerce and Foreign Trade BUREAU OF THE CENSUS, DEPARTMENT OF COMMERCE PUBLIC INFORMATION § 60.1 Public information. The rules and procedures regarding...

Plate impact experiments on DC745U cooled to ~ -60 °C

Energy Technology Data Exchange (ETDEWEB)

Gustavsen, Richard L. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics; Dattelbaum, Dana M. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics; Bartram, Brian Douglas [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics; Gibson, Lloyd Lee [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics; Jones, Justin Daniel [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics; Goodbody, Austin Bernard [Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Shock and Detonation Physics

2016-08-11

Using gas-gun driven plate impact experiments, we have measured the U_S - u_p Hugoniot of the silicone elastomer DC745U cooled to -60 °C. In summary, the initial density changes from p₀ (23°C) = 1.312 ± 0.010 g/cm³ to p₀ (-60°C) = 1.447 ± 0.011 g/cm³. The linear U_S - u_p Hugoniot changes from U_S = 1.62 + 1.74u_p km/s at +23°C, to U_S = 2.03 ± 0.06 + (2.03 ± 0.06) u_p km/s at -60°C. DC745U, therefore is much stiffer at -60°C than at +23°C, probably due to the crystallization that occurs at ~ -50°C. Caveats/deficiencies: 1) This report does not provide an adequate pedigree of the DC745U used. 2) References to unpublished room temperature shock compression data on the elastomer are inadequate. 3) The report has not been fact checked by a DC745 subject matter expert.

Cold fusion

International Nuclear Information System (INIS)

Koster, J.

1989-01-01

In this contribution the author the phenomenom of so-called cold fusion, inspired by the memorable lecture of Moshe Gai on his own search for this effect. Thus much of what follows was presented by Dr. Gai; the rest is from independent reading. What is referred to as cold fusion is of course the observation of possible products of deuteron-deuteron (d-d) fusion within deuterium-loaded (dentended) electrodes. The debate over the two vanguard cold fusion experiments has raged under far more public attention than usually accorded new scientific phenomena. The clamor commenced with the press conference of M. Fleishmann and S. Pons on March 23, 1989 and the nearly simultaneous wide circulation of a preprint of S. Jones and collaborators. The majority of work attempting to confirm these observations has at the time of this writing yet to appear in published form, but contributions to conferences and electronic mail over computer networks were certainly filled with preliminary results. To keep what follows to a reasonable length the author limit this discussion to the searches for neutron (suggested by ref. 2) or for excessive heat production (suggested by ref. 1), following a synopsis of the hypotheses of cold fusion

Quasi-elastic scattering an alternative tool for mapping the fusion barriers for heavy-ion induced fusion reaction

International Nuclear Information System (INIS)

Behera, B.R.

2016-01-01

Heavy element synthesis through heavy-ion induced fusion reaction is an active field in contemporary nuclear physics. Exact knowledge of fusion barrier is one of the essential parameters for planning any experiments for heavy element production. Theoretically there are many models available to predict the exact barrier. Though these models are successful for predicting the fusion of medium mass nuclei, it somehow fails for predicting the exact location of barrier for fusion of heavy nuclei. Experimental determination of barrier for such reactions is required for future experiments for the synthesis of heavy elements. Traditionally fusion barrier is determined taking a double derivative of fusion excitation function. However, such method is difficult in case of fusion of heavy nuclei due to its very low fusion/capture cross section and its experimental complications. Alternatively fusion barrier can be determined by measuring the quasi-elastic cross section at backward angles. This method can be applied for determining the fusion barrier for the fusion of heavy nuclei. Experimental determination of fusion barrier by different methods and comparison of the fusion excitation function and quasi-elastic scattering methods for the determination of fusion barrier are reviewed. At IUAC, New Delhi recently a program has been started for the measurement of fusion barrier through quasi-elastic scattering methods. The experimental facility and the first results of the experiments carried out with this facility are presented. (author)

Fusion neutronics

CERN Document Server

Wu, Yican

2017-01-01

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

Plasma diagnostic techniques in thermal-barrier tandem-mirror fusion experiments

International Nuclear Information System (INIS)

Silver, E.H.; Clauser, J.F.; Carter, M.R.; Failor, B.H.; Foote, J.H.; Hornady, R.S.; James, R.A.; Lasnier, C.J.; Perkins, D.E.

1986-01-01

We review two classes of plasma diagnostic techniques used in thermal-barrier tandem-mirror fusion experiments. The emphasis of the first class is to study mirror-trapped electrons at the thermal-barrier location. The focus of the second class is to measure the spatial and temporal behavior of the plasma space potential at various axial locations. The design and operation of the instruments in these two categories are discussed and data that are representative of their performance is presented

Modeling Cyber Situational Awareness Through Data Fusion

Science.gov (United States)

2013-03-01

following table: Table 3.10: Example Vulnerable Hosts for Criticality Assessment Experiment Example Id OS Applications/Services Version 1 Mac OS X VLC ...linux.org/. [4] Blasch, E., I. Kadar, J. Salerno, M. Kokar, S. Das, G. Powell, D. Corkill, and E. Ruspini. “Issues and challenges of knowledge representation...Holsopple. “Issues and challenges in higher level fusion: Threat/impact assessment and intent modeling (a panel summary)”. Information Fusion (FUSION

46 CFR 189.60-1 - Application.

Science.gov (United States)

2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Application. 189.60-1 Section 189.60-1 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OCEANOGRAPHIC RESEARCH VESSELS INSPECTION AND CERTIFICATION Certificates Under International Convention for Safety of Life at Sea, 1974 § 189.60-1 Application...

Safety concerns for superconducting magnets of upcoming fusion experiments

International Nuclear Information System (INIS)

Turner, L.R.

1983-01-01

-Several fusion experiments being constructed (Tore Supra) or contemplated (DCT 8, Alcator DCT) feature superconducting coils. These coils introduce the following safety concerns: 1. Internally Cooled Conductor (ICC). ICC's are found to be highly stable against short heat pulses, even when the coolant is stagnant or moving at low steady-state velocity. However, a large heat pulse is certain to quench the conductor. Thus, determining the stability limits is vital. 2. Helium II Cooling. Helium II has both unique advantages as a coolant and unique safety problems. 3. Shorted Turns. In magnets with shorts from operational accidents, the current can switch back and forth between the short and the shorted turns, as those alternatively go normal and superconducting. 4. Hybrid Superconducting-Normal Conducting Coil System. The possibility of unequal currents in the different magnets and thus of unexpected forces on the superconducting magnets is much greater than for an all-superconducting system. Analysis of these problems are presented

Enzymatic reduction of U60 nanoclusters by Shewanella oneidensis MR-1

Energy Technology Data Exchange (ETDEWEB)

Yu, Qiang; Fein, Jeremy B. [Notre Dame Univ., IN (United States). Dept. of Civil and Environmental Engineering and Earth Sciences

2018-04-01

In this study, a series of reduction experiments were conducted using a representative uranyl peroxide nanocluster, U60 (K{sub 16}Li{sub 44}[UO{sub 2}(O{sub 2})OH]{sub 60}) and a bacterial species, Shewanella oneidensis MR-1, that is capable of enzymatic U(VI) reduction. U60 was reduced by S. oneidensis in the absence of O{sub 2}, but the reduction kinetics for U60 were significantly slower than was observed in this study for aqueous uranyl acetate, and were faster than was reported in previous studies for solid phase U(VI). Our results indicate that U60 aggregates bigger than 0.2 μm formed immediately upon mixing with the bacterial growth medium, and that these aggregates were gradually broken down during the process of reduction. Neither reduction nor dissolution of U60 was observed during 72 h of control experiments open to the atmosphere, indicating that the breakdown and dissolution of U60 aggregates is caused by the reduction of U60, and that S. oneidensis is capable of direct reduction of the U(VI) within the U60 nanoclusters, likely due to the adsorption of U60 aggregates onto bacterial cells. This study is first to show the reduction capacity of bacteria for uranyl peroxide nanoclusters, and the results yield a better understanding of the long term fate of uranium in environmental systems in which uranyl peroxide nanoclusters are present.

Annual report of Naka Fusion Research Establishment from April 1, 2004 to March 31, 2005

International Nuclear Information System (INIS)

Yamamoto, Takumi; Sato, Masayasu; Kudo, Yusuke; Shu, Wataru; Yoshida, Hidetoshi

2005-09-01

This annual report provides an overview of research and development (R and D) activities at Naka Fusion Research Establishment during the period from 1 April, 2004 to 31 March, 2005, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities. In the JT-60 research program, the pulse length of the tokamak discharge was extended successfully up to 65 s in FY 2003. In FY 2004, following the successful results, optimization of long pulse discharges was continued. The pulse length of the negative-ion based neutral beam injection system has reached up to 25 s with an injection power of 1 MW. In the electron cyclotron wave system, the pulse length has also extended up to 45 s with an RF power of 0.35 MW by using four gyrotrons in a series operation. Sustainment of higher normalized β of β N >2.3 for 22.3 s, or β N >2.5 for 15.5 s has been achieved by exploiting available plasma heating systems. This discharge exhibits not only the high β N , but also high confinement improvement with the H factor of H 89P =1.9-2.3 and high normalized fusion performance of G≡H 89P β N /q 95 2 =0.4-0.5 during the sustainment, where q 95 is a safety factor at the edge. G-0.4 corresponds to the fusion energy gain of Q=10 for the ITER standard scenario. The H-mode plasma with H 89P -1.4 has been maintained for about 30 s, although degradation of the performance was observed at the later half of the discharge. In the reversed shear plasmas, the operation regime was successfully extended. Demonstration of neoclassical tearing mode stabilization and improvement of plasma performance in the high beta region (β N - 3) has been performed using local current drive by the second harmonic electron cyclotron waves. In addition, a real-time control system of safety factor profile has been developed. The design of National Centralized Tokamak (NCT), which is the superconducting modification of JT-60, progressed both in physics and

41 CFR 60-1.1 - Purpose and application.

Science.gov (United States)

2010-07-01

... obligations under the equal opportunity clause regardless of whether or not his contract contains a “Disputes... 41 Public Contracts and Property Management 1 2010-07-01 2010-07-01 true Purpose and application. 60-1.1 Section 60-1.1 Public Contracts and Property Management Other Provisions Relating to Public...

Driver Fusions and Their Implications in the Development and Treatment of Human Cancers

Directory of Open Access Journals (Sweden)

Qingsong Gao

2018-04-01

Full Text Available Summary: Gene fusions represent an important class of somatic alterations in cancer. We systematically investigated fusions in 9,624 tumors across 33 cancer types using multiple fusion calling tools. We identified a total of 25,664 fusions, with a 63% validation rate. Integration of gene expression, copy number, and fusion annotation data revealed that fusions involving oncogenes tend to exhibit increased expression, whereas fusions involving tumor suppressors have the opposite effect. For fusions involving kinases, we found 1,275 with an intact kinase domain, the proportion of which varied significantly across cancer types. Our study suggests that fusions drive the development of 16.5% of cancer cases and function as the sole driver in more than 1% of them. Finally, we identified druggable fusions involving genes such as TMPRSS2, RET, FGFR3, ALK, and ESR1 in 6.0% of cases, and we predicted immunogenic peptides, suggesting that fusions may provide leads for targeted drug and immune therapy. : Gao et al. analyze a 9,624 sample TCGA cohort with 33 cancer types to detect gene fusion events. They provide a landscape of fusion events detected, relate fusions to gene expression, focus on kinase fusion structures, examine mutually exclusive mutation and fusion patterns, and highlight fusion druggability. Keywords: fusion, cancer, RNA, translocation, gene fusions

46 CFR 193.60-1 - Application.

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2010-10-01

... 46 Shipping 7 2010-10-01 2010-10-01 false Application. 193.60-1 Section 193.60-1 Shipping COAST GUARD, DEPARTMENT OF HOMELAND SECURITY (CONTINUED) OCEANOGRAPHIC RESEARCH VESSELS FIRE PROTECTION EQUIPMENT Fire Axes § 193.60-1 Application. (a) The provisions of this subpart shall apply to all vessels...

Calidad de abonos orgánicos empleados en la depresión de Quíbor-Venezuela bajo ambientes protegidos

Directory of Open Access Journals (Sweden)

Duilio Torres Rodríguez

2017-01-01

Full Text Available La depresión de Quíbor es una de las zonas agrícolas más importante de Venezuela, donde en los últimos años se han introducido sistemas de producción bajo ambientes protegidos, los cuales están acompañados por el uso de abonos orgánicos, no certi cados. El objetivo de esta investigación fue evaluar la calidad de los abonos orgánicos empleados en sistemas de producción bajo ambientes protegidos en la depresión de Quíbor, Venezuela. Se realizó un diseño experimental completamente al azar y se evaluaron once (11 abonos orgánicos (cuatro sólidos y siete líquidos por triplicados. Los abonos sólidos fueron colectados en la parte superior, inferior y media de las pilas, mientras que los líquidos fueron tomados directamente de los tanques de almacenamiento. Para la caracterización de los abonos se empleó el protocolo TMECC, la materia orgánica se determinó por calcinación a 450°C, el nitrógeno por Kjeldahl y los macronutrientes (potasio y calcio y micronutrientes (cobre, manganeso, hierro y zinc en extracto acuoso 1/20 (v/v del material y cuantificación por absorción atómica. Los resultados obtenidos muestran que el vermicompost y compost de gallinaza presentaron los valores más altos de macronutrientes, mientras, para los abonos líquidos Macro®, fue quien presentó la mayor concentración de nitrógeno, humus1 los valores más altos de Ca y Mg y Micro® y humus2 los mayores contenidos de manganeso, hierro, cobre y zinc fueron encontrados, todos los abonos sólidos presentaron valores bajos de micronutrientes.

A unified modeling approach for physical experiment design and optimization in laser driven inertial confinement fusion

Energy Technology Data Exchange (ETDEWEB)

Li, Haiyan [Mechatronics Engineering School of Guangdong University of Technology, Guangzhou 510006 (China); Huang, Yunbao, E-mail: Huangyblhy@gmail.com [Mechatronics Engineering School of Guangdong University of Technology, Guangzhou 510006 (China); Jiang, Shaoen, E-mail: Jiangshn@vip.sina.com [Laser Fusion Research Center, China Academy of Engineering Physics, Mianyang 621900 (China); Jing, Longfei, E-mail: scmyking_2008@163.com [Laser Fusion Research Center, China Academy of Engineering Physics, Mianyang 621900 (China); Tianxuan, Huang; Ding, Yongkun [Laser Fusion Research Center, China Academy of Engineering Physics, Mianyang 621900 (China)

2015-11-15

Highlights: • A unified modeling approach for physical experiment design is presented. • Any laser facility can be flexibly defined and included with two scripts. • Complex targets and laser beams can be parametrically modeled for optimization. • Automatically mapping of laser beam energy facilitates targets shape optimization. - Abstract: Physical experiment design and optimization is very essential for laser driven inertial confinement fusion due to the high cost of each shot. However, only limited experiments with simple structure or shape on several laser facilities can be designed and evaluated in available codes, and targets are usually defined by programming, which may lead to it difficult for complex shape target design and optimization on arbitrary laser facilities. A unified modeling approach for physical experiment design and optimization on any laser facilities is presented in this paper. Its core idea includes: (1) any laser facility can be flexibly defined and included with two scripts, (2) complex shape targets and laser beams can be parametrically modeled based on features, (3) an automatically mapping scheme of laser beam energy onto discrete mesh elements of targets enable targets or laser beams be optimized without any additional interactive modeling or programming, and (4) significant computation algorithms are additionally presented to efficiently evaluate radiation symmetry on the target. Finally, examples are demonstrated to validate the significance of such unified modeling approach for physical experiments design and optimization in laser driven inertial confinement fusion.

Annual report of Naka Fusion Research Establishment. From April 1,2000 to March 31, 2001

International Nuclear Information System (INIS)

Kuriyama, Masaaki; Kizu, Kaname; Kusakawa, Fumio; Matsumoto, Hiroshi; Sakamoto, Keishi; Sengoku, Seio

2001-11-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 2000 to March 31, 2001. The activities in the Naka Fusion Research Establishment are outstanding at high performance plasma researches in JT-60 and JFT-2M, and development in ITER EDA including technological R and Ds. The JT-60 project aims at contributing to the physics R and D for ITER and establishing the physics basis for a steady state tokamak fusion reactor like SSTR. For the achievement of those objectives, both physical and engineering researches have been done. The JT-60 have continued to be productive in many areas covering performance improvements of high β p ELMy H-mode regime and reversed shear plasma, non-inductive current drive, physics study relevant to improved modes, stabilization of MHD modes, feedback control, disruption study, understandings on energetic particles, and scrape off layer and divertor studies with increased pumping capability. On JFT-2M, advanced and basic research of tokamak plasma is being promoted, including application of the low activation ferritic steel, with the flexibility of a medium-sized device. The pre-testing on compatibility of ferritic steel plates (FPs), covering ∼20% of the inside wall of the vacuum vessel, with plasma was performed, demonstrating no adverse effects on plasmas. Boronization was introduced for the first time in JFT-2M after installation of inside FPs. High-β N discharges (β N up to ∼2.8) were obtained with inside FPs and boronization. Formation of negative electric field at the H-mode transition during ECH was clarified by the heavy ion beam probe (HIBP). The MSE polarimeter system, which is capable of simultaneous measurement of a radial electric field, has been newly developed. In RF experiments, fast wave electric field profile was directly measured for the first time using the beat wave and HIBP. The principal objective of theoretical and

[Fusion research/tokamak]. Final report, 1 May 1988 - 30 April 1994

International Nuclear Information System (INIS)

1994-01-01

The objectives of the Fusion Research Center Program are: (1) to advance /the transport studies of tokamaks, including the development and maintenance of the Magnetic Fusion Energy Database, and (2) to provide theoretical interpretation, modeling and equilibrium and stability studies for the text-upgrade tokamak. Work is described on five basic categories: (1) magnetic fusion energy database; (2) computational support and numerical modeling; (3) support for TEXT-upgrade and diagnostics; (4) transport studies; and (5) Alfven waves

Annual report of Naka Fusion Research Establishment. From April 1,2000 to March 31, 2001

Energy Technology Data Exchange (ETDEWEB)

Kuriyama, Masaaki; Kizu, Kaname; Kusakawa, Fumio; Matsumoto, Hiroshi; Sakamoto, Keishi; Sengoku, Seio (eds.) [Japan Atomic Energy Research Inst., Naka, Ibaraki (Japan). Naka Fusion Research Establishment

2001-11-01

This report provides an overview of research and development activities at Naka Fusion Research Establishment, JAERI, during the period from April 1, 2000 to March 31, 2001. The activities in the Naka Fusion Research Establishment are outstanding at high performance plasma researches in JT-60 and JFT-2M, and development in ITER EDA including technological R and Ds. The JT-60 project aims at contributing to the physics R and D for ITER and establishing the physics basis for a steady state tokamak fusion reactor like SSTR. For the achievement of those objectives, both physical and engineering researches have been done. The JT-60 have continued to be productive in many areas covering performance improvements of high {beta}{sub p} ELMy H-mode regime and reversed shear plasma, non-inductive current drive, physics study relevant to improved modes, stabilization of MHD modes, feedback control, disruption study, understandings on energetic particles, and scrape off layer and divertor studies with increased pumping capability. On JFT-2M, advanced and basic research of tokamak plasma is being promoted, including application of the low activation ferritic steel, with the flexibility of a medium-sized device. The pre-testing on compatibility of ferritic steel plates (FPs), covering {approx}20% of the inside wall of the vacuum vessel, with plasma was performed, demonstrating no adverse effects on plasmas. Boronization was introduced for the first time in JFT-2M after installation of inside FPs. High-{beta}{sub N} discharges ({beta}{sub N} up to {approx}2.8) were obtained with inside FPs and boronization. Formation of negative electric field at the H-mode transition during ECH was clarified by the heavy ion beam probe (HIBP). The MSE polarimeter system, which is capable of simultaneous measurement of a radial electric field, has been newly developed. In RF experiments, fast wave electric field profile was directly measured for the first time using the beat wave and HIBP. The

Inertial fusion program. Progress report, January 1-June 30, 1978

International Nuclear Information System (INIS)

Skoberne, F.

1980-05-01

Studies and experiments aimed at investigating the possibility of restoring wavefront quality in optical systems through phase conjugation are summarized, and work that could lead to the development of highly damage-resistant isolators is discussed. The effects of various parameters on pulse-energy uniformity and of multipass extraction on laser efficiency are reported. Results of equation-of-state, shock propagation, multiburst simulation, and opacity measurements are discussed. Target designs are described that should provide a smooth transition from the exploding-pusher regime of experiments to that of isentropic compression. Progress in target fabrication techniques toward creating a 20-times-liquid-density target are outlined, and efforts that led to the extension of our neutron detection capability to levels of less than 10 3 n are summarized. The results of various studies of laser fusion application, e.g., for producing ultrahigh-temperature process heat or hydrogen from water decomposition are presented, as well as investigations of fusion-fission hybrids for the production of 233 U from 232 Th

Early and late HIV-1 membrane fusion events are impaired by sphinganine lipidated peptides that target the fusion site.

Science.gov (United States)

Klug, Yoel A; Ashkenazi, Avraham; Viard, Mathias; Porat, Ziv; Blumenthal, Robert; Shai, Yechiel

2014-07-15

Lipid-conjugated peptides have advanced the understanding of membrane protein functions and the roles of lipids in the membrane milieu. These lipopeptides modulate various biological systems such as viral fusion. A single function has been suggested for the lipid, binding to the membrane and thus elevating the local concentration of the peptide at the target site. In the present paper, we challenged this argument by exploring in-depth the antiviral mechanism of lipopeptides, which comprise sphinganine, the lipid backbone of DHSM (dihydrosphingomyelin), and an HIV-1 envelope-derived peptide. Surprisingly, we discovered a partnership between the lipid and the peptide that impaired early membrane fusion events by reducing CD4 receptor lateral diffusion and HIV-1 fusion peptide-mediated lipid mixing. Moreover, only the joint function of sphinganine and its conjugate peptide disrupted HIV-1 fusion protein assembly and folding at the later fusion steps. Via imaging techniques we revealed for the first time the direct localization of these lipopeptides to the virus-cell and cell-cell contact sites. Overall, the findings of the present study may suggest lipid-protein interactions in various biological systems and may help uncover a role for elevated DHSM in HIV-1 and its target cell membranes.

1981 Annual Status Report: thermonuclear fusion technology

International Nuclear Information System (INIS)

1982-01-01

The work perfomed on 1981 concerns four projects, namely: - The project 1: ''Reactor Studies''. During 1981 this activity was made in support to the European participation to the INTOR (INternational TOkamak Reactor) studies. This represents a collaborative effort among Europe, Japan; USA and USSR, under the auspices of IAEA, to design a major fusion experiment beyond the upcoming generation of large tokamaks. - The Project 2: ''Blanket Technology'' has the aim to investigate the behaviour of blanket materials in fusion conditions. - The Project 3: ''Materials Sorting and Development'' has the aim to assess the mechanical properties and radiation damage of standard and advanced materials suited for structures, in particular for application as first wall of the fusion reactors. - The Project 4: ''Cyclotron Operation and Experiments'' has the task to exploit a cyclotron to simulate radiation damages to materials in a fusion ambient

ADVANCED FUSION TECHNOLOGY RESEARCH AND DEVELOPMENT. ANNUAL REPORT TO THE U.S. DEPARTMENT OF ENERGY OCTOBER 1, 2001 THROUGH SEPTEMBER 30, 2002

International Nuclear Information System (INIS)

PROJECT STAFF

2003-01-01

OAK-B135 The General Atomics (GA) Advanced Fusion Technology program seeks to advance the knowledge base needed for next-generation fusion experiments and, ultimately, for an economical and environmentally attractive fusion energy source. To achieve this objective, we carry out fusion systems design studies to evaluate the technologies needed for next-step experiments and power plants, and we conduct research to develop basic and applied knowledge about these technologies. GA's Advanced Fusion Technology program derives from, and draws on, the physics and engineering expertise built up by many years of experience in designing, building, and operating plasma physics experiments. Our technology development activities take full advantage of the GA DIII-D program, the DIII-D facility and the Inertial Confinement Fusion (ICF) program and the ICF Target Fabrication facility. The following sections summarize GA's FY02 work in the areas of Fusion Power Plant Studies (ARIES, Section 2), Inertial Fusion Energy (IFE) Chamber Analysis (Section 3), IFE Target Supply System Development (Section 4), Next Step Fusion Design (Section 5), Advanced Liquid Plasma Facing Surfaces (ALPS, Section 6), Advanced Power Extraction Study (APEX, Section 7), Plasma Interactive Materials (DiMES, Section 8) and RF Technology (Section 9). Our work in these areas continues to address many of the issues that must be resolved for the successful construction and operation of next-generation experiments and, ultimately, the development of safe, reliable, economic fusion power plants

HUWE1 and TRIP12 Collaborate in Degradation of Ubiquitin-Fusion Proteins and Misframed Ubiquitin

DEFF Research Database (Denmark)

Poulsen, Esben G; Steinhauer, Cornelia; Lees, Michael

2012-01-01

In eukaryotic cells an uncleavable ubiquitin moiety conjugated to the N-terminus of a protein signals the degradation of the fusion protein via the proteasome-dependent ubiquitin fusion degradation (UFD) pathway. In yeast the molecular mechanism of the UFD pathway has been well characterized...... in degradation of the UFD substrate Ub(G76V)-YFP. The most significant hits from the screen were the E3 ubiquitin-protein ligase HUWE1, as well as PSMD7 and PSMD14 that encode proteasome subunits. Accordingly, knock down of HUWE1 led to an increase in the steady state level and a retarded degradation of the UFD...... substrate. Knock down of HUWE1 also led to a stabilization of the physiological UFD substrate UBB(+1). Precipitation experiments revealed that HUWE1 is associated with both the Ub(G76V)-YFP substrate and the 26S proteasome, indicating that it functions late in the UFD pathway. Double knock down of HUWE1...

Shock-timing experiments for Inertial Confinement Fusion

International Nuclear Information System (INIS)

Debras, G.

2012-01-01

The Laser Megajoule (LMJ), which should achieve energy gain in an indirect drive inertial confinement fusion configuration, is being built in France by the CEA (Commissariat a l'Energie Atomique et aux Energies Alternatives). To achieve thermonuclear ignition, the compression of a spherical target will have to be controlled by a series of accurately timed centripetal shocks, with a finely tuned level. A first experiment, performed in 2010 on the LIL (Ligne d'Integration Laser) facility at CEA, has allowed us to study the coalescence of two planar shocks in an indirectly-driven sample of polystyrene, within the framework of shock timing. The main objectives were to validate the experimental concept and the numerical simulations, as a proof-of-principle for future shock-timing campaigns. The main diagnostics used for this study are VISAR (Velocity Interferometer System for Any Reflection) and an optical shock breakout diagnostic, taking into account optical perturbations caused by X-rays. In another experiment, conducted on the LULI (Laboratoire pour l'Utilisation des Lasers Intenses) laser facility in 2010, we studied the timing of two planar directly-driven shocks using the same diagnostics. This latter study is related to the shock ignition concept, with the long-term perspective of energy production. This thesis presents these two experiments and their results. (author) [fr

Comparative assessment of world research efforts on magnetic confinement fusion

International Nuclear Information System (INIS)

McKenney, B.L.; McGrain, M.; Rutherford, P.H.

1990-02-01

This report presents a comparative assessment of the world's four major research efforts on magnetic confinement fusion, including a comparison of the capabilities in the Soviet Union, the European Community (Western Europe), Japan, and the United States. A comparative evaluation is provided in six areas: tokamak confinement; alternate confinement approaches; plasma technology and engineering; and fusion computations. The panel members are involved actively in fusion-related research, and have extensive experience in previous assessments and reviews of the world's four major fusion programs. Although the world's four major fusion efforts are roughly comparable in overall capabilities, two conclusions of this report are inescapable. First, the Soviet fusion effort is presently the weakest of the four programs in most areas of the assessment. Second, if present trends continue, the United States, once unambiguously the world leader in fusion research, will soon lose its position of leadership to the West European and Japanese fusion programs. Indeed, before the middle 1990s, the upgraded large-tokamak facilities, JT-60U (Japan) and JET (Western Europe), are likely to explore plasma conditions and operating regimes well beyond the capabilities of the TFTR tokamak (United States). In addition, if present trends continue in the areas of fusion nuclear technology and materials, and plasma technology and materials, and plasma technology development, the capabilities of Japan and Western Europe in these areas (both with regard to test facilities and fusion-specific industrial capabilities) will surpass those of the United States by a substantial margin before the middle 1990s

Fusion Physics

Energy Technology Data Exchange (ETDEWEB)

Kikuchi, Mitsuru; Lackner, Karl; Tran, Minh Quang [eds.

2012-09-15

Recreating the energy production process of the Sun - nuclear fusion - on Earth in a controlled fashion is one of the greatest challenges of this century. If achieved at affordable costs, energy supply security would be greatly enhanced and environmental degradation from fossil fuels greatly diminished. Fusion Physics describes the last fifty years or so of physics and research in innovative technologies to achieve controlled thermonuclear fusion for energy production. The International Atomic Energy Agency (IAEA) has been involved since its establishment in 1957 in fusion research. It has been the driving force behind the biennial conferences on Plasma Physics and Controlled Thermonuclear Fusion, today known as the Fusion Energy Conference. Hosted by several Member States, this biennial conference provides a global forum for exchange of the latest achievements in fusion research against the backdrop of the requirements for a net energy producing fusion device and, eventually, a fusion power plant. The scientific and technological knowledge compiled during this series of conferences, as well as by the IAEA Nuclear Fusion journal, is immense and will surely continue to grow in the future. It has led to the establishment of the International Thermonuclear Experimental Reactor (ITER), which represents the biggest experiment in energy production ever envisaged by humankind.

The nectin-1α transmembrane domain, but not the cytoplasmic tail, influences cell fusion induced by HSV-1 glycoproteins

International Nuclear Information System (INIS)

Subramanian, Ravi P.; Dunn, Jennifer E.; Geraghty, Robert J.

2005-01-01

Nectin-1 is a receptor for herpes simplex virus (HSV), a member of the immunoglobulin superfamily, and a cellular adhesion molecule. To study domains of nectin-1α involved in cell fusion, we measured the ability of nectin-1α/nectin-2α chimeras, nectin-1α/CD4 chimeras, and transmembrane domain and cytoplasmic tail mutants of nectin-1α to promote cell fusion induced by HSV-1 glycoproteins. Our results demonstrate that only chimeras and mutants containing the entire V-like domain and a link to the plasma membrane conferred cell-fusion activity. The transmembrane domain and cytoplasmic tail of nectin-1 were not required for any viral receptor or cell adhesion function tested. Cellular cytoplasmic factors that bind to the nectin-1α cytoplasmic tail, therefore, did not influence virus entry or cell fusion. Interestingly, the efficiency of cell fusion was reduced when membrane-spanning domains of nectin-1α and gD were replaced by glycosylphosphatidylinositol tethers, indicating that transmembrane domains may play a modulatory role in the gD/nectin-1α interaction in fusion

Laser fusion program at LASL. Progress report, January 1--June 30, 1976

Energy Technology Data Exchange (ETDEWEB)

Stark, E.

1976-11-01

Progress in the development of high-energy short-pulse CO/sub 2/ laser systems for fusion research is reported. The Single-Beam System continued to be used in target experiments at a peak intensity of 7 x 10/sup 14/ W/cm/sup 2/, and the system was improved. The status of the Two-Beam System, on which target experiments have begun with 300-J, 1-ns pulses in one beam, is described. Construction and checkout of the Eight-Beam System are continuing. Further design studies for the High-Energy Gas Laser Facility and the initiation of a prototype program are reported. The rare-gas oxides and dimeric mercury were emphasized in investigations into new lasers for fusion research. Experimental kinetics studies, a study of heat-pipe containment of metal vapors, theoretical support, and optical-damage investigations are described. Significant experimental and theoretical results are reported on the question of wavelength-scaling in laser-plasma interaction physics. Studies of vacuum insulation as a means of preventing target preheat by hot electrons are also summarized. Analyses of the ponderomotive force in laser-plasma interactions and of the relationship between x-ray spectrum and suprathermal electron distribution are described. Improvements to the MCRAD and LASNEX design codes are outlined, and a LASNEX analysis of a target heated by laser-generated fast ions is discussed. Improved methods of screening, characterizing, and fabricating microballoons and more complex targets are described, and progress in applying uniform layers of DT ice on the inside of a microballoon is reported. Improvements in diagnostics include x-ray streak photographs, the fabrication of x-ray microscope systems, and x-ray film imaging. New results in our feasibility and systems studies are presented, including the wetted-wall and magnetically protected reactor concepts, the effect of ionized debris on cavity walls, the fusion-fission breeder concept, and the production of synthetic fuels by fusion

Mechanical properties and microstructural investigations of TIG welded 40 mm and 60 mm thick SS 316L samples for fusion reactor vacuum vessel applications

Energy Technology Data Exchange (ETDEWEB)

Buddu, Ramesh Kumar, E-mail: brkumar75@gmail.com; Chauhan, N.; Raole, P.M.

2014-12-15

Highlights: • Austenitic stainless steels (316L) of 40 mm and 60 mm thickness plates were joined by Tungsten Inert Gas welding (TIG) process which are probable materials for advanced fusion reactor vacuum vessel requirements. • Mechanical properties and detailed microstructure studies have been carried out for welded samples. • Fractography analysis of impact test specimens indicated ductile fracture mode in BM, HAZ and WZ samples. • Presence of delta ferrite phase was observed in the welded zone and ferrite number data was measured for the base and weld metal and was found high in welds. - Abstract: The development of advanced fusion reactors like DEMO will have various challenges in materials and fabrication. The vacuum vessel is important part of the fusion reactor. The double walled design for vacuum vessel with thicker stainless steel material (40–60 mm) has been proposed in the advanced fusion reactors like ITER. Different welding techniques will have to be used for such vacuum vessel development. The required mechanical, structural and other properties of stainless steels have to be maintained in these joining processes of components of various shapes and sizes in the form of plates, ribs, shells, etc. The present paper reports characterization of welding joints of SS316L plates with higher thicknesses like 40 mm and 60 mm, prepared using multi-pass Tungsten Inert Gas (TIG) welding process. The weld quality has been evaluated with non-destructive tests by X-ray radiography and ultrasonic methods. The mechanical properties like tensile, bend tests, Vickers hardness and impact fracture tests have been carried out for the weld samples. Tensile property test results indicate sound weld joints with efficiencies over 100%. Hardening was observed in the weld zone in non-uniform manner. Macro and microstructure studies have been carried out for Base Metal (BM), Heat Affected Zone (HAZ) and Weld Zone (WZ). Scanning Electron Microscopy (SEM) analysis carried

Mechanical properties and microstructural investigations of TIG welded 40 mm and 60 mm thick SS 316L samples for fusion reactor vacuum vessel applications

International Nuclear Information System (INIS)

Buddu, Ramesh Kumar; Chauhan, N.; Raole, P.M.

2014-01-01

Highlights: • Austenitic stainless steels (316L) of 40 mm and 60 mm thickness plates were joined by Tungsten Inert Gas welding (TIG) process which are probable materials for advanced fusion reactor vacuum vessel requirements. • Mechanical properties and detailed microstructure studies have been carried out for welded samples. • Fractography analysis of impact test specimens indicated ductile fracture mode in BM, HAZ and WZ samples. • Presence of delta ferrite phase was observed in the welded zone and ferrite number data was measured for the base and weld metal and was found high in welds. - Abstract: The development of advanced fusion reactors like DEMO will have various challenges in materials and fabrication. The vacuum vessel is important part of the fusion reactor. The double walled design for vacuum vessel with thicker stainless steel material (40–60 mm) has been proposed in the advanced fusion reactors like ITER. Different welding techniques will have to be used for such vacuum vessel development. The required mechanical, structural and other properties of stainless steels have to be maintained in these joining processes of components of various shapes and sizes in the form of plates, ribs, shells, etc. The present paper reports characterization of welding joints of SS316L plates with higher thicknesses like 40 mm and 60 mm, prepared using multi-pass Tungsten Inert Gas (TIG) welding process. The weld quality has been evaluated with non-destructive tests by X-ray radiography and ultrasonic methods. The mechanical properties like tensile, bend tests, Vickers hardness and impact fracture tests have been carried out for the weld samples. Tensile property test results indicate sound weld joints with efficiencies over 100%. Hardening was observed in the weld zone in non-uniform manner. Macro and microstructure studies have been carried out for Base Metal (BM), Heat Affected Zone (HAZ) and Weld Zone (WZ). Scanning Electron Microscopy (SEM) analysis carried

Thought Experiment to Examine Benchmark Performance for Fusion Nuclear Data

Science.gov (United States)

Murata, Isao; Ohta, Masayuki; Kusaka, Sachie; Sato, Fuminobu; Miyamaru, Hiroyuki

2017-09-01

There are many benchmark experiments carried out so far with DT neutrons especially aiming at fusion reactor development. These integral experiments seemed vaguely to validate the nuclear data below 14 MeV. However, no precise studies exist now. The author's group thus started to examine how well benchmark experiments with DT neutrons can play a benchmarking role for energies below 14 MeV. Recently, as a next phase, to generalize the above discussion, the energy range was expanded to the entire region. In this study, thought experiments with finer energy bins have thus been conducted to discuss how to generally estimate performance of benchmark experiments. As a result of thought experiments with a point detector, the sensitivity for a discrepancy appearing in the benchmark analysis is "equally" due not only to contribution directly conveyed to the deterctor, but also due to indirect contribution of neutrons (named (A)) making neutrons conveying the contribution, indirect controbution of neutrons (B) making the neutrons (A) and so on. From this concept, it would become clear from a sensitivity analysis in advance how well and which energy nuclear data could be benchmarked with a benchmark experiment.

Thought Experiment to Examine Benchmark Performance for Fusion Nuclear Data

Directory of Open Access Journals (Sweden)

Murata Isao

2017-01-01

Full Text Available There are many benchmark experiments carried out so far with DT neutrons especially aiming at fusion reactor development. These integral experiments seemed vaguely to validate the nuclear data below 14 MeV. However, no precise studies exist now. The author’s group thus started to examine how well benchmark experiments with DT neutrons can play a benchmarking role for energies below 14 MeV. Recently, as a next phase, to generalize the above discussion, the energy range was expanded to the entire region. In this study, thought experiments with finer energy bins have thus been conducted to discuss how to generally estimate performance of benchmark experiments. As a result of thought experiments with a point detector, the sensitivity for a discrepancy appearing in the benchmark analysis is “equally” due not only to contribution directly conveyed to the deterctor, but also due to indirect contribution of neutrons (named (A making neutrons conveying the contribution, indirect controbution of neutrons (B making the neutrons (A and so on. From this concept, it would become clear from a sensitivity analysis in advance how well and which energy nuclear data could be benchmarked with a benchmark experiment.

Progress in JT-60 innovative technologies

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-09-01

This review report provides the synthetic archives of innovative technologies in 20-year facility developments for the large tokamak experimental device JT-60, first founded as the major magnetic fusion device in the Second Basic Program for Fusion Research and Development of Japan. Manufacture of JT-60 was started in 1978, and the first plasma was achieved on April 8, 1985. In 1989-1991, the vacuum vessel and poloidal field coils were entirely reconfigured to improve the plasma performance. The major original mission of the JT-60 project, a breakeven condition for a D-T equivalent plasma, was finally attained in 1996. After this, JT-60, as a leading device for magnetic fusion research in the world, continues to challenge many experimental issues, which has been achieved by collaboration of innovative facility developments and experimental improvements. In addition, at this time to start the ITER construction phase in 2005, this review is expected to contribute the construction and operation activities for the next generation tokamak by providing the basic ideas in facility developments. We classified a tremendous number of development items into the selected sections for this review. Since the authors have been in charge of each development activity of their own, the contents are full of essential stories, points, and keywords in spite of its compact handbook size. We believe this review could provide highly sophisticated, informative ideas matured in JT-60 technological developments. (author)

Annual report of Naka Fusion Research Establishment from April 1, 1999 to March 31, 2000

International Nuclear Information System (INIS)

Ninomiya, Hiromasa; Inabe, Teruo; Kaneko, Tadao; Konoshima, Sigeru; Miura, M. Yushi; Nakamura, Kazuyuki

2001-01-01

In JT-60, some mechanical improvements of the centrifugal pellet injector have been done for stable production and successive ejection of pellet. In addition, a guide tube for an injection from top of high-field side was installed as well as the low-field side in February 2000. The injection power of electron cyclotron heating (ECH) system of the frequency of 110 GHz installed last year was increased up to ∼0.75 MW for 2 seconds in this year using the control of RF beam angle. Two gyrotrons were newly installed with total power increased from 1 MW to 3 MW. Highlights of the JT-60 experiments in FY (Fiscal Year) 2000 may be summarized as follows: (1) A reversed shear discharge with an equivalent fusion multiplication factor Q DT eq of ∼0.5 was achieved successfully at plasma current of 2.4 MA for 0.8 seconds. (2) Quasi-steady operation of low current reversed shear plasma with a large fraction (∼80%) of bootstrap current was realized under full non-inductive current drive condition. H-factor of 3.3-3.8 at electron density as high as 73% of the Greenwald limit was sustained for 6 times of the energy confinement time. (3) Normalized beta exceeding the ideal no-wall stability limit was obtained in reversed shear plasmas with a ratio of an outer-wall radius to a plasma minor radius less than 1.3. (4) L-H transition power was reduced by ∼30% in the W-shaped divertor with pumping from both inside and outside slots compared with that in the open divertor. Helium exhaust rate in ELMy H-mode plasmas was improved up to 50% higher than the inside slot pumping. (5) Current drive efficiency of 1.3x10 19 A/m 2 /W was attained with the central electron temperature of 8.6 keV. The efficiency is about 2.6 times higher than that of 100 keV. On the JFT-2M, advanced and basic research of tokamak plasma is being produced including the application of the low activation ferritic steel. A dramatic reduction of trapped ion loss due to the toroidal field ripple was identified for the

DOE Handbook: Supplementary guidance and design experience for the fusion safety standards DOE-STD-6002-96 and DOE-STD-6003-96

Energy Technology Data Exchange (ETDEWEB)

None

1999-01-01

Two standards have been developed that pertain to the safety of fusion facilities. These are DOE- STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements, and DOE-STD-6003-96, Safety of Magnetic Fusion Facilities: Guidance. The first of these standards identifies requirements that subscribers to that standard must meet to achieve safety in fusion facilities. The second standard contains guidance to assist in meeting the requirements identified in the first This handbook provides additional documentation on good operations and design practices as well as lessons learned from the experiences of designers and operators of previous fusion facilities and related systems. It is intended to capture the experience gained in the various fields and pass it on to designers of future fusion facilities as a means of enhancing success and safety. The sections of this document are presented according to the physical location of the major systems of a fusion facility, beginning with the vacuum vessel and proceeding to those systems and components outside the vacuum vessel (the "Ex-vessel Systems"). The last section describes administrative procedures that cannot be localized to specific components. It has been tacitly assumed that the general structure of the fusion facilities addressed is that of a tokamak though the same principles would apply to other magnetic confinement options.

1982 annual status report: thermonuclear fusion technology

International Nuclear Information System (INIS)

1982-01-01

The objective of this programme is to study the technological problems related to ''Post Jet'' experimental machines and, in a longer range, to assess the engineering aspects of Fusion Power Reactor Plants. According to the decision taken by the Council of Ministers on the JRC multiannual programme (1980-1983), the work performed on 1982 concerns four projects, namely: The Project 1: ''Fusion Reactor Studies''concerns mainly the NET (Next European Torus) studies which have been continued in the framework of the European participation to INTOR (INternational TOkamak Reactor). This represents a collaborative effort to design a major fusion experiment beyond the-upcoming generation of large tokamaks. The Project 2: ''Blanket Technology'' has the aim to investigate the behaviour of blanket materials in fusion conditions. The Project 3: ''Materials Sorting and Development'' has the aim to assess the mechanical properties and radiation damage of standard and advanced materials suited for structures, in particular for application as first wall of the fusion reactors. The Project 4: ''Cyclotron Operation and Experiments''has the task to exploit a cyclotron to simulate radiation damages to materials in a fusion ambient

Fusion research in Hungary

International Nuclear Information System (INIS)

Zoletnik, S.

2004-01-01

Hungarian fusion research started in the 1970s, when the idea of installing a small tokamak experiment emerged. In return to computer equipment a soviet tokamak was indeed sent to Hungary and started to operate as MT-1 at the Central Research Institute for Physics (KFKI) in 1979. Major research topics included diagnostic development, edge plasma studies and investigation of disruptions. Following a major upgrade in 1992 (new vacuum vessel, active position control and PC network based data acquisition system) the MT-1M tokamak was used for the study of transport processes with trace impurity injection, micropellet ablation studies, X-ray tomography and laser blow-off diagnostic development. Although funding ceased in the middle of the 90's the group was held alive by collaborations with EU fusion labs: FZ -Juelich, IPP-Garching and CRPP-EPFL Lausanne. In 1998 the machine was dismantled due to reorganization of the Hungarian Academy of Sciences. New horizons opened to fusion research from 1999, when Hungary joined EURATOM and a fusion Association was formed. Since then fusion physics studies are done in collaboration with major EU fusion laboratories, Hungarian researchers also play an active role in JET diagnostics upgrade and ITER design. Major topics are pellet ablation studies, plasma turbulence diagnosis using Beam Emission Spectroscopy and other techniques, tomography and plasma diagnostics using various neutral beams. In fusion relevant technology R and D Hungary has less records. Before joining EURATOM some materials irradiation studies were done at the Budapest Research Reactor at KFKI-AEKI. The present day fusion technology programme focuses still on irradiation studies, nuclear material database and electromagnetic testing techniques. Increasing the fusion technology research activities is a difficult task, as the competition in Hungarian industry is very strong and the interest of organizations in long-term investments into R and D is rather weak and

Fusion Ignition Research Experiment System Integration

International Nuclear Information System (INIS)

Brown, T.

1999-01-01

The FIRE (Fusion Ignition Research Experiment) configuration has been designed to meet the physics objectives and subsystem requirements in an arrangement that allows remote maintenance of in-vessel components and hands-on maintenance of components outside the TF (toroidal-field) boundary. The general arrangement consists of sixteen wedged-shaped TF coils that surround a free-standing central solenoid (CS), a double-wall vacuum vessel and internal plasma-facing components. A center tie rod is used to help support the vertical magnetic loads and a compression ring is used to maintain wedge pressure in the inboard corners of the TF coils. The magnets are liquid nitrogen cooled and the entire device is surrounded by a thermal enclosure. The double-wall vacuum vessel integrates cooling and shielding in a shape that maximizes shielding of ex-vessel components. The FIRE configuration development and integration process has evolved from an early stage of concept selection to a higher level of machine definition and component details. This paper describes the status of the configuration development and the integration of the major subsystem components

Fusion technology 1992

International Nuclear Information System (INIS)

Ferro, C.; Gasparatto, M.; Knoepfel, H.

1993-01-01

The aim of the biennial series of symposia on the title subject, organized by the European Fusion Laboratories, is the exchange of information on the design, construction and operation of fusion experiments and on the technology being developed for the next step devices and fusion reactors. The coverage of the volume includes the technological aspects of fusion reactors in relation to new developments, this forming a guideline for the definition of future work. These proceedings comprise three volumes and contain both the invited lectures and contributed papers presented at the symposium which was attended by 569 participants from around the globe. The 343 papers, including 12 invited papers, characterize the increasing interest of industry in the fusion programme, giving a broad and current overview on the progress and trends fusion technology is experiencing now, as well as indicating the future for fusion devices

Observation of tritium in cold fusion experiments

International Nuclear Information System (INIS)

Krishnan, M.S.; Malhotra, S.K.; Gaonkar, D.G.; Sadhukhan, H.K.

1990-01-01

This paper describes the results of tritium measurements carried out during the electrolysis of heavy water in different electrolysers employing palladium and titanium as cathodes. The tritium level of electrolytes have been found to be many orders of magnitudes higher than what can be explained on the basis of isotope enrichment and evaporation during electrolysis. The neutron measurement results have also been included and these observations have been attributed to the phenomenon of cold fusion. (author). 6 refs., 1 tab

Research and development of JT-60 tokamak

International Nuclear Information System (INIS)

Saito, Ryusei; Sato, Hiroshi; Murata, Toshifumi; Ito, Yoshiyasu.

1978-01-01

The development of nuclear fusion apparatuses for the purpose of utilizing energy due to nuclear fusion reaction has been forwarded in various countries, and in Japan, the critical plasma testing apparatus JT-60 is about to be constructed, centering around Japan Atomic Energy Research Institute. This is one of four large apparatuses to be constructed in the world, and it is expected to be completed in 1982. JT-60 is a nuclear fusion apparatus of tokamak type aiming at generating critical plasma. The features of JT-60 are the formation of the plasma with small aspect ratio, the equipment of a magnetic limiter, the arrangement of the first wall of molybdenum and high temperature baking as the measures to impurities. The large toroidal magnetic field coil of JT-60 is composed of 18 unit coils. The analyses of magnetic field, thermal behavior and structural strength, the selection of materials, and the development of manufacturing techniques regarding the toroidal coil are described. The vacuum container of JT-60 is composed of the main body of torus type comprising thickwalled rings and bellows, the first wall comprising liners, fixed limiter and magnetic limiter, and observation ports. It is large torus-form container with non-circular cross section, and baking at 500 deg. C is required as the measure to ultrahigh vacuum. Complex forces including electromagnetic force act on it. (Kako, I.)

Advanced fuels for nuclear fusion reactors

International Nuclear Information System (INIS)

McNally, J.R. Jr.

1974-01-01

Should magnetic confinement of hot plasma prove satisfactory at high β (16 πnkT//sub B 2 / greater than 0.1), thermonuclear fusion fuels other than D.T may be contemplated for future fusion reactors. The prospect of the advanced fusion fuels D.D and 6 Li.D for fusion reactors is quite promising provided the system is large, well reflected and possesses a high β. The first generation reactions produce the very active, energy-rich fuels t and 3 He which exhibit a high burnup probability in very hot plasmas. Steady state burning of D.D can ensue in a 60 kG field, 5 m reactor for β approximately 0.2 and reflectivity R/sub mu/ = 0.9 provided the confinement time is about 38 sec. The feasibility of steady state burning of 6 Li.D has not yet been demonstrated but many important features of such systems still need to be incorporated in the reactivity code. In particular, there is a need for new and improved nuclear cross section data for over 80 reaction possibilities

On-going activities in Belgium in the field of FR & ADS: The progress since 2010

International Nuclear Information System (INIS)

De Bruyn, Didier

2012-01-01

Some R&D achievements: • LEXUR II: investigate combined irradiation & LBE environment; irradiation in BOR60; 1st PIE currently running; • FP7 MAX (Myrrha Accelerator eXperiments) started, dealing with reliability & availability; • RHAPTER (Remote HAndling Proof-of-principle TEst Rig) : commissioning running; • LiLIPuTTeR (Liquid Lead-bismuth Innovative Pump Technology Test Rig): now used to test pump components; • HELIOS (rig for experimental gas – liquid oxygen conditioning programme): under commissioning; support for other experimental activities

Fusion - 2050 perspective (in Polish)

CERN Document Server

Romaniuk, R S

2013-01-01

The results of strongly exothermic reaction of thermonuclear fusion between nuclei of deuterium and tritium are: helium nuclei and neutrons, plus considerable kinetic energy of neutrons of over 14 MeV. DT nuclides synthesis reaction is probably not the most favorable one for energy production, but is the most advanced technologically. More efficient would be possibly aneutronic fusion. The EU by its EURATOM agenda prepared a Road Map for research and implementation of Fusion as a commercial method of thermonuclear energy generation in the time horizon of 2050.The milestones on this road are tokomak experiments JET, ITER and DEMO, and neutron experiment IFMIF. There is a hope, that by engagement of the national government, and all research and technical fusion communities, part of this Road Map may be realized in Poland. The infrastructure build for fusion experiments may be also used for material engineering research, chemistry, biomedical, associated with environment protection, power engineering, security, ...

The ARBOR irradiation project

International Nuclear Information System (INIS)

Petersen, C.; Shamardin, V.; Fedoseev, A.; Shimansky, G.; Efimov, V.; Rensman, J.

2002-01-01

The irradiation project 'ARBOR', for 'Associated Reactor Irradiation in BOR 60', includes 150 mini-tensile/low cycle fatigue specimens and 150 mini-Charpy (KLST) specimens of nine different RAFM steels. Specimens began irradiation on 22 November 2000 in an specially designed irradiation rig in BOR 60, in a fast neutron flux (>0.1 MeV) of 1.8x10 15 n/cm 2 s and with direct sodium cooling at a temperature less than 340 deg. C. Tensile, low cycle fatigue and Charpy specimens of the following materials are included: EUROFER 97, F82H mod., OPTIFER IVc, EUROFER 97 with different boron contents, ODS-EUROFER 97, as well as EUROFER 97 electron-beam welded and reference bulk material, from NRG, Petten

Conceptual design of Fusion Experimental Reactor (FER)

International Nuclear Information System (INIS)

Tone, T.; Fujisawa, N.

1983-01-01

Conceptual design studies of the Fusion Experimental Reactor (FER) have been performed. The FER has an objective of achieving selfignition and demonstrating engineering feasibility as a next generation tokamak to JT-60. Various concepts of the FER have been considered. The reference design is based on a double-null divertor. Optional design studies with some attractive features based on advanced concepts such as pumped limiter and RF current drive have been carried out. Key design parameters are; fusion power of 440 MW, average neutron wall loading of 1MW/m 2 , major radius of 5.5m, plasma minor radius of 1.1m, plasma elongation of 1.5, plasma current of 5.3MA, toroidal beta of 4%, toroidal field on plasma axis of 5.7T and tritium breeding ratio of above unity

High temperature experiment for accelerator inertial fusion

International Nuclear Information System (INIS)

Lee, E.P.

1985-01-01

The High Temperature Experiment (HTE) is intended to produce temperatures of 50-100 eV in solid density targets driven by heavy ion beams from a multiple beam induction linac. The fundamental variables (particle species, energy number of beamlets, current and pulse length) must be fixed to achieve the temperature at minimum cost, subject to criteria of technical feasibility and relevance to the development of a Fusion Driver. The conceptual design begins with an assumed (radiation-limited) target temperature and uses limitations due to particle range, beamlet perveance, and target disassembly to bound the allowable values of mass number (A) and energy (E). An accelerator model is then applied to determine the minimum length accelerator, which is a guide to total cost. The accelerator model takes into account limits on transportable charge, maximum gradient, core mass per linear meter, and head-to-tail momentum variation within a pulse

Advanced synfuel production with fusion

International Nuclear Information System (INIS)

Powell, J.R.; Fillo, J.

1979-01-01

An important first step in the synthesis of liquid and gaseous fuels is the production of hydrogen. Thermonuclear fusion offers a nearly inexhaustible source of energy for the production of hydrogen from water. Depending on design, electric generation efficiencies of approx. 40 to 60% and hydrogen production efficiencies by high temperature electrolysis of approx. 50 to 70% are projected for fusion reactors using high temperature blankets

Modeling and experiments on tritium permeation in fusion reactor blankets

International Nuclear Information System (INIS)

Holland, D.F.; Longhurst, G.R.

1985-01-01

Issues are discussed that are critical in determining tritium loss from helium-cooled fusion breeding blankets. These issues are: (a) applicability of present models to permeation at low tritium pressures, (b) effectiveness of oxide layers in reducing permeation, (c) effectiveness of hydrogen addition as a means to lower tritium permeation, and (d) effectiveness of conversion to tritiated water and subsequent trapping as a means to reduce permeation. The paper discusses theoretical models applicable to these issues, and presents results of experiments in two areas: permeation of mixtures of hydrogen isotopes and conversion to tritiated water

Assessment of fire hazards in buildings housing fusion energy experiments

International Nuclear Information System (INIS)

Alvares, N.; Lipska, A.

1978-01-01

A number of materials in and within the proximity of buildings housing fusion energy experiments (FEE) were analyzed for their potential fire hazard. The materials used in this study were mostly: electrical and thermal insulations. The fire hazard of these materials was assessed in terms of their ease of ignition, heat release rate, generation of smoke, and the effect of thermal environment on the combustion behavior. Several fire protection measures for buildings housing the (FEE) projects are analyzed and as a result of this study are found to be adequate for the near term

In vitro translocation experiments with RxLR-reporter fusion proteins of Avr1b from Phytophthora sojae and AVR3a from Phytophthora infestans fail to demonstrate specific autonomous uptake in plant and animal cells.

Science.gov (United States)

Wawra, Stephan; Djamei, Armin; Albert, Isabell; Nürnberger, Thorsten; Kahmann, Regine; van West, Pieter

2013-05-01

Plant-pathogenic oomycetes have a large set of secreted effectors that can be translocated into their host cells during infection. One group of these effectors are the RxLR effectors for which it has been shown, in a few cases, that the RxLR motif is important for their translocation. It has been suggested that the RxLR-leader sequences alone are enough to translocate the respective effectors into eukaryotic cells through binding to surface-exposed phosphoinositol-3-phosphate. These conclusions were primary based on translocation experiments conducted with recombinant fusion proteins whereby the RxLR leader of RxLR effectors (i.e., Avr1b from Phytophthora sojae) were fused to the green fluorescent protein reporter-protein. However, we failed to observe specific cellular uptake for a comparable fusion protein where the RxLR leader of the P. infestans AVR3a was fused to monomeric red fluorescent protein. Therefore, we reexamined the ability of the reported P. sojae AVR1b RxLR leader to enter eukaryotic cells. Different relevant experiments were performed in three independent laboratories, using fluorescent reporter fusion constructs of AVR3a and Avr1b proteins in a side-by-side comparative study on plant tissue and human and animal cells. We report that we were unable to obtain conclusive evidence for specific RxLR-mediated translocation.

Stagnation morphology in Magnetized Liner Inertial Fusion experiments

Science.gov (United States)

Gomez, M. R.; Harding, E. C.; Ampleford, D. J.; Jennings, C. A.; Awe, T. J.; Chandler, G. A.; Glinsky, M. E.; Hahn, K. D.; Hansen, S. B.; Jones, B.; Knapp, P. F.; Martin, M. R.; Peterson, K. J.; Rochau, G. A.; Ruiz, C. L.; Schmit, P. F.; Sinars, D. B.; Slutz, S. A.; Weis, M. R.; Yu, E. P.

2017-10-01

In Magnetized Liner Inertial Fusion (MagLIF) experiments on the Z facility, an axial current of 15-20 MA is driven through a thick metal cylinder containing axially-magnetized, laser-heated deuterium fuel. The cylinder implodes, further heating the fuel and amplifying the axial B-field. Instabilities, such as magneto-Rayleigh-Taylor, develop on the exterior of the liner and may feed through to the inner surface during the implosion. Monochromatic x-ray emission at stagnation shows the stagnation column is quasi-helical with axial variations in intensity. Recent experiments demonstrated that the stagnation emission structure changed with modifications to the target wall thickness. Additionally, applying a thick dielectric coating to the exterior of the target modified the stagnation column. A new version of the x-ray self-emission diagnostic has been developed to investigate stagnation with higher resolution. Sandia National Laboratories is a multi-mission laboratory managed and operated by National Technology & Engineering Solutions of Sandia, LLC., a wholly owned subsidiary of Honeywell International, Inc., for the U.S. Department of Energy's National Nuclear Security Administration under contract DE-NA0003525.

Viral membrane fusion

International Nuclear Information System (INIS)

Harrison, Stephen C.

2015-01-01

Membrane fusion is an essential step when enveloped viruses enter cells. Lipid bilayer fusion requires catalysis to overcome a high kinetic barrier; viral fusion proteins are the agents that fulfill this catalytic function. Despite a variety of molecular architectures, these proteins facilitate fusion by essentially the same generic mechanism. Stimulated by a signal associated with arrival at the cell to be infected (e.g., receptor or co-receptor binding, proton binding in an endosome), they undergo a series of conformational changes. A hydrophobic segment (a “fusion loop” or “fusion peptide”) engages the target-cell membrane and collapse of the bridging intermediate thus formed draws the two membranes (virus and cell) together. We know of three structural classes for viral fusion proteins. Structures for both pre- and postfusion conformations of illustrate the beginning and end points of a process that can be probed by single-virion measurements of fusion kinetics. - Highlights: • Viral fusion proteins overcome the high energy barrier to lipid bilayer merger. • Different molecular structures but the same catalytic mechanism. • Review describes properties of three known fusion-protein structural classes. • Single-virion fusion experiments elucidate mechanism

Viral membrane fusion

Energy Technology Data Exchange (ETDEWEB)

Harrison, Stephen C., E-mail: harrison@crystal.harvard.edu

2015-05-15

Membrane fusion is an essential step when enveloped viruses enter cells. Lipid bilayer fusion requires catalysis to overcome a high kinetic barrier; viral fusion proteins are the agents that fulfill this catalytic function. Despite a variety of molecular architectures, these proteins facilitate fusion by essentially the same generic mechanism. Stimulated by a signal associated with arrival at the cell to be infected (e.g., receptor or co-receptor binding, proton binding in an endosome), they undergo a series of conformational changes. A hydrophobic segment (a “fusion loop” or “fusion peptide”) engages the target-cell membrane and collapse of the bridging intermediate thus formed draws the two membranes (virus and cell) together. We know of three structural classes for viral fusion proteins. Structures for both pre- and postfusion conformations of illustrate the beginning and end points of a process that can be probed by single-virion measurements of fusion kinetics. - Highlights: • Viral fusion proteins overcome the high energy barrier to lipid bilayer merger. • Different molecular structures but the same catalytic mechanism. • Review describes properties of three known fusion-protein structural classes. • Single-virion fusion experiments elucidate mechanism.

Socio-economic research on fusion: SERF 2 (1999-2000). Task 1: Externalities of fusion. Exploitation and improvement of work performed under SERF 1

Energy Technology Data Exchange (ETDEWEB)

Schneider, T.; Lepicard, S. [Centre d' Etude sur l' Evaluation de la Protection dans le Domaine Nucleaire, 92 - Fontenay-aux-Roses (France); Hamacher, T. [Euratom/IPP Fusion Association (Germany); Hallberg, B.; Aquilonius, K. [Studsvik Eco and Safety AB, Association Euratom-NFR (Sweden); Ward, D. [Euratom/UKAEA Fusion Association (United Kingdom); Korhonen, R. [VTT, Association Euratom-Tekes (Finland); Lechon, Y.; Cabal, H.; Saez, R. [Euratom/CIEMAT Fusion Association (Spain)

2001-01-01

In the previous phase of the SERF project an assessment of the external costs of two conceptual models of a fusion power plant was performed, as well as a comparison with other energy options. Results obtained ranged from 1,29 mEURO/kWh to 2,71 mEURO/kWh for the two models analysed respectively, well below those obtained for fossil-fuelled power and nuclear fission power plants confirming the role of fusion as a sustainable energy source in the long term. Some elements were identified as the predominant cause of external costs. The most important of them was collective doses produced by the global dispersion of C-14. Additional work has been carried out in the framework of the SEAFP (Safety and Environmental Assessment of Fusion Power) and SEAL within SEAFP-2 programme. In the present phase of the SERF project the effects of all of these technological advances in the external costs of fusion power have been evaluated. An analysis of the key variables influencing the external cost aiming to set some recommendations for the design of fusion power plants with minimum external costs has been also carried out. Furthermore, the effects of a scenario of intensive use of fusion power to meet energy requirement in future have been analysed in terms of its incidence in global radiation level and global warming. (author)

Detection of EWS/FLI-1 fusion in non-Ewing soft tissue tumors.

Science.gov (United States)

Trancău, I O; Huică, R; Surcel, M; Munteanu, A; Ursaciuc, C

2015-01-01

EWS/FLI-1 fusion mainly appears in Ewing's sarcoma or the primitive neuroectodermal tumors and represents a genomic marker for these tumors. However, it can appear with lower frequency in other soft tissue tumors. The paper investigates the presence of EWS/FLI-1 fusion in clinically diagnosed sarcoma belonging to different non-Ewing connective tissue tumors in order to search for a possible new biomarker valuable for investigators. 20 patients with soft tissue tumors, who underwent surgery, were tested. Intra-operative samples of normal and tumor tissue were collected for histopathological diagnosis and genetics determinations. The patients' RNA from tumor and normal peritumoral tissue was extracted and EWS/FLI-1 fusion screened by quantitative real-time PCR. The relative expression of the fusion in the tumor sample was compared to the similar expression in normal tissue. The amplification in the threshold zone was shown by 5 samples (25%): 2 clear cell sarcoma, 1 fibrosarcoma, 1 malignant tumor of nerve sheath, 1 metastatic adenocarcinoma. We differentiated between the unspecific amplification and concluded that these are weak positive results. Genomic investigation may establish the tumor malignancy and its possible affiliation earlier than histopathology. It can support the screening of EWS/FLI-1 fusion in a larger variety of clinically diagnosed soft tissue tumors.

Laser driven inertial fusion: the physical basis of current and recently proposed ignition experiments

International Nuclear Information System (INIS)

Atzeni, S

2009-01-01

A brief overview of the inertial fusion principles and schemes is presented. The bases for the laser driven ignition experiments programmed for the near future at the National Ignition Facility are outlined. These experiments adopt indirect-drive and aim at central ignition. The principles of alternate approaches, based on direct-drive and different routes to ignition (fast ignition and shock ignition) are also discussed. Gain curves are compared and discussed.

Fusion Materials Research at Oak Ridge National Laboratory in Fiscal Year 2015

Energy Technology Data Exchange (ETDEWEB)

Wiffen, F. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Melton, Stephanie G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-12-01

The realization of fusion energy is a formidable challenge with significant achievements resulting from close integration of the plasma physics and applied technology disciplines. Presently, the most significant technological challenge for the near-term experiments such as ITER, and next generation fusion power systems, is the inability of current materials and components to withstand the harsh fusion nuclear environment. The overarching goal of the Oak Ridge National Laboratory (ORNL) fusion materials program is to provide the applied materials science support and understanding to underpin the ongoing Department of Energy (DOE) Office of Science fusion energy program while developing materials for fusion power systems. In doing so the program continues to be integrated both with the larger United States (US) and international fusion materials communities, and with the international fusion design and technology communities.This document provides a summary of Fiscal Year (FY) 2015 activities supporting the Office of Science, Office of Fusion Energy Sciences Materials Research for Magnetic Fusion Energy (AT-60-20-10-0) carried out by ORNL. The organization of this report is mainly by material type, with sections on specific technical activities. Four projects selected in the Funding Opportunity Announcement (FOA) solicitation of late 2011 and funded in FY2012-FY2014 are identified by “FOA” in the titles. This report includes the final funded work of these projects, although ORNL plans to continue some of this work within the base program.

Conceptual requirements for large fusion experiment control, data, robotics, and management systems

International Nuclear Information System (INIS)

Gaudreau, M.P.J.; Sullivan, J.D.

1987-05-01

The conceptual system requirements for the control, data, robotics, and project management (CDRM) system for the next generation of fusion experiments are developed by drawing on the success of the Tara control and data system. The requirements are described in terms of an integrated but separable matrix of well-defined interfaces among the various systems and subsystems. The study stresses modularity, performance, cost effectiveness, and exportability

Muon-catalyzed fusion experiment target and detector system. Preliminary design report

International Nuclear Information System (INIS)

Jones, S.E.; Watts, K.D.; Caffrey, A.J.; Walter, J.B.

1982-03-01

We present detailed plans for the target and particle detector systems for the muon-catalyzed fusion experiment. Requirements imposed on the target vessel by experimental conditions and safety considerations are delineated. Preliminary designs for the target vessel capsule and secondary containment vessel have been developed which meet these requirements. In addition, the particle detection system is outlined, including associated fast electronics and on-line data acquisition. Computer programs developed to study the target and detector system designs are described

Reconstruction of Co-60 Irradiation Facility No.1

International Nuclear Information System (INIS)

Nakamura, Yoshiteru; Takada, Isao; Kaneko, Hirohisa; Hirao, Toshio; Haneda, Noriyuki; Mitomo, Shouichi; Tachibana, Hiroyuki; Yoshida, Kenzou

1989-01-01

Cobalt Irradiation Facility No.1 was constructed in 1964 as the first large scale Co-60 irradiation facility equipped a deep water pool for source storage of Co-60 sources. Recently, the reconstruction of the facility was decided because the aging of various parts of the facility became remarkable and new research programs required upgradings of the facility. Important points of upgradings are as follows: A shielding capacity of the source storage and pool is increased to 55.5 PBq from 18.5 PBq. The opening in a floor of the irradiation room which is used for the source lifting in the room, is enlarged in order to utilize a large and high intensity source. Radiation resistance of the irradiation apparatus and installed equipments in the radiation room is increased for a high dose rate irradiation. Basic structure and shape of the facility building such as shielding, pool and building roof is not changed but electrical, mechanical equipments and systems are completely renewed. To increase a reliability, the irradiation apparatus and systems are also replaced with an improved and up-to-date one designed based on operation experiences of Co-60 facilities at TRCRE through many years. In addition, auxiliary equipments such as radiation monitors, manipulators, water treatment system and so on are replaced. This report presents the reconstruction of Co-60 Irradiation Facility No.1 stressing on the replacement and modification of the irradiation apparatus. (author)

Present status of Fast Ignition Realization EXperiment (FIREX) and inertial fusion energy development

International Nuclear Information System (INIS)

Azechi, H.; Fujimoto, Y.; Fujioka, S.

2012-11-01

Controlled thermonuclear ignition and subsequent burn will be demonstrated in a couple of years on the central ignition scheme. Fast ignition has the high potential to ignite a fuel using only about one tenth of laser energy necessary to the central ignition. This compactness may largely accelerate inertial fusion energy development. One of the most advanced fast ignition programs is the Fast Ignition Realization Experiment (FIREX). The goal of its first phase is to demonstrate ignition temperature of 5 keV, followed by the second phase to demonstrate ignition-and-burn. The second series experiment of FIREX-I from late 2010 to early 2011 has demonstrated a high (≈20%) coupling efficiency from laser to thermal energy of the compressed core, suggesting that one can achieve the ignition temperature at the laser energy below 10 kJ. Given the demonstrations of the ignition temperature at FIREX-I and the ignition-and-burn at the National Ignition Facility, the inertial fusion research would then shift from the plasma physics era to power generation era. (author)

Fusion Simulation Program

International Nuclear Information System (INIS)

Greenwald, Martin

2011-01-01

Many others in the fusion energy and advanced scientific computing communities participated in the development of this plan. The core planning team is grateful for their important contributions. This summary is meant as a quick overview the Fusion Simulation Program's (FSP's) purpose and intentions. There are several additional documents referenced within this one and all are supplemental or flow down from this Program Plan. The overall science goal of the DOE Office of Fusion Energy Sciences (FES) Fusion Simulation Program (FSP) is to develop predictive simulation capability for magnetically confined fusion plasmas at an unprecedented level of integration and fidelity. This will directly support and enable effective U.S. participation in International Thermonuclear Experimental Reactor (ITER) research and the overall mission of delivering practical fusion energy. The FSP will address a rich set of scientific issues together with experimental programs, producing validated integrated physics results. This is very well aligned with the mission of the ITER Organization to coordinate with its members the integrated modeling and control of fusion plasmas, including benchmarking and validation activities. (1). Initial FSP research will focus on two critical Integrated Science Application (ISA) areas: ISA1, the plasma edge; and ISA2, whole device modeling (WDM) including disruption avoidance. The first of these problems involves the narrow plasma boundary layer and its complex interactions with the plasma core and the surrounding material wall. The second requires development of a computationally tractable, but comprehensive model that describes all equilibrium and dynamic processes at a sufficient level of detail to provide useful prediction of the temporal evolution of fusion plasma experiments. The initial driver for the whole device model will be prediction and avoidance of discharge-terminating disruptions, especially at high performance, which are a critical

Binaural Pitch Fusion in Bilateral Cochlear Implant Users.

Science.gov (United States)

Reiss, Lina A J; Fowler, Jennifer R; Hartling, Curtis L; Oh, Yonghee

Binaural pitch fusion is the fusion of stimuli that evoke different pitches between the ears into a single auditory image. Individuals who use hearing aids or bimodal cochlear implants (CIs) experience abnormally broad binaural pitch fusion, such that sounds differing in pitch by as much as 3-4 octaves are fused across ears, leading to spectral averaging and speech perception interference. The goal of this study was to determine if adult bilateral CI users also experience broad binaural pitch fusion. Stimuli were pulse trains delivered to individual electrodes. Fusion ranges were measured using simultaneous, dichotic presentation of reference and comparison stimuli in opposite ears, and varying the comparison stimulus to find the range that fused with the reference stimulus. Bilateral CI listeners had binaural pitch fusion ranges varying from 0 to 12 mm (average 6.1 ± 3.9 mm), where 12 mm indicates fusion over all electrodes in the array. No significant correlations of fusion range were observed with any subject factors related to age, hearing loss history, or hearing device history, or with any electrode factors including interaural electrode pitch mismatch, pitch match bandwidth, or within-ear electrode discrimination abilities. Bilateral CI listeners have abnormally broad fusion, similar to hearing aid and bimodal CI listeners. This broad fusion may explain the variability of binaural benefits for speech perception in quiet and in noise in bilateral CI users.

DOE Handbook: Supplementary guidance and design experience for the fusion safety standards DOE-STD-6002-96 and DOE-STD-6003-96

International Nuclear Information System (INIS)

1999-01-01

Two standards have been developed that pertain to the safety of fusion facilities. These are DOE- STD-6002-96, Safety of Magnetic Fusion Facilities: Requirements, and DOE-STD-6003-96, Safety of Magnetic Fusion Facilities: Guidance. The first of these standards identifies requirements that subscribers to that standard must meet to achieve safety in fusion facilities. The second standard contains guidance to assist in meeting the requirements identified inthefirst This handbook provides additional documentation on good operations and design practices as well as lessons learned from the experiences of designers and operators of previous fusion facilities and related systems. It is intended to capture the experience gained in the various fields and pass it on to designers of future fusion facilities as a means of enhancing success and safeiy. The sections of this document are presented according to the physical location of the major systems of a t%sion facility, beginning with the vacuum vessel and proceeding to those systems and components outside the vacuum vessel (the ''Ex-vessel Systems''). The last section describes administrative procedures that cannot be localized to specific components. It has been tacitly assumed that the general structure of the fusion facilities addressed is that of a tokamak though the same principles would apply to other magnetic confinement options

The influence of asymmetry on mix in direct-drive inertial confinement fusion experiments

International Nuclear Information System (INIS)

Christensen, C.R.; Wilson, D.C.; Barnes, Cris W.; Grim, G.P.; Morgan, G.L.; Wilke, M.D.; Marshall, F.J.; Glebov, V.Yu.; Stoeckl, C.

2004-01-01

The mix of shell material into the fuel of inertial confinement fusion (ICF) implosions is thought to be a major cause of the failure of most ICF experiments to achieve the fusion yield predicted by computer codes. Implosion asymmetry is a simple measurable quantity that is expected to affect the mix. In order to measure the coupling of asymmetry to mix in ICF implosions, we have performed experiments on the OMEGA laser [T. R. Boehly et al., Rev. Sci. Instrum. 66, 508 (1995)] that vary the energy of each of the sixty beams individually to achieve a given fraction of L2, the second-order Legendre polynomial. Prolate, symmetric, and oblate implosions resulted. Three different fill pressures were used. Simultaneous x-ray and neutron images were obtained. The experiments were modeled with a radiation/hydrodynamics code using the multi-fluid interpenetration mix model of Scannapieco and Cheng. It fits the data well with a single value of its one adjustable parameter (0.07±0.01). This agreement is demonstrated by neutron yield, x-ray images, neutron images, and ion temperatures. The degree of decline of the neutron yield with asymmetry at different fill pressures provides a hard constraint on ICF mix modeling

First downscattered neutron images from Inertial Confinement Fusion experiments at the National Ignition Facility

Directory of Open Access Journals (Sweden)

Guler Nevzat

2013-11-01

Full Text Available Inertial Confinement Fusion experiments at the National Ignition Facility (NIF are designed to understand and test the basic principles of self-sustaining fusion reactions by laser driven compression of deuterium-tritium (DT filled cryogenic plastic (CH capsules. The experimental campaign is ongoing to tune the implosions and characterize the burning plasma conditions. Nuclear diagnostics play an important role in measuring the characteristics of these burning plasmas, providing feedback to improve the implosion dynamics. The Neutron Imaging (NI diagnostic provides information on the distribution of the central fusion reaction region and the surrounding DT fuel by collecting images at two different energy bands for primary (13–15 MeV and downscattered (10–12 MeV neutrons. From these distributions, the final shape and size of the compressed capsule can be estimated and the symmetry of the compression can be inferred. The first downscattered neutron images from imploding ICF capsules are shown in this paper.

First downscattered neutron images from Inertial Confinement Fusion experiments at the National Ignition Facility

Science.gov (United States)

Guler, Nevzat; Aragonez, Robert J.; Archuleta, Thomas N.; Batha, Steven H.; Clark, David D.; Clark, Deborah J.; Danly, Chris R.; Day, Robert D.; Fatherley, Valerie E.; Finch, Joshua P.; Gallegos, Robert A.; Garcia, Felix P.; Grim, Gary; Hsu, Albert H.; Jaramillo, Steven A.; Loomis, Eric N.; Mares, Danielle; Martinson, Drew D.; Merrill, Frank E.; Morgan, George L.; Munson, Carter; Murphy, Thomas J.; Oertel, John A.; Polk, Paul J.; Schmidt, Derek W.; Tregillis, Ian L.; Valdez, Adelaida C.; Volegov, Petr L.; Wang, Tai-Sen F.; Wilde, Carl H.; Wilke, Mark D.; Wilson, Douglas C.; Atkinson, Dennis P.; Bower, Dan E.; Drury, Owen B.; Dzenitis, John M.; Felker, Brian; Fittinghoff, David N.; Frank, Matthias; Liddick, Sean N.; Moran, Michael J.; Roberson, George P.; Weiss, Paul; Buckles, Robert A.; Cradick, Jerry R.; Kaufman, Morris I.; Lutz, Steve S.; Malone, Robert M.; Traille, Albert

2013-11-01

Inertial Confinement Fusion experiments at the National Ignition Facility (NIF) are designed to understand and test the basic principles of self-sustaining fusion reactions by laser driven compression of deuterium-tritium (DT) filled cryogenic plastic (CH) capsules. The experimental campaign is ongoing to tune the implosions and characterize the burning plasma conditions. Nuclear diagnostics play an important role in measuring the characteristics of these burning plasmas, providing feedback to improve the implosion dynamics. The Neutron Imaging (NI) diagnostic provides information on the distribution of the central fusion reaction region and the surrounding DT fuel by collecting images at two different energy bands for primary (13-15 MeV) and downscattered (10-12 MeV) neutrons. From these distributions, the final shape and size of the compressed capsule can be estimated and the symmetry of the compression can be inferred. The first downscattered neutron images from imploding ICF capsules are shown in this paper.

A review of fusion breeder blanket technology, part 1

International Nuclear Information System (INIS)

Jackson, D.P.; Selander, W.N.; Townes, B.M.

1985-01-01

This report presents the results of a study of fusion breeder blanket technology. It reviews the role of the breeder blanket, the current understanding of the scientific and engineering bases of liquid metal and solid breeder blankets and the programs now underway internationally to resolve the uncertainities in current knowledge. In view of existing national expertise and experience, a solid breeder R and D program for Canada is recommended

High convergence, indirect drive inertial confinement fusion experiments at Nova

International Nuclear Information System (INIS)

Lerche, R.A.; Cable, M.D.; Hatchett, S.P.; Caird, J.A.; Kilkenny, J.D.; Kornblum, H.N.; Lane, S.M.; Laumann, C.; Murphy, T.J.; Murray, J.; Nelson, M.B.; Phillion, D.W.; Powell, H.; Ress, D.

1996-01-01

High convergence, indirect drive implosion experiments have been done at the Nova Laser Facility. The targets were deuterium and deuterium/tritium filled, glass microballoons driven symmetrically by x rays produced in a surrounding uranium hohlraum. Implosions achieved convergence ratios of 24:1 with fuel densities of 19 g/cm 3 ; this is equivalent to the range required for the hot spot of ignition scale capsules. The implosions used a shaped drive and were well characterized by a variety of laser and target measurements. The primary measurement was the fuel density using the secondary neutron technique (neutrons from the reaction 2 H( 3 H,n) 4 He in initially pure deuterium fuel). Laser measurements include power, energy and pointing. Simultaneous measurement of neutron yield, fusion reaction rate, and x-ray images provide additional information about the implosion process. Computer models are in good agreement with measurement results. copyright 1996 American Institute of Physics

JAERI contribution to the 19th IAEA Fusion Energy Conference

International Nuclear Information System (INIS)

2003-03-01

This report compiles the contributed papers and presentation materials from JAERI to the 19th IAEA Fusion Energy Conference held at Lyon, France, from October 14th to 19th, 2002. The papers describe the recent progress in the experimental research in JT-60U and JFT-2M tokamaks, theoretical studies, fusion technology and R and D for ITER and fusion reactors. Total 32 papers consist of 1 overview talk, 14 oral and 17 poster presentations. Eight papers written by authors from other institutes and universities under collaboration with JAERI are also included. The 40 of the presented papers are indexed individually. (J.P.N.)