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Sample records for s10fs-4 reactor

  1. Single d-metal atoms on F(s) and F(s+) defects of MgO(001): a theoretical study across the periodic table.

    Science.gov (United States)

    Neyman, Konstantin M; Inntam, Chan; Matveev, Alexei V; Nasluzov, Vladimir A; Rösch, Notker

    2005-08-24

    Single d-metal atoms on oxygen defects F(s) and F(s+) of the MgO(001) surface were studied theoretically. We employed an accurate density functional method combined with cluster models, embedded in an elastic polarizable environment, and we applied two gradient-corrected exchange-correlation functionals. In this way, we quantified how 17 metal atoms from groups 6-11 of the periodic table (Cu, Ag, Au; Ni, Pd, Pt; Co, Rh, Ir; Fe, Ru, Os; Mn, Re; and Cr, Mo, W) interact with terrace sites of MgO. We found bonding with F(s) and F(s+) defects to be in general stronger than that with O2- sites, except for Mn-, Re-, and Fe/F(s) complexes. In M/F(s) systems, electron density is accumulated on the metal center in a notable fashion. The binding energy on both kinds of O defects increases from 3d- to 4d- to 5d-atoms of a given group, at variance with the binding energy trend established earlier for the M/O2- complexes, 4d period, group 7 atoms are slightly destabilized compared to their group 6 congeners in both the F(s) and F(s+) complexes; for later transition elements, the binding energy increases gradually up to group 10 and finally decreases again in group 11, most strongly on the F(s) site. This trend is governed by the negative charge on the adsorbed atoms. We discuss implications for an experimental detection of metal atoms on oxide supports based on computed core-level energies.

  2. Fs = μs Fn

    Directory of Open Access Journals (Sweden)

    Bruno Ministro

    2016-09-01

    Full Text Available http://dx.doi.org/10.5007/1807-9288.2016v12n1p195 Fs = μs Fn é uma releitura a três vozes dos Homeóstatos de José-Alberto Marques. Partindo do desmembramento e recomposição digital do material sonoro, testam-se, com base nas possibilidades oferecidas pelo cruzamento entre a plasticidade vocal e as ferramentas digitais de manipulação, as potencialidades combinatórias que uma obra desta natureza encerra.

  3. Submersion-Subcritical Safe Space (S4) reactor

    International Nuclear Information System (INIS)

    King, Jeffrey C.; El-Genk, Mohamed S.

    2006-01-01

    The Submersion-Subcritical Safe Space (S 4 ) reactor, developed for future space power applications and avoidance of single point failures, is presented. The S 4 reactor has a Mo-14% Re solid core, loaded with uranium nitride fuel, cooled by He-30% Xe and sized to provide 550 kWth for 7 years of equivalent full power operation. The beryllium oxide reflector of the S 4 reactor is designed to completely disassemble upon impact on water or soil. The potential of using Spectral Shift Absorber (SSA) materials in different forms to ensure that the reactor remains subcritical in the worst-case submersion accident is investigated. Nine potential SSAs are considered in terms of their effect on the thickness of the radial reflector and on the combined mass of the reactor and the radiation shadow shield. The SSA materials are incorporated as a thin (0.1 mm) coating on the outside surface of the reactor core and as core additions in three possible forms: 2.0 mm diameter pins in the interstices of the core block, 0.25 mm thick sleeves around the fuel stacks and/or additions to the uranium nitride fuel. Results show that with a boron carbide coating and 0.25 mm iridium sleeves around the fuel stacks the S 4 reactor has a reflector outer diameter of 43.5 cm with a combined reactor and shadow shield mass of 935.1 kg. The S 4 reactor with 12.5 at.% gadolinium-155 added to the fuel, 2.0 mm diameter gadolinium-155 sesquioxide interstitial pins, and a 0.1 mm thick gadolinium-155 sesquioxide coating has a slightly smaller reflector outer diameter of 43.0 cm, resulting in a smaller total reactor and shield mass of 901.7 kg. With 8.0 at.% europium-151 added to the fuel, along with europium-151 sesquioxide for the pins and coating, the reflector's outer diameter and the total reactor and shield mass are further reduced to 41.5 cm and 869.2 kg, respectively

  4. Controlling S2 terminal using FS software

    Science.gov (United States)

    Xue, Zhuhe

    New S2FS software for controlling S2 terminal of Sheshan station has been developed. It works under Field System software. All S2 operation commands are incorporated in a station program. The interface of SWT computer and S2 terminal is RS232 interface. S2FS software is designed by using Shell and C language. It has been used in VSOP experiments.

  5. Trichoderma reesei FS10-C enhances phytoremediation of Cd-contaminated soil by Sedum plumbizincicola and associated soil microbial activities

    Science.gov (United States)

    Teng, Ying; Luo, Yang; Ma, Wenting; Zhu, Lingjia; Ren, Wenjie; Luo, Yongming; Christie, Peter; Li, Zhengao

    2015-01-01

    This study aimed to explore the effects of Trichoderma reesei FS10-C on the phytoremediation of Cd-contaminated soil by the hyperaccumulator Sedum plumbizincicola and on soil fertility. The Cd tolerance of T. reesei FS10-C was characterized and then a pot experiment was conducted to investigate the growth and Cd uptake of S. plumbizincicola with the addition of inoculation agents in the presence and absence of T. reesei FS10-C. The results indicated that FS10-C possessed high Cd resistance (up to 300 mg L-1). All inoculation agents investigated enhanced plant shoot biomass by 6–53% of fresh weight and 16–61% of dry weight and Cd uptake by the shoots by 10–53% compared with the control. All inoculation agents also played critical roles in increasing soil microbial biomass and microbial activities (such as biomass C, dehydrogenase activity and fluorescein diacetate hydrolysis activity). Two inoculation agents accompanied by FS10-C were also superior to the inoculation agents, indicating that T. reesei FS10-C was effective in enhancing both Cd phytoremediation by S. plumbizincicola and soil fertility. Furthermore, solid fermentation powder of FS10-C showed the greatest capacity to enhance plant growth, Cd uptake, nutrient release, microbial biomass and activities, as indicated by its superior ability to promote colonization by Trichoderma. The solid fermentation powder of FS10-C might serve as a suitable inoculation agent for T. reesei FS10-C to enhance both the phytoremediation efficiency of Cd-contaminated soil and soil fertility. PMID:26113858

  6. Quick Look Report for Semiscale MOD-2C Test S-FS-2

    International Nuclear Information System (INIS)

    Boucher, T.J.; Chen, T.H.

    1985-01-01

    Results of a preliminary analysis of the first test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-2 simulated a pressurized water reactor transient initiated by a double-ended offset shear of a steam generator main steam line upstream of the flow restrictor. Initial conditions represented normal ''hot-standby'' operation. The transient included an initial 600-s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant at conditions required to allow a natural circulation cooldown. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overcooling and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overcooling and primary-to-secondary heat transfer. 57 figs., 3 tabs

  7. Fast Spectrum Molten Salt Reactor Options

    Energy Technology Data Exchange (ETDEWEB)

    Gehin, Jess C [ORNL; Holcomb, David Eugene [ORNL; Flanagan, George F [ORNL; Patton, Bruce W [ORNL; Howard, Rob L [ORNL; Harrison, Thomas J [ORNL

    2011-07-01

    During 2010, fast-spectrum molten-salt reactors (FS-MSRs) were selected as a transformational reactor concept for light-water reactor (LWR)-derived heavy actinide disposition by the Department of Energy-Nuclear Energy Advanced Reactor Concepts (ARC) program and were the subject of a preliminary scoping investigation. Much of the reactor description information presented in this report derives from the preliminary studies performed for the ARC project. This report, however, has a somewhat broader scope-providing a conceptual overview of the characteristics and design options for FS-MSRs. It does not present in-depth evaluation of any FS-MSR particular characteristic, but instead provides an overview of all of the major reactor system technologies and characteristics, including the technology developments since the end of major molten salt reactor (MSR) development efforts in the 1970s. This report first presents a historical overview of the FS-MSR technology and describes the innovative characteristics of an FS-MSR. Next, it provides an overview of possible reactor configurations. The following design features/options and performance considerations are described including: (1) reactor salt options-both chloride and fluoride salts; (2) the impact of changing the carrier salt and actinide concentration on conversion ratio; (3) the conversion ratio; (4) an overview of the fuel salt chemical processing; (5) potential power cycles and hydrogen production options; and (6) overview of the performance characteristics of FS-MSRs, including general comparative metrics with LWRs. The conceptual-level evaluation includes resource sustainability, proliferation resistance, economics, and safety. The report concludes with a description of the work necessary to begin more detailed evaluation of FS-MSRs as a realistic reactor and fuel cycle option.

  8. Sub-fs electron bunch generation with sub-10-fs bunch arrival-time jitter via bunch slicing in a magnetic chicane

    Directory of Open Access Journals (Sweden)

    J. Zhu

    2016-05-01

    Full Text Available The generation of ultrashort electron bunches with ultrasmall bunch arrival-time jitter is of vital importance for laser-plasma wakefield acceleration with external injection. We study the production of 100-MeV electron bunches with bunch durations of subfemtosecond (fs and bunch arrival-time jitters of less than 10 fs, in an S-band photoinjector by using a weak magnetic chicane with a slit collimator. The beam dynamics inside the chicane is simulated by using two codes with different self-force models. The first code separates the self-force into a three-dimensional (3D quasistatic space-charge model and a one-dimensional coherent synchrotron radiation (CSR model, while the other one starts from the first principle with a so-called 3D sub-bunch method. The simulations indicate that the CSR effect dominates the horizontal emittance growth and the 1D CSR model underestimates the final bunch duration and emittance because of the very large transverse-to-longitudinal aspect ratio of the sub-fs bunch. Particularly, the CSR effect is also strongly affected by the vertical bunch size. Due to the coupling between the horizontal and longitudinal phase spaces, the bunch duration at the entrance of the last dipole magnet of the chicane is still significantly longer than that at the exit of the chicane, which considerably mitigates the impact of space charge and CSR effects on the beam quality. Exploiting this effect, a bunch charge of up to 4.8 pC in a sub-fs bunch could be simulated. In addition, we analytically and numerically investigate the impact of different jitter sources on the bunch arrival-time jitter downstream of the chicane, and define the tolerance budgets assuming realistic values of the stability of the linac for different bunch charges and compression schemes.

  9. Pretest analysis document for Test S-FS-6

    International Nuclear Information System (INIS)

    Shaw, R.A.; Hall, D.G.

    1985-05-01

    This report documents the pretest analyses completed for Semiscale Test S-FS-6. This test will simulate a transient initiated by a 100% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represent normal operating conditions for a C-E System 80 nuclear power plant. Predictions of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The enclosed analyses include a RELAP5/MOD2/CY21 code calculation and preliminary results from a facility hot, integrated test which was conducted to near S-FS-6 specifications. The results of these analyses indicate that the test objectives for Test S-FS-6 can be achieved. The primary system overpressurization will pose no threat to personnel or plant integrity

  10. Study of core characteristics on fuel and coolant type. Results of F/S phase-I

    International Nuclear Information System (INIS)

    Ikegami, Tetsuo; Hayashi, Hideyuki; Sasaki, Makoto; Mizuno, Tomoyasu; Yamadate, Megumi; Takaki, Naoyuki; Kurosawa, Norifumi; Sakashita, Yoshiaki; Naganuma, Masayuki

    2001-03-01

    The phase-I of the Feasibility Study of Commercialized Fast Reactor Cycle Systems (F/S) were started from July, 1999 and terminated at the end of FY2000 in order to executed examination about technology alternatives of various commercialized fast reactor (FR) recycle concepts, in response to the JNC middle long term enterprise plan. In the phase-I of this F/S, a number of conceptual candidates have been selected from the following 5 viewpoints: a) ensuring safety, b) economic competitiveness to future LWRs, c) efficient utilization of resources, d) reduction of environmental burden, e) enhancement of nuclear non-proliferation. As for this study from the above viewpoints, core characteristics of many kinds of reactors have been investigated, analyzed and examined a core / a fuel characteristic in the combinations of fuel and coolant types and power output scales. Based on these results, R and D plans of the phase-II to be performed have been proposed, and a database to select candidate reactor concepts has been prepared. The conclusions have been obtained in the phase-I are as follows: (1) Evaluation of a fuel form in every each coolant was compared. A promising fuel form was extracted as follows: an oxide and a metal fuel for sodium coolant cores, a metal and a nitride fuel for heavy metal coolant cores, an oxide and a nitride fuel for carbon dioxide coolant cores and a nitride fuel for He gas coolant cores. (2) As the general idea that performance of a core nucleus can be compatible with re-criticality evasion in sodium coolant large-sized oxide fuel cores, a axial blanket particle elimination radial heterogeneous core is one influential candidate. (3) In case of Pb-Bi coolant nature circulation medium size core with an oxide fuel, it is difficult to simultaneously achieve higher discharged burn-up and higher breeding ratio according to the viewpoints of the phase-I. (4) Core characteristics of a carbon dioxide coolant core shows to be almost equivalent to that of

  11. Expression of chemokine CXCL12 and its receptor CXCR4 in folliculostellate (FS) cells of the rat anterior pituitary gland: the CXCL12/CXCR4 axis induces interconnection of FS cells.

    Science.gov (United States)

    Horiguchi, Kotaro; Ilmiawati, Cimi; Fujiwara, Ken; Tsukada, Takehiro; Kikuchi, Motoshi; Yashiro, Takashi

    2012-04-01

    The anterior pituitary gland is composed of five types of hormone-producing cells plus folliculostellate (FS) cells, which do not produce classical anterior pituitary hormones. FS cells are interconnected by cytoplasmic processes and encircle hormone-producing cells or aggregate homophilically. Using living-cell imaging of primary culture, we recently reported that some FS cells precisely extend their cytoplasmic processes toward other FS cells and form interconnections with them. These phenomena suggest the presence of a chemoattractant factor that facilitates the interconnection. In this study, we attempted to discover the factor that induces interconnection of FS cells and succeeded in identifying chemokine (CXC)-L12 and its receptor CXCR4 as potential candidate molecules. CXCL12 is a chemokine of the CXC subfamily. It exerts its effects via CXCR4, a G protein-coupled receptor. The CXCL12/CXCR4 axis is a potent chemoattractant for many types of neural cells. First, we revealed that CXCL12 and CXCR4 are expressed by FS cells in rat anterior pituitary gland. Next, to clarify the function of the CXCL12/CXCR4 axis in FS cells, we observed living anterior pituitary cells in primary culture with specific CXCL12 inhibitor or CXCR4 antagonist and noted that extension of cytoplasmic processes and interconnection of FS cells were inhibited. Finally, we examined FS cell migration and invasion by using Matrigel matrix assays. CXCL12 treatment resulted in markedly increased FS cell migration and invasion. These data suggest that FS cells express chemokine CXCL12 and its receptor CXCR4 and that the CXCL12/CXCR4 axis evokes interconnection of FS cells.

  12. Quick look report for semiscale MOD-2C Test S-FS-11

    International Nuclear Information System (INIS)

    Plessinger, M.P.

    1985-11-01

    Results of a preliminary analysis of the fifth test performed in the Semiscale MOD-2C Steam Generator Feedwater and Steam Line Break (FS) experiment series are presented. Test S-FS-11 simulated a pressurized water reactor transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. With the exception of primary pressure, the initial conditions represented the initial conditions used for the C-E System 80 Final Safety Analysis Report (FSAR) Appendix 15B calculations. The transient included an initial 600 s period in which only automatic plant protection systems responded to the initiating event. This period was followed by a series of operator actions necessary to stabilize the plant followed by break isolation and affected loop steam generator refill with auxiliary feedwater. The test results provided a measured evaluation of the effectiveness of the automatic responses in minimizing primary system overpressurization and operator actions in stabilizing the plant. Test data also provided a basis for comparison with other tests in the series of the effects of break size on primary overpressurization and primary-to-secondary heat transfer. 64 figs

  13. The concept of the sodium cooled small fast reactor 4S and the analyses of the loss of flow events

    International Nuclear Information System (INIS)

    Nishi, Yoshihisa; Ueda, Nobuyuki; Koga, Tomonari; Matsumiya, Hisato

    2007-01-01

    CRIEPI has been developing the 4S reactor (Super Safe, Small and Simple reactor) for application in dispersed energy supply and multipurpose use, in conjunction with Toshiba Corporation. The 4S is sodium cooled fast reactor and their electrical output has two options of 10MWe and 50MWe. In this paper, 10MWe 4S (4S-10M) was proposed. 4S-10M has some unique features. It employs a burn-up control system with annular reflector in place of the control rod that requires the frequent maintenance service. The core life time of the 4S-10M is 30 years and the fuel transport is not required during core life time. All temperature feedback coefficients are negative during core life time. In the latest design for 4S-10M, a pool and tall type reactor design was selected to reduce the construction cost. Two types of decay heat removal system (Reactor Vessel Auxiliary Cooling System; RVACS, Intermediate Reactor Auxiliary Cooling System; IRACS) using natural convection power were adopted. It is necessary to confirm that these two heat removal system can operate appropriately. The transition analyses were executed by the CERES code to evaluate the design feasibility and the thermal hydraulic characteristics of the 4S-10M. CERES is a multi-dimensional plant dynamics simulation code for liquid metal reactors developed by the CRIEPI. CERES can perform simulations ranging from forced circulation (full/partial power operation) to natural circulation. Components (pumps, IHXs, SGs, pipings, etc.) of the reactor are modeled as one-dimensional. Multi-dimensional plena are connected to such components. Two loss-of-flow accident sequences are considered. In the first case, it is assumed that the primary and the secondary pump were stopped by the total station black out. The reactor shut down system was assumed to be success. This sequence is referred to as the protected loss-of-flow accident (PLOF). In the second case, it is assumed that the reactor shut down systems fail to operate and the

  14. Coulomb explosion of H2 induced by a sub-10 fs intense laser pulse

    International Nuclear Information System (INIS)

    Saugout, S.

    2006-12-01

    This work presents an experimental and theoretical study of the interaction of H2 with an intense sub-10 fs-laser pulse. The ejection of the two electrons of the molecule by the laser pulse leads to the fragmentation of the physical sys em in two protons. This process is called Coulomb Explosion. The electronic and nuclear dynamics can be analyzed by measuring the kinetic energy spectra as a function of different laser parameters. This dynamics is also analyzed through a non-perturbative, double active electron theoretical model, based on the resolution of the time dependent Schroedinger equation. In this model, the internuclear distance is treated as a quantum variable. The experimental and theoretical results enlight the translation of the kinetic energy spectra towards a higher energy when the pulse duration decreases. Experimentally, laser pulses from 40 to 10 fs were used and down to 1 fs using theoretical simulations. This study shows that, for laser pulses shorter than 4 fs, the carrier envelope phase becomes a crucial parameter. Furthermore, the molecular dynamics of H2 in intense laser field is sensitive to the peak intensity of the pulse. The experimental and theoretical results show that, as the intensity increases, the kinetic energy spectra are centered around a higher energy. In addition, the presence of two double ionization regimes is theoretically demonstrated for a pulse duration of 4 fs. The H 2 molecule is also sensitive to the temporal shape of the laser pulse. This sensitivity allows for the detection of pre- or post-pulses by measuring the experimental kinetic energy spectra. Finally, the different double ionization processes are studied. The results show that the electron rescattering influences the femtosecond nuclear dynamics. (author)

  15. Using S3 cloud storage with ROOT and CvmFS

    Science.gov (United States)

    Arsuaga-Ríos, María; Heikkilä, Seppo S.; Duellmann, Dirk; Meusel, René; Blomer, Jakob; Couturier, Ben

    2015-12-01

    Amazon S3 is a widely adopted web API for scalable cloud storage that could also fulfill storage requirements of the high-energy physics community. CERN has been evaluating this option using some key HEP applications such as ROOT and the CernVM filesystem (CvmFS) with S3 back-ends. In this contribution we present an evaluation of two versions of the Huawei UDS storage system stressed with a large number of clients executing HEP software applications. The performance of concurrently storing individual objects is presented alongside with more complex data access patterns as produced by the ROOT data analysis framework. Both Huawei UDS generations show a successful scalability by supporting multiple byte-range requests in contrast with Amazon S3 or Ceph which do not support these commonly used HEP operations. We further report the S3 integration with recent CvmFS versions and summarize the experience with CvmFS/S3 for publishing daily releases of the full LHCb experiment software stack.

  16. Pretest analysis document for Test S-FS-11

    International Nuclear Information System (INIS)

    Hall, D.G.; Shaw, R.A.

    1985-07-01

    This report documents the pretest calculations completed for Semiscale Test S-FS-11. This test will simulate a transient initiated by a 50% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represents normal operating conditions for a C-E System 80 nuclear plant. Prediction of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The results of a RELAP5/MOD2/CY21 code calculation indicate that the test objectives for Test S-FS-11 can be achieved. The primary system overpressurization will occur but pose no threat to personnel or plant integrity. 3 refs., 15 figs., 5 tabs

  17. Nb-base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging

    International Nuclear Information System (INIS)

    Leonard, Keith J.; Busby, Jeremy T.; Hoelzer, David T.; Zinkle, Steven J.

    2009-01-01

    The proposed use of fission reactors for manned or deep space missions have typically relied on the potential use of refractory metal alloys as structural materials. Throughout the history of these programs, the lead candidate has been Nb-1Zr due to its good fabrication and welding characteristics. However, the less than optimal creep resistance of this alloy has encouraged interest in the more complex FS-85 (Nb-28Ta-10W-1Zr) alloy. Despite this interest, a relatively small database exists for the properties of FS-85. These gaps include potential microstructural instabilities that can lead to mechanical property degradation. In this work, changes in microstructure and mechanical properties of FS-85 were investigated following 1100 h of thermal aging at 1098, 1248 and 1398 K. The changes in electrical resistivity, hardness and tensile properties between the as-annealed and aged materials are compared. Evaluation of the microstructural changes was performed through optical, scanning and transmission electron microscopy. The development of intragranular and grain boundary precipitation of Zr-rich compounds as a function of aging temperature was followed. Brittle tensile behavior was measured in the 1248 K aged material, while ductile behavior occurred in material aged above and below this temperature. The effect of temperature on the under and overaging of the grain boundary particles are believed to have contributed to the mechanical property behavior of the aged material

  18. Pretest analysis document for Test S-FS-7

    International Nuclear Information System (INIS)

    Hall, D.G.

    1985-06-01

    This report documents the pretest calculations completed for Semiscale Test S-FS-7. This test will simulate a transient initiated by a 14.3% break in a steam generator bottom feedwater line downstream of the check valve. The initial conditions represent normal operating conditions for a C-E System 80 nuclear power plant. Predictions of transients resulting from feedwater line breaks in these plants have indicated that significant primary system overpressurization may occur. The results of a RELAP5/MOD2/CY21 code calculation indicate that the test objectives for Test S-FS-7 can be achieved. The primary system overpressurization will occur but pose no threat to personnel or to plant integrity. 3 refs., 15 figs., 5 tabs

  19. Nb-Base FS-85 Alloy as a Candidate Structural Material for Space Reactor Applications: Effects of Thermal Aging

    Science.gov (United States)

    Leonard, Keith J.; Busby, Jeremy T.; Hoelzer, David T.; Zinkle, Steven J.

    2009-04-01

    The proposed uses of fission reactors for manned or deep space missions have typically relied on the potential use of refractory metal alloys as structural materials. Throughout the history of these programs, a leading candidate has been Nb-1Zr, due to its good fabrication and welding characteristics. However, the less-than-optimal creep resistance of this alloy has encouraged interest in the more complex FS-85 (Nb-28Ta-10W-1Zr) alloy. Despite this interest, only a relatively small database exists for the properties of FS-85. Database gaps include the potential microstructural instabilities that can lead to mechanical property degradation. In this work, changes in the microstructure and mechanical properties of FS-85 were investigated following 1100 hours of thermal aging at 1098, 1248, and 1398 K. The changes in electrical resistivity, hardness, and tensile properties between the as-annealed and aged materials are compared. Evaluation of the microstructural changes was performed through optical microscopy (OM), scanning electron microscopy (SEM), and transmission electron microscopy (TEM). The development of intragranular and grain-boundary precipitation of Zr-rich compounds as a function of aging temperature was followed. Brittle tensile behavior was measured in the material aged at 1248 K, while ductile behavior occurred in samples aged above and below this temperature. The effect of temperature on the under- and overaging of the grain-boundary particles is believed to have contributed to the mechanical property behavior of the aged materials.

  20. InterProScan Result: FS888414 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS888414 FS888414_1_ORF2 7BD3608BC4DF6C01 PRINTS PR01186 INTEGRINB 7.4e-10 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  1. Neutron Radiography at the RP-10 reactor

    International Nuclear Information System (INIS)

    Hinostrosa, H.; Ravello, Y.; Cornejo, N.; Mendoza, M.; Montoya, M.

    1992-01-01

    The facility of neutron radiography at the RP-10 peruvian research reactor is described. The factor of collimation L/D is 149; the Cadmium ratio for the gold in the inspection's area is 4.5, and the thermal neutrons flux on the sample is 3,14 x 10 6 n/cm 2 s (author). 5 refs. 5 fig

  2. Design study on sodium-cooled middle-scale modular reactor

    International Nuclear Information System (INIS)

    Shimakawa, Yoshio; Nibe, Nobuaki; Hori, Toru

    2002-05-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled middle-scale modular reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled middle-scale modular reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled middle-scale modular reactor performed in JFY2001, which is the first year of Phase 2. As the construction cost of the sodium-cooled middle-scale modular reactor, which has been constructed in Phase 1, was about 10% higher than that of the sodium-cooled large-scale reactor, a new concept of the middle-scale modular reactor, which is expected to be equal to the large-scale reactor from a viewpoint of economic competitiveness, has been re-constructed based on the design of the advanced loop type reactor. After that, fundamental specifications of main systems and components for the new concept have been set, and critical subjects related to safety, structural integrity, thermal hydraulics, operability, maintainability and economy have been examined and evaluated. As a result of this study, the plant concept of the sodium-cooled middle-scale modular reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  3. All-fiber interferometer-based repetition-rate stabilization of mode-locked lasers to 10-14-level frequency instability and 1-fs-level jitter over 1  s.

    Science.gov (United States)

    Kwon, Dohyeon; Kim, Jungwon

    2017-12-15

    We report on all-fiber Michelson interferometer-based repetition-rate stabilization of femtosecond mode-locked lasers down to 1.3×10 -14 frequency instability and 1.4 fs integrated jitter in a 1 s time scale. The use of a compactly packaged 10 km long single-mode fiber (SMF)-28 fiber link as a timing reference allows the scaling of phase noise at a 10 GHz carrier down to -80  dBc/Hz at 1 Hz Fourier frequency. We also tested a 500 m long low-thermal-sensitivity fiber as a reference and found that, compared to standard SMF-28 fiber, it can mitigate the phase noise divergence by ∼10  dB/dec in the 0.1-1 Hz Fourier frequency range. These results suggest that the use of a longer low-thermal-sensitivity fiber may achieve sub-femtosecond integrated timing jitter with sub-10 -14 -level frequency instability in repetition rate by a simple and robust all-fiber-photonic method.

  4. 10 CFR 51.52 - Environmental effects of transportation of fuel and waste-Table S-4.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental effects of transportation of fuel and waste... Environmental effects of transportation of fuel and waste—Table S-4. Under § 51.50, every environmental report... detailed analysis of the environmental effects of transportation of fuel and wastes to and from the reactor...

  5. InterProScan Result: FS873218 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873218 FS873218_6_ORF2 0A64BA7E960F39C4 PANTHER PTHR18958:SF308 gb def: Mus musculus 10 days neonate cereb...ellum cDNA, RIKEN full-length enriched library 7.7e-09 T IPR020683 unintegrated ...

  6. Pretest analysis document for Semiscale Test S-FS-1

    International Nuclear Information System (INIS)

    Chen, T.H.

    1985-02-01

    This report documents the pretest analysis calculation completed with the RELAP5/MOD2/CY21 code for Semiscale Test S-FS-1. The test will simulate the double-ended offset shear of the main steam line at the exit of the broken loop steam generator (downstream of the flow restrictor) and the subsequent plant recovery. The recovery portion of the test consists of a plant stabilization phase and a plant cooldown phase. The recovery procedures involve normal charging/letdown operation, pressurizer heater operation, secondary steam and feed of the unaffected steam generator, and pressurizer auxiliary spray. The test will be terminated after the unaffected steam generator and pressurizer pressures and liquid levels are stable, and the average priamry fluid temperature is stable at about 480 K (405 0 F) for at least 10 minutes

  7. InterProScan Result: FS895048 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895048 FS895048_5_ORF1 A78EA11E5E964520 PRINTS PR00385 P450 4.5e-10 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  8. Feasibility of processing the experimental breeder reactor-II driver fuel from the Idaho National Laboratory through Savannah River Site's H-Canyon facility

    Energy Technology Data Exchange (ETDEWEB)

    Magoulas, V. E. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2017-07-28

    Savannah River National Laboratory (SRNL) was requested to evaluate the potential to receive and process the Idaho National Laboratory (INL) uranium (U) recovered from the Experimental Breeder Reactor II (EBR-II) driver fuel through the Savannah River Site’s (SRS) H-Canyon as a way to disposition the material. INL recovers the uranium from the sodium bonded metallic fuel irradiated in the EBR-II reactor using an electrorefining process. There were two compositions of EBR-II driver fuel. The early generation fuel was U-5Fs, which consisted of 95% U metal alloyed with 5% noble metal elements “fissium” (2.5% molybdenum, 2.0% ruthenium, 0.3% rhodium, 0.1% palladium, and 0.1% zirconium), while the later generation was U-10Zr which was 90% U metal alloyed with 10% zirconium. A potential concern during the H-Canyon nitric acid dissolution process of the U metal containing zirconium (Zr) is the explosive behavior that has been reported for alloys of these materials. For this reason, this evaluation was focused on the ability to process the lower Zr content materials, the U-5Fs material.

  9. Design study on sodium-cooled large-scale reactor

    International Nuclear Information System (INIS)

    Shimakawa, Yoshio; Nibe, Nobuaki; Hori, Toru

    2002-05-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled large-scale reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2 of the F/S, it is planed to precede a preliminary conceptual design of a sodium-cooled large-scale reactor based on the design of the advanced loop type reactor. Through the design study, it is intended to construct such a plant concept that can show its attraction and competitiveness as a commercialized reactor. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2001, which is the first year of Phase 2. In the JFY2001 design study, a plant concept has been constructed based on the design of the advanced loop type reactor, and fundamental specifications of main systems and components have been set. Furthermore, critical subjects related to safety, structural integrity, thermal hydraulics, operability, maintainability and economy have been examined and evaluated. As a result of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  10. Bioremediation of polychlorinated-p-dioxins/dibenzofurans contaminated soil using simulated compost-amended landfill reactors under hypoxic conditions

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Wei-Yu; Wu, Jer-Horng, E-mail: enewujh@mail.ncku.edu.tw; Lin, Shih-Chiang; Chang, Juu-En

    2016-07-15

    Highlights: • We developed a new hypoxic reactor system for remediating PCDD/Fs. • We demonstrated effects of compost on the degradation of PCDD/Fs. • We uncovered microbial compositions and dynamics during the degradation of PCDD/Fs. - Abstract: Compost-amended landfill reactors were developed to reduce polychlorinated-p-dioxins and dibenzofurans (PCDD/Fs) in contaminated soils. By periodically recirculating leachate and suppling oxygen, the online monitoring of the oxidation reduction potential confirmed that the reactors were maintained under hypoxic conditions, with redox levels constantly fluctuating between −400 and +80 mV. The subsequent reactor operation demonstrated that PCDD/F degradation in soil could be facilitated by amending compost originating from the cow manure and waste sludge and that the degradation might be affected by the availability of easily degradable substrates in the soil and compost. The pyrosequencing analysis of V4/V5 regions of bacterial 16S rRNA genes suggested that species richness of the soil microbial community was increased by a factor of 1.37–1.61. Although the bacterial community varied with the compost origin and changed markedly during reactor operation, it was dominated by Alphaproteobacteria, Gammaproteobacteria, Actinobacteria, and Firmicutes. The aerotolerant anaerobic Sedimentibacter and Propionibacterium spp., and the uncultured Chloroflexi group could be temporarily induced to a high abundance by amending the cow manure compost; the bacterial growths were associated with the rapid degradation of PCDD/Fs. Overall, the novel bioremediation method for PCDD/F-contaminated soils using hypoxic conditions was effective, simple, energy saving, and thus easily practicable.

  11. Bioremediation of polychlorinated-p-dioxins/dibenzofurans contaminated soil using simulated compost-amended landfill reactors under hypoxic conditions

    International Nuclear Information System (INIS)

    Chen, Wei-Yu; Wu, Jer-Horng; Lin, Shih-Chiang; Chang, Juu-En

    2016-01-01

    Highlights: • We developed a new hypoxic reactor system for remediating PCDD/Fs. • We demonstrated effects of compost on the degradation of PCDD/Fs. • We uncovered microbial compositions and dynamics during the degradation of PCDD/Fs. - Abstract: Compost-amended landfill reactors were developed to reduce polychlorinated-p-dioxins and dibenzofurans (PCDD/Fs) in contaminated soils. By periodically recirculating leachate and suppling oxygen, the online monitoring of the oxidation reduction potential confirmed that the reactors were maintained under hypoxic conditions, with redox levels constantly fluctuating between −400 and +80 mV. The subsequent reactor operation demonstrated that PCDD/F degradation in soil could be facilitated by amending compost originating from the cow manure and waste sludge and that the degradation might be affected by the availability of easily degradable substrates in the soil and compost. The pyrosequencing analysis of V4/V5 regions of bacterial 16S rRNA genes suggested that species richness of the soil microbial community was increased by a factor of 1.37–1.61. Although the bacterial community varied with the compost origin and changed markedly during reactor operation, it was dominated by Alphaproteobacteria, Gammaproteobacteria, Actinobacteria, and Firmicutes. The aerotolerant anaerobic Sedimentibacter and Propionibacterium spp., and the uncultured Chloroflexi group could be temporarily induced to a high abundance by amending the cow manure compost; the bacterial growths were associated with the rapid degradation of PCDD/Fs. Overall, the novel bioremediation method for PCDD/F-contaminated soils using hypoxic conditions was effective, simple, energy saving, and thus easily practicable.

  12. Development of an innovative reflector drive mechanism using magnetic repulsion force for 4S reactor

    International Nuclear Information System (INIS)

    Tsuji, K.; Watanabe, M.; Inagaki, H.; Nishikawa, A.; Takahashi, H.; Wakamatsu, M.; Matsumiya, H.; Nishiguchi, Y.

    2001-01-01

    A small sized fast reactor 4S: (Super Safe Small and Simple) which has a core of 10 - 30 years life time is controlled by reflectors. The reflector is required to be risen at very low speed to make up for the reactivity swing during operation. This report shows the development of an innovative reflector drive mechanism using magnetic repulsion force that can move at a several micrometer per one step. This drive mechanism has a passive shut down capability, and can eliminate reflector drive line. (author)

  13. EST Table: FS873739 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873739 E_FL_fner_51P23_R_0 10/09/28 100 %/172 aa ref|NP_001037572.1| translationa...pp0225303|DvirGJ10886-PA 10/08/29 44 %/180 aa F25H2.11#CE09656#WBGene00009122#locus:tct-1#TCTP protein#statu...s:Confirmed#UniProt:Q93573#protein_id:CAB02 099.1 10/09/10 73 %/172 aa AGAP002667

  14. EST Table: FS932533 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932533 E_FL_fwgP_34I10_F_0 10/09/28 96 %/124 aa ref|NP_001129358.1| osiris 21 [Bo...mbyx mori] gb|ACI23616.1| osiris 21 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 low homology 10/09/10 n.h 10/09/10 n.h FS930345 fwgP ...

  15. EST Table: FS930675 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS930675 E_FL_fwgP_28O10_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  16. EST Table: FS934649 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS934649 E_FL_fwgP_40K10_F_0 10/09/28 31 %/210 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 low homology 10/09/10 n.h 10/09/10 n.h FS923180 fwgP ...

  17. EST Table: FS809383 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS809383 E_FL_fmgV_28P15_F_0 10/09/28 91 %/173 aa ref|NP_001036831.1| saposin-relat...29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 39 %/158 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 fmgV ...

  18. EST Table: FS828361 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828361 E_FL_fmgV_28P15_R_0 10/09/28 92 %/173 aa ref|NP_001036831.1| saposin-relat...29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 39 %/158 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS895586 fmgV ...

  19. EST Table: FS935181 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS935181 E_FL_fwgP_42D15_F_0 10/09/28 40 %/118 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  20. EST Table: FS930504 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS930504 E_FL_fwgP_28G04_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  1. EST Table: FS938424 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS938424 E_FL_fwgP_51P06_F_0 10/09/28 39 %/128 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  2. EST Table: FS924814 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS924814 E_FL_fwgP_11K20_F_0 10/09/28 39 %/114 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  3. EST Table: FS938378 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS938378 E_FL_fwgP_51N02_F_0 10/09/28 40 %/120 aa ref|NP_001129360.1| osiris 9 [Bom...byx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS935058 fwgP ...

  4. EST Table: FS933330 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933330 E_FL_fwgP_36M07_F_0 10/09/28 100 %/103 aa ref|NP_001129360.1| osiris 9 [Bo...mbyx mori] gb|ACI23620.1| osiris 9 [Bombyx mori] 10/09/13 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS930560 fwgP ...

  5. EST Table: FS915156 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915156 E_FL_fufe_34G19_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  6. EST Table: FS906636 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906636 E_FL_fufe_08M11_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  7. EST Table: FS917709 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917709 E_FL_fufe_42C09_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  8. EST Table: FS908946 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908946 E_FL_fufe_15L23_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  9. EST Table: FS914517 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914517 E_FL_fufe_32I12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  10. EST Table: FS911186 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911186 E_FL_fufe_22H12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  11. EST Table: FS917981 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917981 E_FL_fufe_42P12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  12. EST Table: FS912711 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912711 E_FL_fufe_27A14_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  13. EST Table: FS916402 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916402 E_FL_fufe_38D15_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  14. EST Table: FS919976 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919976 E_FL_fufe_48P22_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  15. EST Table: FS911993 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911993 E_FL_fufe_24O22_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  16. EST Table: FS912253 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912253 E_FL_fufe_25L04_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  17. EST Table: FS917956 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917956 E_FL_fufe_42O09_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  18. EST Table: FS917447 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917447 E_FL_fufe_41G05_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  19. EST Table: FS914674 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914674 E_FL_fufe_32P17_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  20. EST Table: FS917785 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917785 E_FL_fufe_42F24_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  1. EST Table: FS904384 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS904384 E_FL_fufe_01N19_F_0 10/09/28 100 %/164 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  2. EST Table: FS904587 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS904587 E_FL_fufe_02H08_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  3. EST Table: FS919260 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919260 E_FL_fufe_46M19_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  4. EST Table: FS908267 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908267 E_FL_fufe_13L04_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  5. EST Table: FS912841 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912841 E_FL_fufe_27H01_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  6. EST Table: FS905814 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS905814 E_FL_fufe_06D23_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  7. EST Table: FS912585 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS912585 E_FL_fufe_26K20_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  8. EST Table: FS919646 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919646 E_FL_fufe_47P17_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  9. EST Table: FS908281 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908281 E_FL_fufe_13L21_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  10. EST Table: FS906986 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906986 E_FL_fufe_09N12_F_0 10/09/28 100 %/191 aa ref|NP_001098700.1| nanos-M [Bom...byx mori] dbj|BAF73619.1| nanos-M [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h FS918893 fufe ...

  11. EST Table: FS893327 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS893327 E_FL_ftes_11B24_R_0 10/09/28 87 %/134 aa ref|NP_001036831.1| saposin-relat...mology 10/09/10 35 %/119 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS895586 ftes ...

  12. Study on image quality and dosage comparison of F/S system and DR system

    International Nuclear Information System (INIS)

    Kim, Sun Chil; Jung, Jae Eun

    2003-01-01

    Currently, many hospital are hastening to introduce digital radiography systems. This is a direct result of the intentions to improve medical services and to digitalized radiology information systems, and is also leading to the improvement of medical imaging technology. Throughout F/S system's long history, many people have researched the image quality and dosage concerning these systems, and as a result, huge improvements in the dosage of patients were possible. Similarly, I believe that DR systems need the same kind of effort. Of course, decreases in dosage that ignore image quality are unthinkable. The results of experiments conducted by five hospitals during a period of 3 months brought to us the conclusions listed below. Based on the comparison and analysis of the exposure control of F/S systems and DR systems, DR systems generally showed higher exposure control for parts of the phantom that became thicker, and the exposure control improved rapidly as the thickness increased. DR systems still proved to be somewhat deficient in resolution measurements compared to existing F/S systems. The image processing part of DR systems contributed much to these result. Under conditions used clinically, the dosage measurements of DR systems were generally higher regardless of region. According to the evaluation of image quality, DR systems showed a higher degree of satisfaction as the thickness of the region became thinner. As mentioned above and based on the mutual relationship experiments between the dosage and image quality of F/S systems and DR systems, research to increase the satisfaction of DR systems must be considered

  13. EST Table: FS737373 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737373 E_FL_bmmt_08K06_R_0 10/09/28 37 %/161 aa ref|XP_002067709.1| GK12566 [Dros...ophila willistoni] gb|EDW78695.1| GK12566 [Drosophila willistoni] 10/09/03 37 %/161 aa FBpp0241709|DwilGK12566-PA 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS737272 bmmt ...

  14. EST Table: FS895588 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895588 E_FL_ftes_18N10_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 ftes ...

  15. EST Table: FS880548 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS880548 E_FL_ftes_18N10_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  16. EST Table: FS904516 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 1461 10/09/10 48 %/243 aa gnl|Amel|GB18846-PA 10/09/10 46 %/242 aa gi|91086187|ref|XP_971225.1| PREDICTED: similar to medulloblastoma...oblastoma antigen MU-MB-50.4 [Tribolium castaneum] gb|EFA06682.1| hypothetical prot...FS904516 E_FL_fufe_02D20_F_0 11/12/09 n.h 10/09/28 46 %/242 aa ref|XP_971225.1| PREDICTED: similar to medull

  17. EST Table: FS920143 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920143 E_FL_fufe_49H24_F_0 11/12/09 GO hit GO:0005874(microtubule)|GO:0007021(tub...:AGAP002130 10/09/10 59 %/109 aa gnl|Amel|GB17804-PA 10/09/10 60 %/109 aa gi|91091982|ref|XP_969241.1| PREDICTED: similar to AGAP002130-PA [Tribolium castaneum] FS920143 fufe ...

  18. EST Table: FS885453 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885453 E_FL_ftes_33C19_F_0 10/09/28 97 %/223 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 40 %/239 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ftes ...

  19. EST Table: FS798702 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS798702 E_FL_ffbm_28C11_F_0 10/09/28 89 %/278 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 52 %/117 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ffbm ...

  20. EST Table: FS795138 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS795138 E_FL_ffbm_17H02_F_0 10/09/28 92 %/267 aa ref|NP_001036831.1| saposin-relat...a gnl|Amel|GB16561-PA 10/09/10 55 %/106 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS791050 ffbm ...

  1. EST Table: FS871051 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available aa ref|NP_001139536.1| mortality factor 4-like [Bombyx mori] gb|ABJ99463.1| mrg15-like protein [Bombyx mori...FS871051 E_FL_fner_44F14_R_0 11/12/09 GO hit GO:0005634(nucleus) 10/09/28 100 %/257

  2. EST Table: FS875608 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875608 E_FL_ftes_04F20_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  3. EST Table: FS891805 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891805 E_FL_ftes_04F20_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 ftes ...

  4. EST Table: FS874950 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874950 E_FL_ftes_02G24_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 ftes ...

  5. EST Table: FS862828 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS862828 E_FL_fner_20A08_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fner ...

  6. EST Table: FS844168 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS844168 E_FL_fner_20A08_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fner ...

  7. EST Table: FS847583 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS847583 E_FL_fner_29M11_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fner ...

  8. EST Table: FS865993 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS865993 E_FL_fner_29M11_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fner ...

  9. EST Table: FS887803 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS887803 E_FL_ftes_40G04_F_0 10/09/28 35 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 35 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 ftes ...

  10. EST Table: FS900811 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS900811 E_FL_ftes_40G04_R_0 10/09/28 35 %/117 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/144 aa gnl|Amel|GB19565-PA 10/09/10 35 %/117 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS788262 ftes ...

  11. EST Table: FS915066 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915066 E_FL_fufe_34C05_F_0 10/09/28 35 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 35 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 fufe ...

  12. EST Table: FS737308 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737308 E_FL_bmmt_08H07_R_0 11/12/09 GO hit GO:0003678(DNA helicase activity)|GO:0...455:8982171:1|gene:AGAP010720 10/09/10 70 %/220 aa gnl|Amel|GB17337-PA 10/09/10 71 %/212 aa gi|189235245|ref...|XP_970366.2| PREDICTED: similar to pom1 [Tribolium castaneum] FS737308 bmmt ...

  13. EST Table: FS771324 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS771324 E_FL_fcaL_21P07_F_0 10/09/28 46 %/146 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/146 aa gnl|Amel|GB14856-PA 10/09/10 46 %/146 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fcaL ...

  14. EST Table: FS787608 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS787608 E_FL_fcaL_21P07_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fcaL ...

  15. EST Table: FS803374 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS803374 E_FL_fmgV_12D12_F_0 10/09/28 45 %/149 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/150 aa gnl|Amel|GB14856-PA 10/09/10 45 %/149 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fmgV ...

  16. EST Table: FS822360 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS822360 E_FL_fmgV_12D12_R_0 10/09/28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...46 %/151 aa gnl|Amel|GB14856-PA 10/09/10 46 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 fmgV ...

  17. EST Table: FS928974 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS928974 E_FL_fwgP_23N08_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fwgP ...

  18. EST Table: FS923051 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS923051 E_FL_fwgP_06G17_F_0 10/09/28 45 %/153 aa ref|XP_973163.1| PREDICTED: similar to jump...45 %/151 aa gnl|Amel|GB14856-PA 10/09/10 45 %/153 aa gi|91086783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS906679 fwgP ...

  19. EST Table: FS934225 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS934225 E_FL_fwgP_39G18_F_0 10/09/28 34 %/122 aa ref|XP_967620.1| PREDICTED: similar to anopheles stephen... %/149 aa gnl|Amel|GB19565-PA 10/09/10 34 %/122 aa gi|91093471|ref|XP_967620.1| PREDICTED: similar to anopheles stephensi ubiquitin, putative [Tribolium castaneum] FS914988 fwgP ...

  20. EST Table: FS750177 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS750177 E_ET_caL-_21J18_F_0 11/12/09 n.h 10/09/28 90 %/101 aa ref|NP_001036899.1| pro-corazon...in precursor [Bombyx mori] sp|Q86N75.1|CORZ_BOMMO RecName: Full=Pro-corazonin; Short=Crz; Short=B...CPRP; Flags: Precursor dbj|BAC66443.1| corazonin preprohormone [Bombyx mori] 10/09/08 n.h 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS750177 caL- ...

  1. EST Table: FS755944 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS755944 E_ET_caL-_21J18_R_0 11/12/09 n.h 10/09/28 91 %/101 aa ref|NP_001036899.1| pro-corazon...in precursor [Bombyx mori] sp|Q86N75.1|CORZ_BOMMO RecName: Full=Pro-corazonin; Short=Crz; Short=B...CPRP; Flags: Precursor dbj|BAC66443.1| corazonin preprohormone [Bombyx mori] 10/09/08 n.h 10/08/28 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h FS755944 caL- ...

  2. Application of WIMSD-4 for ''MARIA'' reactor lattice calculations

    International Nuclear Information System (INIS)

    Andrzejewski, K.; Kulikowska, T.

    1993-12-01

    A general description of the WIMSD-4 lattice code is given with the emphasis on available geometrical models. The difficulties encountered while modelling reactor lattices with the tubular type fuel elements are explained. Then the analysis of code options allowing to overcome these difficulties is carried out. Eventually, recommendations of options and input parameters for calculations of MARIA reactor lattice with satisfactory accuracy are given. During the work a set of modifications had to be introduced leading to a new code version called WIMS-S. Another version, under the name WIMS-T has been developed to allow for burnup calculations of the MARIA reactor lattice with improved resonance approach. (author). 14 refs, 6 figs, 10 tabs

  3. Pebble bed reactors simulation using MCNP: The Chinese HTR-10 reactor

    Directory of Open Access Journals (Sweden)

    SA Hosseini

    2013-09-01

    Full Text Available   Given the role of Gas-Graphite reactors as the fourth generation reactors and their recently renewed importance, in 2002 the IAEA proposed a set of Benchmarking problems. In this work, we propose a model both efficient in time and resources and exact to simulate the HTR-10 reactor using MCNP-4C code. During the present work, all of the pressing factors in PBM reactor design such as the inter-pebble leakage, fuel particle distribution and fuel pebble packing fraction effects have been taken into account to obtain an exact and easy to run model. Finally, the comparison between the results of the present work and other calculations made at INEEL proves the exactness of the proposed model.

  4. Neutron dose rate analysis on HTGR-10 reactor using Monte Carlo code

    Science.gov (United States)

    Suwoto; Adrial, H.; Hamzah, A.; Zuhair; Bakhri, S.; Sunaryo, G. R.

    2018-02-01

    The HTGR-10 reactor is cylinder-shaped core fuelled with kernel TRISO coated fuel particles in the spherical pebble with helium cooling system. The outlet helium gas coolant temperature outputted from the reactor core is designed to 700 °C. One advantage HTGR type reactor is capable of co-generation, as an addition to generating electricity, the reactor was designed to produce heat at high temperature can be used for other processes. The spherical fuel pebble contains 8335 TRISO UO2 kernel coated particles with enrichment of 10% and 17% are dispersed in a graphite matrix. The main purpose of this study was to analysis the distribution of neutron dose rates generated from HTGR-10 reactors. The calculation and analysis result of neutron dose rate in the HTGR-10 reactor core was performed using Monte Carlo MCNP5v1.6 code. The problems of double heterogeneity in kernel fuel coated particles TRISO and spherical fuel pebble in the HTGR-10 core are modelled well with MCNP5v1.6 code. The neutron flux to dose conversion factors taken from the International Commission on Radiological Protection (ICRP-74) was used to determine the dose rate that passes through the active core, reflectors, core barrel, reactor pressure vessel (RPV) and a biological shield. The calculated results of neutron dose rate with MCNP5v1.6 code using a conversion factor of ICRP-74 (2009) for radiation workers in the radial direction on the outside of the RPV (radial position = 220 cm from the center of the patio HTGR-10) provides the respective value of 9.22E-4 μSv/h and 9.58E-4 μSv/h for enrichment 10% and 17%, respectively. The calculated values of neutron dose rates are compliant with BAPETEN Chairman’s Regulation Number 4 Year 2013 on Radiation Protection and Safety in Nuclear Energy Utilization which sets the limit value for the average effective dose for radiation workers 20 mSv/year or 10μSv/h. Thus the protection and safety for radiation workers to be safe from the radiation source has

  5. EST Table: FS764450 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS764450 E_FL_fcaL_36N15_F_0 10/09/28 42 %/214 aa ref|XP_001945612.1| PREDICTED: similar to glucocerebro...608.1| PREDICTED: similar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS759318 fcaL ...

  6. Analyses of hypothetical nuclear criticality excursions in 10- and 20-MW freezer/sublimer vessels

    International Nuclear Information System (INIS)

    Haught, C.F.; Jordan, W.C.; Basoglu, B.; Dodds, H.L.; Wilkinson, A.D.

    1995-01-01

    A theoretical model is used to predict the consequences of a postulated hypothetical nuclear criticality excursion in a freezer/sublimer (F/S). Previous work has shown that an intrusion of water into a F/S may result in a critical configuration. A first attempt is made to model the neutronic and thermal-hydraulic phenomena occurring during a criticality excursion involving both uranium hexafluoride (UF 6 ) and uranyl fluoride (UO 2 F 2 ) solution, which is present in the F/S during upset conditions. The model employs point neutronics coupled with simple thermal hydraulics. Reactivity feedback from changes in the properties of the system are included in the model. The excursion is studied in a 10-MW F/S with an initial load of 3,500 kg of 5% weight enriched UF 6 and in a 20-MW F/S with an initial load of 6,800 kg of 2% weight enriched UF 6 . The magnitude of the fission release determined in this work is 5.93 x 10 18 fissions in the 10-MW F/S and 4.21 x 10 18 fissions in the 20-MW F/S. In order to demonstrate the reliability of the techniques used in this work, a limited validation study was conducted by comparing the fission release and peak fission rate determined by this work with experimental results for a limited number of experiments. The agreement between calculations and experiments in the validation study is considered to be satisfactory. The calculational results for the hypothetical accidents in the two F/S vessels appear reasonable

  7. EST Table: FS933547 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933547 E_FL_fwgP_37G10_F_0 10/09/28 56 %/205 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  8. Directed Acceleration of Electrons from a Solid Surface by Sub-10-fs Laser Pulses

    International Nuclear Information System (INIS)

    Brandl, F.; Hidding, B.; Osterholz, J.; Hemmers, D.; Pretzler, G.; Karmakar, A.; Pukhov, A.

    2009-01-01

    Electrons have been accelerated from solid target surfaces by sub-10-fs laser pulses of 120 μJ energy which were focused to an intensity of 2x10 16 W/cm 2 . The electrons have a narrow angular distribution, and their observed energies exceed 150 keV. We show that these energies are not to be attributed to collective plasma effects but are mainly gained directly via repeated acceleration in the transient field pattern created by incident and reflected laser, alternating with phase-shift-generating scattering events in the solid.

  9. Influence of remaining fission products in low-decontaminated fuel on reactor core characteristics

    International Nuclear Information System (INIS)

    Ohki, Shigeo

    2002-07-01

    Design study of core, fuel and related fuel cycle system with low-decontaminated fuel has been performed in the framework of the feasibility study (F/S) on commercialized fast reactor cycle systems. This report summarizes the influence on core characteristics of remaining fission products (FPs) in low-decontaminated fuel related to the reprocessing systems nominated in F/S phase I. For simple treatment of the remaining FPs in core neutronics calculation the representative nuclide method parameterized by the FP equivalent coefficient and the FP volume fraction was developed, which enabled an efficient evaluation procedure. As a result of the investigation on the sodium cooled fast reactor with MOX fuel designed in fiscal year 1999, it was found that the pyrochemical reprocessing with molten salt (the RIAR method) brought the largest influence. Nevertheless, it was still within the allowable range. Assuming an infinite-times recycling, the alternations in core characteristics were evaluated as follows: increment of burnup reactivity by 0.5%Δk/kk', decrement of breeding ratio by 0.04, increment of sodium void reactivity by 0.1x10 -2 Δk/kk' and decrement of Doppler constant (in absolute value) by 0.7x10 -3 Tdk/dT. (author)

  10. EST Table: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 E_FL_fcaL_03D22_R_0 11/12/09 GO hit GO:0004872(receptor activity)|GO:00054...n#status:Confirmed#UniProt:Q27874#protein_id:CAA84 677.1 10/09/10 30 %/244 aa AGAP000815-PA Protein|X:149373...2 aa gi|189241337|ref|XP_969214.2| PREDICTED: similar to integrin beta subunit (AGAP000815-PA) [Tribolium castaneum] FS773973 fcaL ...

  11. EST Table: FS732173 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS732173 E_FL_bmmt_25M21_F_0 10/09/28 70 %/116 aa ref|XP_002425199.1| conserved hyp...0 70 %/116 aa gi|91092740|ref|XP_973214.1| PREDICTED: similar to family with sequence similarity 108, member B1 [Tribolium castaneum] FS796084 bmmt ...

  12. Study of the RP-10 reactor neutron beam applied to the neutron radiography

    International Nuclear Information System (INIS)

    Zegarra, Manuel; Lopez, Alcides

    2013-01-01

    We have studied the RP-10 reactor radial neutron beam No. 3, which is used for neutron radiographies, by comparing radiograph's with and without the inner duct, and neutron flux determination with in flakes along the external duct, being the presence of photons creating signals at comparable levels of neutron effects, which reduce the quality of the analysis, values around 10 6 and 10 4 n/cm 2 s for thermal and epithermal flux were obtained respectively. It is recommended evaluate the design of the internal duct which presents strong photon emission. (authors).

  13. InterProScan Result: FS932793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932793 FS932793_2_ORF2 6EA452AE762D110F PANTHER PTHR12479:SF4 LYSOSOMAL-ASSOCIATED TRANSME...MBRANE PROTEIN 4.4e-71 T IPR018400 Lysosomal-associated transmembrane protein, CG14767-PB ...

  14. STECH,4(2), S/NO 10, MAY, 2015

    African Journals Online (AJOL)

    Balogun

    2015-05-10

    May 10, 2015 ... 0.2(g).the characteristic cycle of ground motion is 0.35(s)~ 0.4(s).Because .... The additional stress in the cushion bottom is shown as figure 1: ... perspective of theoretical research and practical pay equal attention to, with the.

  15. Research reactor`s role in Korea

    Energy Technology Data Exchange (ETDEWEB)

    Choi, C-O [Korea Atomic Energy Research Inst., Taejon (Korea, Republic of)

    1996-12-31

    After a TRIGA MARK-II was constructed in 1962, new research activity of a general nature, utilizing neutrons, prevailed in Korea. Radioisotopes produced from the MARK-II played a good role in the 1960`s in educating people as to what could be achieved by a neutron source. Because the research reactor had implanted neutron science in the country, another TRIGA MARK-III had to be constructed within 10 years after importing the first reactor, due to increased neutron demand from the nuclear community. With the sudden growth of nuclear power, however, the emphasis of research changed. For a while research activities were almost all oriented to nuclear power plant technology. However, the specifics of nuclear power plant technology created a need for a more highly capable research reactor like HANARO 30MWt. HANARO will perform well with irradiation testing and other nuclear programs in the future, including: production of key radioisotopes, doping of silicon by transmutation, neutron activation analysis, neutron beam experiments, cold neutron source. 3 tabs., 2 figs.

  16. Feasibility study on commercialized fast reactor cycle systems. Phase II final report

    International Nuclear Information System (INIS)

    Ieda, Yoshiaki; Uchikawa, Sadao; Okubo, Tsutomu; Ono, Kiyoshi; Kato, Atsushi; Kurisaka, Kenichi; Sakamoto, Yoshihiko; Sato, Kazujiro; Sato, Koji; Chikazawa, Yoshitaka; Nakai, Ryodai; Nakabayashi, Hiroki; Nakamura, Hirofumi; Namekawa, Takashi; Niwa, Hajime; Nomura, Kazunori; Hayashi, Hideyuki; Hayafune, Hiroki; Hirao, Kazunori; Mizuno, Tomoyasu; Muramatsu, Toshiharu; Ando, Masato; Ono, Katsumi; Ogata, Takanari; Kubo, Shigenobu; Kotake, Shoji; Sagayama, Yutaka; Takakuma, Katsuyuki; Tanaka, Toshihiko; Namba, Takashi; Fujii, Sumio; Muramatsu, Kazuyoshi

    2006-06-01

    A joint project team of Japan Atomic Energy Agency and the Japan Atomic Power Company (as the representative of the electric utilities) started the feasibility study on commercialized fast reactor cycle systems (F/S) in July 1999 in cooperation with Central Research Institute of Electric Power Industry and vendors. On the major premise of safety assurance, F/S aims to present an appropriate picture of commercialization of fast reactor (FR) cycle system which has economic competitiveness with light water reactor cycle systems and other electricity base load systems, and to establish FR cycle technologies for the future major energy supply. In the period from Japanese fiscal year (JFY) 1999 to 2000, the phase-I of F/S was carried out to screen our representative FR, reprocessing and fuel fabrication technologies. In the phase-II (JFY 2001-2005), the design study of FR cycle concepts, the development of significant technologies necessary for the feasibility evaluation, and the confirmation of key technical issues were performed to clarify the promising candidate concepts toward the commercialization. In this final phase-II report clarified the most promising concept, the R and D plan until around 2015, and the key issues for the commercialization. Based on the comprehensive evaluation in F/S, the combination of the sodium-cooled FR with MOX fuel core, the advanced-aqueous reprocessing process and the simplified-pelletizing fuel fabrication process was recommended as the mainline choice for the most promising concept. The concept exceeds in technical advancement, and the conformity to the development targets was higher compared with that of the others. Alternative technologies are prepared to be decrease the development risk of innovative technologies in the mainline choice. (author)

  17. Root colonization and growth promotion of sunflower (Helianthus annuus L.) by phosphate solubilizing Enterobacter sp. Fs-11.

    Science.gov (United States)

    Shahid, Muhammad; Hameed, Sohail; Imran, Asma; Ali, Saira; van Elsas, Jan Dirk

    2012-08-01

    An Enterobacter sp. Fs-11 was isolated from sunflower rhizosphere, identified on the basis of 16S rRNA gene sequence analysis (GeneBank accession no. GQ179978) and studied for its root colonization and growth promotion ability in sunflower. Morphologically, it was rod shaped Gram-negative, motile bacterium, producing 4.5 μg mL(-1) indole acetic acid in tryptophan-supplemented medium. It utilized 27 out of 95 substrates in BIOLOG GN2 micro plate system. It was able to convert insoluble tri-calcium phosphate to soluble phosphorus up to 43.5 μg mL(-1) with decrease in pH of the medium up to 4.5 after 10 days incubation at 28 ± 2 °C in the Pikovskaya's broth. High performance liquid chromatography of cell free supernatant showed that Fs-11 produced malic acid and gluconic acid (2.43 and 16.64 μg mL(-1), respectively) in Pikovskaya's broth. Analysis of 900 bp fragment of pyrroloquinoline quinine pqqE gene sequence showed 98 % homology with that of E. cloacae pqqE gene. Confocal laser scanning microscope revealed strong colonization of fluorescently labeled Fs-11 with sunflower roots. Sunflower inoculation with Fs-11 and its rifampicin resistant derivative in sterile sand and natural soil showed that Fs-11 colonized sunflower roots up to 30 days after transplanting in both sterile sand as well as natural soil. Moreover, Fs-11 inoculation resulted in increased plant height, fresh weight, dry weight and total phosphorus contents as compared to un-inoculated plants. The data showed that Enterobacter sp. Fs-11 is an efficient phosphate solubilizing and plant growth promoting rhizobacterium and has great potential to be used as bio-inoculant for sunflower under phosphorus deficient conditions.

  18. Comparison of SeaWiFS measurements of the Moon with the U.S. Geological Survey lunar model.

    Science.gov (United States)

    Barnes, Robert A; Eplee, Robert E; Patt, Frederick S; Kieffer, Hugh H; Stone, Thomas C; Meister, Gerhard; Butler, James J; McClain, Charles R

    2004-11-01

    The Sea-Viewing Wide-Field-of-View Sensor (SeaWiFS) has made monthly observations of the Moon since 1997. Using 66 monthly measurements, the SeaWiFS calibration team has developed a correction for the instrument's on-orbit response changes. Concurrently, a lunar irradiance model has been developed by the U.S. Geological Survey (USGS) from extensive Earth-based observations of the Moon. The lunar irradiances measured by SeaWiFS are compared with the USGS model. The comparison shows essentially identical response histories for SeaWiFS, with differences from the model of less than 0.05% per thousand days in the long-term trends. From the SeaWiFS experience we have learned that it is important to view the entire lunar image at a constant phase angle from measurement to measurement and to understand, as best as possible, the size of each lunar image. However, a constant phase angle is not required for using the USGS model. With a long-term satellite lunar data set it is possible to determine instrument changes at a quality level approximating that from the USGS lunar model. However, early in a mission, when the dependence on factors such as phase and libration cannot be adequately determined from satellite measurements alone, the USGS model is critical to an understanding of trends in instruments that use the Moon for calibration. This is the case for SeaWiFS.

  19. Wet storage of nuclear spent fuel from nuclear research reactor WWR-S

    International Nuclear Information System (INIS)

    Dragolici, A. C; Zorliu, A.; Petran, C.; Mincu, I.

    2001-01-01

    Nuclear research reactor WWR-S of IFIN-HH was commissioned on 29 July 1957 and shut down on December 1997. Now it is in Conservation State. During 40 years , the reactor was operated about 150,000 hours at variable power level ranging within 5 W and 3500 kW, and producing a total power of 9,510 MWday. After 20 years of operation a large number of spent fuel elements became available for storage exceeding the stocking capacity of the small cooling pond near reactor. Therefore, in 1980 the nuclear spent fuel repository was commissioned that contains at present all the fuel elements burnt in the reactor during years, minus 51 S-36 fuel assemblies which are conserved in the cooling pond. This repository contains 4 identical ponds, each of them having the storage capacity of 60 fuel assemblies. Every pond having the outer sizes of 2,750 mm (length) x 900 mm (breadth) x 5,700 mm (depth), is made from a special aluminum alloy (AlMg 3 ), with the walls thickness of 10 mm and bottom thickness of 15 mm. Pond's lids are made of cast iron having the thickness of 500 mm; they provide only the biological protection for the maintenance personnel. A 1.5 m concrete layer ensures the biological protection of the ponds. Over the fuel elements in every pond a 4.5 m water layer is provided, playing the role of biological protection and coolant. Inside the ponds exists an aluminum rack, which contains 60 locations for fuel storage. The spacing between these locations was determined from considerations of criticality and it is was the same with that of the cooling pond near the reactor. To have supplementary protection in the case of an accident which can destroy the entire rack and put together all the fuel elements thus forming critical mass, cadmium plates were placed on the ponds bottom for a better neutron absorption. Exploitation of cooling pond near the WWR-S reactor which has the identical structure with that of nuclear spent fuel repository, demonstrate the reliability and

  20. InterProScan Result: FS932793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932793 FS932793_2_ORF2 6EA452AE762D110F PANTHER PTHR12479 LYSOSOMAL-ASSOCIATED TRANSME...MBRANE PROTEIN 4.4e-71 T IPR004687 Golgi 4-transmembrane spanning transporter Biological Process: transport (GO:0006810)|Cellular Component: integral to membrane (GO:0016021) ...

  1. 256 fs, 2 nJ soliton pulse generation from MoS2 mode-locked fiber laser

    Science.gov (United States)

    Jiang, Zike; Chen, Hao; Li, Jiarong; Yin, Jinde; Wang, Jinzhang; Yan, Peiguang

    2017-12-01

    We demonstrate an Er-doped fiber laser (EDFL) mode-locked by a MoS2 saturable absorber (SA), delivering a 256 fs, 2 nJ soliton pulse at 1563.4 nm. The nonlinear property of the SA prepared by magnetron sputtering deposition (MSD) is measured with a modulation depth (MD) of ∼19.48% and a saturable intensity of 4.14 MW/cm2. To the best of our knowledge, the generated soliton pulse has the highest pulse energy of 2 nJ among the reported mode-locked EDFLs based on transition metal dichalcogenides (TMDs). Our results indicate that MSD-grown SAs could offer an exciting platform for high pulse energy and ultrashort pulse generation.

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

    International Nuclear Information System (INIS)

    Tombakoglu, M.; Cecen, Y.

    2001-01-01

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

  3. InterProScan Result: FS787904 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS787904 FS787904_5_ORF1 F46B8A7F4DCFA20B SUPERFAMILY SSF55194 Ribosome recycling f...actor, RRF 4.1e-24 T IPR002661 Ribosome recycling factor Biological Process: translation (GO:0006412) ...

  4. EST Table: FS730803 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS730803 E_FL_bmmt_19O18_F_0 10/09/28 54 %/206 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 bmmt ...

  5. EST Table: FS918214 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS918214 E_FL_fufe_43K22_F_0 10/09/28 53 %/199 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fufe ...

  6. InterProScan Result: FS898954 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS898954 FS898954_4_ORF2 AA99CAAFD037F5BB PFAM PF04615 Utp14 1.4e-56 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  7. EST Table: FS926804 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS926804 E_FL_fwgP_17H18_F_0 10/09/28 58 %/249 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  8. EST Table: FS800709 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS800709 E_FL_fmgV_04M06_F_0 10/09/28 57 %/262 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  9. EST Table: FS807612 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS807612 E_FL_fmgV_24A09_F_0 10/09/28 57 %/266 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  10. EST Table: FS806480 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS806480 E_FL_fmgV_20N06_F_0 10/09/28 57 %/259 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  11. EST Table: FS804646 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804646 E_FL_fmgV_15M02_F_0 10/09/28 54 %/215 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  12. EST Table: FS804486 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804486 E_FL_fmgV_15E24_F_0 10/09/28 53 %/199 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  13. EST Table: FS921913 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS921913 E_FL_fwgP_03B17_F_0 10/09/28 54 %/215 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  14. EST Table: FS810510 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS810510 E_FL_fmgV_32C08_F_0 10/09/28 57 %/259 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fmgV ...

  15. EST Table: FS937969 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS937969 E_FL_fwgP_50K04_F_0 10/09/28 56 %/264 aa ref|XP_001659582.1| xaa-pro dipeptidase pepd/pepq(e.coli...) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti... aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fwgP ...

  16. EST Table: FS822271 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS822271 E_FL_fmgV_11P16_R_0 11/12/09 n.h 10/09/28 75 %/112 aa ref|XP_001656149.1| fetal alzheimer... antigen, falz [Aedes aegypti] gb|EAT35210.1| fetal alzheimer antigen, falz [Aedes aegypti] 1...8 %/115 aa gi|189240808|ref|XP_001811424.1| PREDICTED: similar to fetal alzheimer antigen, falz [Tribolium castaneum] FS822271 fmgV ...

  17. InterProScan Result: FS758275 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758275 FS758275_1_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) NA ? IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  18. InterProScan Result: FS827626 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827626 FS827626_6_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) NA ? IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  19. InterProScan Result: FS827626 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827626 FS827626_6_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) 9e-35 T IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  20. InterProScan Result: FS758275 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758275 FS758275_1_ORF2 2EC8961369A7A64F PANTHER PTHR11064:SF10 DNA POLYMERASE EPSILON P17 SUBUNIT (DNA POL...YMERASE EPSILON SUBUNIT 3) 9e-35 T IPR009072 unintegrated Molecular Function: DNA binding (GO:0003677) ...

  1. EST Table: FS819070 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 1|gene:AGAP012772 10/09/10 47 %/123 aa gnl|Amel|GB30341-PA 10/09/10 47 %/123 aa gi|91086723|ref|XP_970869.1|... PREDICTED: similar to fear-of-intimacy CG6817-PA [Tribolium castaneum] FS825450 fmgV ...

  2. SeaWiFS

    Data.gov (United States)

    Washington University St Louis — SEAWiFS_US is a high resolution (1km) satellite dataset derived from the eight wavelength SEAWiFS sensor. The dataset also includes the aerosol reflectance over the...

  3. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status

    International Nuclear Information System (INIS)

    2011-01-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  4. InterProScan Result: FS777434 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS777434 FS777434_4_ORF1 546CBAAA77BF4D8A PRINTS PR00385 P450 3.7e-11 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  5. Radiation influencing of the extraction properties of the CyMe{sub 4}-BTBP and CyMe{sub 4}-BTPhen solvents with FS-13

    Energy Technology Data Exchange (ETDEWEB)

    Konde, J.; Distler, P.; John, J. [Department of Nuclear Chemistry, Czech Technical University in Prague, BGehova 7, 11519 Prague 1 (Czech Republic); Svehla, J.; Gruner, B.; Belcicka, Z. [Institute of Inorganic Chemistry, Academy of Sciences of the Czech Republic, 250 68 Rez near Prague (Czech Republic)

    2016-07-01

    The radiolytic stability of two ligands, CyMe4-BTBP and CyMe4-BTPhen in system with the FS-13 (phenyl trifluoromethyl sulfone) diluent was investigated under irradiation by accelerated electrons to study impact of the degradation products on the separation process efficiency and safety. Irradiation experiments were carried out up to the absorbed dose of 200 kGy. The irradiated samples were analysed by HPLC for the degree of extractant degradation. In addition, the effect of the presence of HNO{sub 3} during the irradiation was studied. Extraction properties of the irradiated solvents were evaluated and compared with the extraction properties of non-irradiated solvents to assess the impact of the degradation products on extractions properties. The results obtained show that the stabilities of these ligands are higher in FS-13 than in the cyclohexanone-type solvents. The extraction properties are significantly influenced by degradation products contained in these systems. Surprisingly, both the distribution ratios for americium and europium, and the Am/Eu separation factor increase with the absorbed dose for the system withCyMe{sub 4}-BTPhen in FS-13. Obviously, the degradation products of this ligand are efficient extractants too. In the next phase, an attempt will be done to identify the main degradation products, synthesise them and study their extraction properties. (authors)

  6. Licensing experience of the HTR-10 test reactor

    International Nuclear Information System (INIS)

    Sun, Y.; Xu, Y.

    1996-01-01

    A 10MW high temperature gas-cooled test reactor (HTR-10) is now being projected by the Institute of Nuclear Energy Technology within China's National High Technology Programme. The Construction Permit of HTR-10 was issued by the Chinese nuclear licensing authority around the end of 1994 after a period of about one year of safety review of the reactor design. HTR-10 is the first high temperature gas-cooled reactor (HTGR) to be constructed in China. The purpose of this test reactor project is to test and demonstrate the technology and safety features of the advanced modular high temperature reactor design. The reactor uses spherical fuel elements with coated fuel particles. The reactor unit and the steam generator unit are arranged in a ''side-by-side'' way. Maximum fuel temperature under the accident condition of a complete loss of coolant is limited to values much lower than the safety limit set for the fuel element. Since the philosophy of the technical and safety design of HTR-10 comes from the high temperature modular reactor design, the reactor is also called the Test Module. HTR-10 represents among others also a licensing challenge. On the one side, it is the first helium reactor in China, and there are less licensing experiences both for the regulator and for the designer. On the other side, the reactor design incorporates many advanced design features in the direction of passive or inherent safety, and it is presently a world-wide issue how to treat properly the passive or inherent safety design features in the licensing safety review. In this presentation, the licensing criteria of HTR-10 are discussed. The organization and activities of the safety review for the construction permit licensing are described. Some of the main safety issues in the licensing procedure are addressed. Among these are, for example, fuel element behaviour, source term, safety classification of systems and components, containment design. The licensing experiences of HTR-10 are of

  7. EST Table: FS849735 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available acetyltransferase [Periplaneta americana] 10/09/11 34 %/218 aa FBpp0169479|DmojGI20262-PA 10/08/29 n.h 10/09...FS849735 E_FL_fner_35N12_F_0 10/09/28 33 %/215 aa dbj|BAC87874.1| arylalkylamine N-

  8. EST Table: FS725108 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS725108 E_FL_bmmt_03L12_F_0 10/09/28 58 %/105 aa gb|ACY09589.1| cytochrome oxidase subunit 1 [Tetracis cach...exiata] 10/09/03 low homology 10/08/28 low homology 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h AU001277 bmmt ...

  9. EST Table: FS853636 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS853636 E_FL_fner_46O23_F_0 10/09/28 50 %/122 aa gb|EFA10616.1| hypothetical prote...GAP010623-PA Protein|3L:7358821:7360505:1|gene:AGAP010623 10/09/10 low homology 10/09/10 50 %/122 aa gi|2700

  10. EST Table: FS731731 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS731731 E_FL_bmmt_24I23_F_0 10/09/28 44 %/191 aa ref|XP_001869607.1| monocarboxyla...10/09/03 39 %/191 aa FBpp0160203|DmojGI10986-PA 10/08/28 low homology 10/09/10 44 %/191 aa AGAP002587-PA Pro

  11. InterProScan Result: FS932451 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932451 FS932451_2_ORF2 773A43AAFA4CCB66 PANTHER PTHR10082:SF12 INTEGRIN BETA-3 NA...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  12. InterProScan Result: FS891448 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891448 FS891448_6_ORF1 45634B4CEFE7200E PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  13. InterProScan Result: FS891448 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891448 FS891448_6_ORF1 45634B4CEFE7200E PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 8...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  14. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_1_ORF2 2E2F43F4558B5288 PRINTS PR00309 ARRESTIN 4.7e-22 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  15. EST Table: FS827794 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS827794 E_FL_fmgV_27G02_R_0 10/09/28 42 %/239 aa ref|XP_002092266.1| GE14094 [Dros...ophila yakuba] gb|EDW91978.1| GE14094 [Drosophila yakuba] 10/09/10 42 %/239 aa FBpp0259104|DyakGE14094-PA 10

  16. EST Table: FS920967 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920967 E_FL_fufe_52E08_F_0 10/09/28 83 %/296 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09

  17. EST Table: FS910029 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS910029 E_FL_fufe_19A04_F_0 10/09/28 88 %/296 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  18. EST Table: FS908976 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908976 E_FL_fufe_15N15_F_0 10/09/28 88 %/289 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  19. EST Table: FS910254 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS910254 E_FL_fufe_19K18_F_0 10/09/28 87 %/274 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  20. EST Table: FS913950 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS913950 E_FL_fufe_30M22_F_0 10/09/28 87 %/272 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09

  1. EST Table: FS919738 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919738 E_FL_fufe_48E09_F_0 10/09/28 87 %/288 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/13 low homology 10/08/29 n.h 10/09

  2. Calibration of SeaWiFS after two years on orbit

    Science.gov (United States)

    Barnes, Robert A.; McClain, Charles R.

    1999-12-01

    The Sea-viewing Wide Field-of-view Sensor (SeaWiFS) was launched on 1 August 1997, and the first Earth images were taken on 4 September 1997. Regular, daily measurements of the sun, via the onboard diffuser, started on 9 September 1997 and regular, monthly measurements of the moon on November 14, 1997. These lunar measurements, as first reported at EUROPTO'98, provide a highly sensitive method for determining the change in the radiometric sensitivity of SeaWiFS. The prelaunch radiometric calibration used by SeaWiFS was performed in the Spring of 1997 at the spacecraft manufacturer's facility. The calibration measurements were made by a team from the National Institute of Standards and Technology (NIST) and the SeaWiFS Project. The uncertainties in this calibration range from 2% to 3% for the eight SeaWiFS bands. In addition, a set of outdoor measurements of the sun were made at the instrument manufacturer's facility in November 1993, just before the delivery of SeaWiFS to the spacecraft manufacturer. These solar measurements, using the instrument's diffuser, were combined with a separate set of solar radiometer measurements to determine the transmittance of the atmosphere. At the start of on-orbit measurements by SeaWiFS, solar measurements were made again by the instrument. These two sets of measurements make up the transfer-to-orbit experiment. From the ground measurements, the outputs of the SeaWiFS bands on orbit were predicted. For each band, the output from the initial on-orbit measurements agree with the predicted values by 21/2% or less. The uncertainties for the transfer-to-orbit experiment are estimated to be approximately 3% to 4%. From 14 November 1997 to 29 June 1999, SeaWiFS has made 20 measurements of the moon. The analysis of lunar measurements presented here has minor modifications to that presented at EUROPTO'98. The trend lines from the current analysis have been extrapolated back from 14 November 1997 to 4 September 1997 to describe the changes

  3. EST Table: FS758989 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758989 E_FL_fcaL_09P10_F_0 10/09/28 34 %/195 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  4. EST Table: FS841713 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] 10/09/10 53 %/160 aa FBpp0120238|DanaGF170... similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fner ...

  5. SeaWiFS technical report series. Volume 4: An analysis of GAC sampling algorithms. A case study

    Science.gov (United States)

    Yeh, Eueng-Nan (Editor); Hooker, Stanford B. (Editor); Hooker, Stanford B. (Editor); Mccain, Charles R. (Editor); Fu, Gary (Editor)

    1992-01-01

    The Sea-viewing Wide Field-of-view Sensor (SeaWiFS) instrument will sample at approximately a 1 km resolution at nadir which will be broadcast for reception by realtime ground stations. However, the global data set will be comprised of coarser four kilometer data which will be recorded and broadcast to the SeaWiFS Project for processing. Several algorithms for degrading the one kilometer data to four kilometer data are examined using imagery from the Coastal Zone Color Scanner (CZCS) in an effort to determine which algorithm would best preserve the statistical characteristics of the derived products generated from the one kilometer data. Of the algorithms tested, subsampling based on a fixed pixel within a 4 x 4 pixel array is judged to yield the most consistent results when compared to the one kilometer data products.

  6. Strategy to support HTGR fuel for the 10 MW Indonesia’s experimental power reactor (RDE)

    International Nuclear Information System (INIS)

    Taswanda Taryo; Geni Rina Sunaryo; Ridwan; Meniek Rachmawati

    2018-01-01

    The Indonesia’s 10 MW experimental power reactor (RDE) is developed based on high temperature gas-cooled reactor (HTGR) and the program of the RDE was firstly introduced to the Agency for National Development Planning (BAPPENAS) at the beginning of 2014. The RDE program is expected to have positive impacts on community prosperity, self-reliance and sovereignty of Indonesia. The availability of RDE will be able to accelerate advanced nuclear power technology development and hence elevate Indonesia to be the nuclear champion in the ASEAN region. The RDE is expected to be operable in 2022/2023. In terms of fuel supply for the reactor, the first batch of RDE fuel will be inclusive in the RDE engineering, procurement and construction (RDE-EPC) contract for the assurance of the RDE reactor operation from 2023 to 2027. Consideration of RDE fuel plant construction is important as RDE can be the basis for the development of reactors of similar type with small-medium power(25 MWe–200/300 MWe), which are preferable for eastern part of Indonesia. To study the feasibility of the construction of RDE fuel plant, current state of the art of the R&D on HTGR fuel in some advanced countries such as European countries, the United States, South Africa and Japan will be discussed and overviewed to draw a conclusion about the prospective countries for supporting the fuel for long-term RDE operation. The strategy and road map for the preparation of the RDE fuel plant construction with the involvement of national stake holders have been developed. The best possible vendor country to support HTGR fuel for long-term operation is finally accomplished. In the end, this paper can be assigned as a reference for the planning and construction of HTGR RDE fuel fabrication plant in Indonesia. (author)

  7. InterProScan Result: FS766396 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS766396 FS766396_2_ORF2 2EA98AF8E0AD3165 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 6.4e-05 T IPR008429 Cleft lip and palate transmembrane 1 ...

  8. InterProScan Result: FS888414 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS888414 FS888414_1_ORF2 7BD3608BC4DF6C01 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 2...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  9. InterProScan Result: FS869255 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS869255 FS869255_4_ORF1 7290E0DA14F8EDE2 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.1e-55 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  10. InterProScan Result: FS735919 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS735919 FS735919_4_ORF2 1C0441A9D0DDEE80 SUPERFAMILY SSF47798 Barrier-to-autointegration... factor, BAF 1.3e-44 T IPR004122 Barrier- to-autointegration factor, BAF Molecular Function: DNA binding (GO:0003677) ...

  11. EST Table: FS840242 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available l|Amel|GB10584-PA 10/09/10 47 %/128 aa gi|91087383|ref|XP_975651.1| PREDICTED: similar to Glucosylceramidase precursor (Beta-glucocer...ebrosidase) (Acid beta-glucosidase) (D-glucosyl-N-acylsphingosine glucohydrolase) [Tribolium castaneum] FS796494 fner ...

  12. EST Table: FS736730 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS736730 E_FL_bmmt_06M14_R_0 10/09/28 100 %/193 aa ref|NP_001037510.1| elongation f... dbj|BAA02601.1| elongation factor 1 alpha [Bombyx mori] 10/09/03 95 %/193 aa FBpp0257399|DyakGE12389-PA 10/

  13. EST Table: FS747376 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available milar to xaa-pro dipeptidase pepd/pepq(e.coli) [Nasonia vitripennis] 10/09/08 58 %/234 aa FBpp0241989|DwilGK...AP004775 10/09/10 low homology 10/09/10 54 %/235 aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 caL- ...

  14. InterProScan Result: FS756793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS756793 FS756793_1_ORF2 CD4194218B70284D PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 4e-37 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  15. InterProScan Result: FS873128 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS873128 FS873128_4_ORF1 97398CBF49C72044 PFAM PF08625 Utp13 2.9e-34 T IPR013934 Small-subunit process...ome, Utp13 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  16. EST Table: FS839039 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS839039 E_FL_fner_05J12_F_0 10/09/28 57 %/212 aa gb|ADE18444.1| cytochrome c oxida...se subunit I [Bombyx mori] 10/09/10 50 %/212 aa FBpp0100176|mt:CoI-PA 10/08/29 39 %/207 aa MTCE.26#CE35350#W

  17. EST Table: FS920740 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920740 E_FL_fufe_51G05_F_0 10/09/28 40 %/209 aa ref|XP_001867321.1| partner of drosha... [Culex quinquefasciatus] gb|EDS44779.1| partner of drosha [Culex quinquefasciatus] 10/09/13 39 %/204 aa

  18. EST Table: FS915741 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS915741 E_FL_fufe_36D23_F_0 10/09/28 88 %/287 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  19. EST Table: FS907852 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS907852 E_FL_fufe_12H06_F_0 10/09/28 92 %/258 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  20. EST Table: FS913382 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS913382 E_FL_fufe_29B08_F_0 10/09/28 87 %/287 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  1. EST Table: FS908536 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908536 E_FL_fufe_14I01_F_0 10/09/28 93 %/263 aa ref|NP_001098702.1| nanos-like pr...otein [Bombyx mori] gb|ABS17681.1| nanos-like protein [Bombyx mori] 10/09/12 low homology 10/08/29 n.h 10/09/10 low homology 10/09/10 low homology 10/09/10 n.h NM_001105232 fufe ...

  2. Design study on sodium cooled large-scale reactor

    International Nuclear Information System (INIS)

    Murakami, Tsutomu; Hishida, Masahiko; Kisohara, Naoyuki

    2004-07-01

    In Phase 1 of the 'Feasibility Studies on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled large-scale reactor, which has a possibility to fulfill the design requirements of the F/S. In Phase 2, design improvement for further cost reduction of establishment of the plant concept has been performed. This report summarizes the results of the design study on the sodium-cooled large-scale reactor performed in JFY2003, which is the third year of Phase 2. In the JFY2003 design study, critical subjects related to safety, structural integrity and thermal hydraulics which found in the last fiscal year has been examined and the plant concept has been modified. Furthermore, fundamental specifications of main systems and components have been set and economy has been evaluated. In addition, as the interim evaluation of the candidate concept of the FBR fuel cycle is to be conducted, cost effectiveness and achievability for the development goal were evaluated and the data of the three large-scale reactor candidate concepts were prepared. As a results of this study, the plant concept of the sodium-cooled large-scale reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  3. SeaWiFS Postlaunch Calibration and Validation Analyses

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine (Editor); McClain, Charles R.; Barnes, Robert A.; Eplee, Robert E., Jr.; Franz, Bryan A.; Hsu, N. Christina; Patt, Frederick S.; Pietras, Christophe M.; Robinson, Wayne D.

    2000-01-01

    The effort to resolve data quality issues and improve on the initial data evaluation methodologies of the SeaWiFS Project was an extensive one. These evaluations have resulted, to date, in three major reprocessings of the entire data set where each reprocessing addressed the data quality issues that could be identified up to the time of the reprocessing. Three volumes of the SeaWiFS Postlaunch Technical Report Series (Volumes 9, 10, and 11) are needed to document the improvements implemented since launch. Volume 10 continues the sequential presentation of postlaunch data analysis and algorithm descriptions begun in Volume 9. Chapter 1 of Volume 10 describes an absorbing aerosol index, similar to that produced by the Total Ozone Mapping Spectrometer (TOMS) Project, which is used to flag pixels contaminated by absorbing aerosols, such as, dust and smoke. Chapter 2 discusses the algorithm being used to remove SeaWiFS out-of-band radiance from the water-leaving radiances. Chapter 3 provides an itemization of all significant changes in the processing algorithms for each of the first three reprocessings. Chapter 4 shows the time series of global clear water and deep-water (depths greater than 1,000m) bio-optical and atmospheric properties (normalized water-leaving radiances, chlorophyll, atmospheric optical depth, etc.) based on the eight-day composites as a check on the sensor calibration stability. Chapter 5 examines the variation in the derived products with scan angle using high resolution data around Hawaii to test for residual scan modulation effects and atmospheric correction biases. Chapter 6 provides a methodology for evaluating the atmospheric correction algorithm and atmospheric derived products using ground-based observations. Similarly, Chapter 7 presents match-up comparisons of coincident satellite and in situ data to determine the accuracy of the water-leaving radiances, chlorophyll a, and K(490) products.

  4. Experiment Operating Specification for the Semiscale MOD-2C feedwater and steam line break experiment series. Appendix S-FS-6 and 7

    International Nuclear Information System (INIS)

    Boucher, T.J.; Owca, W.A.

    1985-05-01

    This document is the Semiscale MOD-2C feedwater and steam line break experiment series Experiment Operating Specification Appendix for tests S-FS-6 and S-FS-7. Test S-FS-6 is the third test in the series and simulates a 100% break in a steam generator bottom feedwater line downstream of the check valve accompanied by compounding factors (such as check valve failure, loss-of-offsite power at SIS and SIS delayed until low steam generator pressure signal). The test is terminated after plant stabilization and recovery procedures including unaffected loop steam and feed, pressurizer heater operation, pressurizer auxiliary spray operation, and normal charging/letdown operation. Test S-FS-7 is the fourth test in the series and simulates a 14.3% break in a steam generator bottom feedwater line downstream of the check valve, accompanied by compounding factors. The test is terminated after plant stabilization procedures including unaffected loop steam and feed, pressurizer heater operation, and normal charging/letdown operation. The test was followed by an affected loop secondary refill after isolating the break. The Appendix contains information on the major fluid systems, initial experiment conditions, experiment boundary conditions, and sequence of experiment events. Also included is a discussion of the scaling criteria and philosophy used to develop the experiment initial and boundary conditions and system configuration

  5. InterProScan Result: FS826604 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS826604 FS826604_5_ORF1 1C8DFE9F04A27A5C PRINTS PR00385 P450 2.3e-10 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  6. EST Table: FS846041 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS846041 E_FL_fner_25G13_F_0 10/09/28 50 %/132 aa ref|XP_001606590.1| PREDICTED: similar to glucocerebro...el|GB10584-PA 10/09/10 47 %/138 aa gi|91087383|ref|XP_975651.1| PREDICTED: similar to Glucosylceramidase precursor (Beta-glucocerebro

  7. InterProScan Result: FS932451 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932451 FS932451_2_ORF2 773A43AAFA4CCB66 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 7e-07 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  8. InterProScan Result: FS892858 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS892858 FS892858_4_ORF2 0C92A671D1557189 PFAM PF00995 Sec1 1.1e-50 T IPR001619 Sec1-like protein Biological... Process: vesicle docking involved in exocytosis (GO:0006904)|Biological Process: vesicle-mediated transport (GO:0016192) ...

  9. InterProScan Result: FS779843 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS779843 FS779843_4_ORF1 437F417A972B5635 PFAM PF04615 Utp14 6.5e-33 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  10. Simulation for Remote Operation for REX10 Nuclear Reactor

    International Nuclear Information System (INIS)

    Lee, Sim Won; Kim, Dong Su; Na, Man Gyun; Lee, Yoon Joon; Lee, Yeon Gun; Park, Goon Cherl

    2010-01-01

    The newly designed REX10 (Regional Energy Reactor, 10MWth) is an environmentally-friendly and stable small nuclear reactor for a small-scale reactor based Multi-purpose regional energy system. The REX10 has been developed to maintain system safety in order to be placed in densely populated region, island, etc. In addition, it is significantly hard to recruit many operation and maintenance personnel for small power reactors differently from usual commercial reactors because of its remote location and of economic reasons. In order to overcome these constraints, to decrease the operation cost by reducing operation and maintenance personnel, and to increase plant reliability through autonomous plant control, it is needed to design the control system of the small power reactors and to establish its unmanned remote operation system. In this study, the REX10 reactor core thermal power controller is designed by using a REX10 code analyzer. The remote control facility through man-machine interface (MMI) design and interface between programming languages was established and it was used to verify remote operation of REX10

  11. EST Table: FS908806 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS908806 E_FL_fufe_15F06_F_0 10/09/28 64 %/229 aa ref|XP_974421.1| PREDICTED: similar to synoviolin.../09/10 58 %/222 aa gnl|Amel|GB14313-PA 10/09/10 64 %/229 aa gi|91087035|ref|XP_974421.1| PREDICTED: similar to synoviolin [Tribolium castaneum] DC547331 fufe ...

  12. EST Table: FS733278 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS733278 E_FL_bmmt_20O16_F_0 10/09/28 77 %/113 aa ref|XP_974421.1| PREDICTED: similar to synoviolin.../09/10 70 %/106 aa gnl|Amel|GB14313-PA 10/09/10 77 %/113 aa gi|91087035|ref|XP_974421.1| PREDICTED: similar to synoviolin [Tribolium castaneum] DC547331 bmmt ...

  13. Evaluation of the HTR-10 Reactor as a Benchmark for Physics Code QA

    International Nuclear Information System (INIS)

    William K. Terry; Soon Sam Kim; Leland M. Montierth; Joshua J. Cogliati; Abderrafi M. Ougouag

    2006-01-01

    The HTR-10 is a small (10 MWt) pebble-bed research reactor intended to develop pebble-bed reactor (PBR) technology in China. It will be used to test and develop fuel, verify PBR safety features, demonstrate combined electricity production and co-generation of heat, and provide experience in PBR design, operation, and construction. As the only currently operating PBR in the world, the HTR-10 can provide data of great interest to everyone involved in PBR technology. In particular, if it yields data of sufficient quality, it can be used as a benchmark for assessing the accuracy of computer codes proposed for use in PBR analysis. This paper summarizes the evaluation for the International Reactor Physics Experiment Evaluation Project (IRPhEP) of data obtained in measurements of the HTR-10's initial criticality experiment for use as benchmarks for reactor physics codes

  14. EST Table: FS813939 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS813939 E_FL_fmgV_41L05_F_0 10/09/28 65 %/121 aa ref|NP_001136225.1| hypothetical ...protein LOC100216500 [Bombyx mori] gb|ACJ66918.1| hypothetical protein 39 [Bombyx mori] 10/09/09 n.h 10/08/29 n.h 10/09/10 n.h 10/09/10 n.h 10/09/10 n.h AU001277 fmgV ...

  15. MAPLE-X10 reactor digital control system

    International Nuclear Information System (INIS)

    Deverno, M.T.; Hinds, H.W.

    1991-10-01

    The MAPLE-X10 reactor, currently under construction at the Chalk River Laboratories of Atomic Energy of Canada Limited, is a 10 MW t , pool-type, light-water reactor. It will be used for radioisotope production and silicon neutron transmutation doping. The reactor is controlled by a Digital Control System (DCS) and protected against abnormal process events by two independent safety systems. The DCS is an integrated control system used to regulate the reactor power and process systems. The safety philosophy for the control system is to minimize unsafe events arising from system failures and operational errors. this is achieved through redundancy, fail-safe design, automatic fault detection, and the selection of highly reliable components. The DCS provides both computer-controlled reactor regulation from the shutdown state to full power and automated reactor shutdown if safe limits are exceeded or critical sensors malfunction. The use of commercially available hardware with enhanced quality assurance makes the system cost effective while providing a high degree of reliability

  16. EST Table: FS796464 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to putative lysosomal glucocerebrosidase [Tribolium castaneum] 10/09/09 32 %/334 aa FBpp0237202|DvirGJ227...milar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS796494 ffbm ...

  17. PBDD/Fs in surface sediments from the East River, China.

    Science.gov (United States)

    Ren, M; Peng, P A; Chen, D Y; Chen, P; Zhou, L

    2009-09-01

    The contamination status of polybrominated dibenzo-p-dioxins and dibenzofurans (PBDD/Fs) was preliminarily investigated in surface sediments from the East River. The concentrations of eight 2,3,7,8-substituted tetra- to hexa- PBDD/Fs were found to be in the range of 0.32-110 (mean 13) pg g(-1) and the corresponding TEQ concentrations were 0.087-18 (mean 2) pg I-TEQ g(-1). All sediments were characterized by the dominant PBDFs. 2,3,4,7,8-PeBDF was the most important TEQ contributor, accounting for 47%-77% of the total I-TEQ of PBDD/Fs. PCDD/Fs contributed dominantly to the total TEQs of PCDD/Fs, PBDD/Fs and dioxin-like PCBs in most samples except of the sediment from the Shima River. The higher PBDD/F concentrations in the Shima River may be attributed to the use of BFRs in the electrical and electronics industries, which posed a potential risk of dioxins on ecological system.

  18. EST Table: FS928371 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS928371 E_FL_fwgP_22B11_F_0 10/09/28 87 %/119 aa ref|XP_975463.1| PREDICTED: similar to rasputin...066-PA 10/09/10 87 %/119 aa gi|91076984|ref|XP_975463.1| PREDICTED: similar to rasputin CG9412-PB [Tribolium castaneum] CK541017 fwgP ...

  19. Fuel recycling and 4. generation reactors

    International Nuclear Information System (INIS)

    Devezeaux de Lavergne, J.G.; Gauche, F.; Mathonniere, G.

    2012-01-01

    The 4. generation reactors meet the demand for sustainability of nuclear power through the saving of the natural resources, the minimization of the volume of wastes, a high safety standard and a high reliability. In the framework of the GIF (Generation 4. International Forum) France has decided to study the sodium-cooled fast reactor. Fast reactors have the capacity to recycle plutonium efficiently and to burn actinides. The long history of reprocessing-recycling of spent fuels in France is an asset. A prototype reactor named ASTRID could be entered into operation in 2020. This article presents the research program on the sodium-cooled fast reactor, gives the status of the ASTRID project and present the scenario of the progressive implementation of 4. generation reactors in the French reactor fleet. (A.C.)

  20. Emission factors and congener-specific characterization of PCDD/Fs, PCBs, PBDD/Fs and PBDEs from an off-road diesel engine using waste cooking oil-based biodiesel blends.

    Science.gov (United States)

    Chen, Shui-Jen; Tsai, Jen-Hsiung; Chang-Chien, Guo-Ping; Huang, Kuo-Lin; Wang, Lin-Chi; Lin, Wen-Yinn; Lin, Chih-Chung; Yeh, C Kuei-Jyum

    2017-10-05

    Few studies have been performed up to now on the emission factors and congener profiles of persistent organic pollutants (POPs) emitted from off-road diesel engines. This investigation elucidates the emission factors and congener profiles of various POPs, namely polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs), polychlorinated biphenyl (PCBs), polybrominated dibenzo-p-dioxins and polybrominated dibenzofurans (PBDD/Fs) and polybrominated diphenyl ethers (PBDEs), in the exhausts of a diesel generator fueled with different waste cooking oil-based biodiesel (WCO-based biodiesel) blends. The PCDD/Fs contributed 87.2% of total dioxin-like toxicity (PCDD/Fs+PCBs+PBDD/Fs) in the exhaust, while the PCBs and PBDD/Fs only contributed 8.2% and 4.6%, respectively. Compared with petroleum diesel, B20 (20vol% WCO-based biodiesel+80vol% diesel) reduced total toxicity by 46.5% for PCDD/Fs, 47.1% for PCBs, and 24.5% for PBDD/Fs, while B40 (40vol% WCO-based biodiesel+60vol% diesel) reduced it by 89.5% for PCDD/Fs, 57.1% for PCBs, and 63.2% for PBDD/Fs in POP emission factors. The use of WCO-based biodiesel not only solves the problem of waste oil disposal, but also lowers POP emissions from diesel generators. Copyright © 2017 Elsevier B.V. All rights reserved.

  1. Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

    International Nuclear Information System (INIS)

    Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

    1992-01-01

    A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

  2. Effect of Utilization of Silicide Fuel with the Density 4.8 gU/cc on the Kinetic Parameters of RSG-GAS Reactor

    International Nuclear Information System (INIS)

    Setiyanto; Sembiring, Tagor M.; Pinem, Surian

    2007-01-01

    Presently, the RSG-GAS reactor using silicide fuel element of 2.96 gU/cc. For increasing reactor operation time, its planning to change to higher density fuel. The kinetic calculation of silicide core with density 4.8 gU/cc has been carried out, since it has an influence on the reactor operation safety. The calculated kinetic parameters are the effective delayed neutron fraction, the delayed neutron decay constant, prompt neutron lifetime and feedback reactivity coefficient very important for reactor operation safety. the calculation is performed in 2-dimensional neutron diffusion-perturbation method using modified Batan-2DIFF code. The calculation showed that the effective delayed neutron fraction is 7. 03256x10 -03 , total delay neutron time constant is 7.85820x10 -02 s -1 and the prompt neutron lifetime is 55.4900 μs. The result of prompt neutron lifetime smaller 10 % compare with silicide fuel of 4.8 gU/cc. The calculated results showed that all of the feedback reactivity coefficient silicide core 4.8 gU/cc is negative. Totally, the feedback reactivity coefficient of silicide fuel of 4.8 gU/cc is 10% less than that of silicide fuel of 2.96 gU/cc. The results shown that kinetic parameters result decrease compared with the silicide core with density 2.96 gU/cc, but no significant influence in the RSG-GAS reactor operation. (author)

  3. Design study on sodium-cooled middle-scale modular reactor

    International Nuclear Information System (INIS)

    Kisohara, Naoyuki; Hishida, Masahiko; Nibe, Nobuaki

    2003-09-01

    In Phase 1 of the 'Feasibility Study on Commercialized Fast Reactor Cycle Systems (F/S)', an advanced loop type reactor has been selected as a promising concept of sodium-cooled middle-scale modular reactor, which has a possibility to fulfill the design requirements of the F/S. This report summarizes the results of the design study on the sodium-cooled middle-scale modular reactor performed in JFY2002, which is the second year of Phase 2. The construction cost of the sodium-cooled middle-scale modular reactor, which has been constructed in JFY2002, was almost achieved the economical goal. But its achievability was not sufficient to accept the concept. In order to reduce the construction cost, the plant concept has been re-constructed based on the 50 MWe plant studied in JFY2002. After that, fundamental specifications of main systems and components for the new concept have been set, and critical subjects have been examined and evaluated. In addition, in order to achieve the further cost reduction, the plant with simplified secondary system, the plant with electric magnetic pump in secondary system, and the fuel handling system are examined and evaluated. As a result of this study, the plant concept of the sodium-cooled middle-scale modular reactor has been constructed, which has a prospect to satisfy the economic goal (construction cost: less than 200,000 yens/kWe, etc.) and has a prospect to solve the critical subjects. From now on, reflecting the results of elemental experiments, the preliminary conceptual design of this plant will be preceded toward the selection for narrowing down candidate concepts at the end of Phase 2. (author)

  4. EST Table: FS779999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS779999 E_FL_fcaL_32K04_R_0 10/09/28 100 %/145 aa dbj|BAG30799.1| actin [Papilio x...locus:act- 2#actin#status:Confirmed#UniProt:P10984#protein_id:CAB04 675.1 10/09/10 100 %/145 aa AGAP005095-PA Protein|2L:9969318:99

  5. InterProScan Result: FS836461 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS836461 FS836461_6_ORF1 4B253188815CBC36 PRINTS PR00385 P450 2.2e-08 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  6. InterProScan Result: FS739298 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS739298 FS739298_4_ORF2 E65DEA0712139D30 PFAM PF00067 p450 3.3e-19 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  7. InterProScan Result: FS807624 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS807624 FS807624_3_ORF2 727CB335F709D390 PFAM PF00067 p450 3.4e-19 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  8. InterProScan Result: FS874329 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874329 FS874329_4_ORF1 93DDB3924654C140 PFAM PF00067 p450 3.6e-36 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  9. InterProScan Result: FS764425 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS764425 FS764425_1_ORF2 38B2ED93758BCB7B PFAM PF00067 p450 4.2e-24 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  10. InterProScan Result: FS784665 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS784665 FS784665_4_ORF1 7E959D55ADFEC376 PRINTS PR00385 P450 5.5e-11 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  11. Research reactor utilization. Summary reports of three study group meetings: Irradiation techniques at research reactors, held in Istanbul 15-19 November 1965; Research reactor operation and maintenance problems, held in Caracas 6-10 December 1965; and Research reactor utilization in the Far East, held in Lucas Heights 28 February - 4 March 1966

    International Nuclear Information System (INIS)

    1967-01-01

    The three sections of this book, which are summary reports of three Study Group meetings of the IAEA: Irradiation techniques at research reactors, Istanbul, 15-19 November 1965; Research reactor operation and maintenance problems, Caracas, 6-10 December 1965; and Research reactor utilization in the Far East, Lucas Heights, Australia, 28 February - 4 March 1966. These meetings were the latest in a series designed to promote efficient utilization of research reactors, to disseminate information on advances in techniques, to discuss common problems in reactor operations, and to outline some advanced areas of reactor-based research. (author)

  12. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-09-01

    The MAPLE-X10 reactor is a D 2 0-reflected, H 2 0-cooled and -moderated pool-type reactor under construction at the Chalk River Nuclear Laboratories. This 10-MW reactor will produce key medical and industrial radio-isotopes such as 99 Mo, 125 I, and 192 Ir. As the prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor since standards for the licensing of new research reactors have not been developed yet by the licensing authority in Canada

  13. (1S,3S,8R,9S,10R-9,10-Epoxy-3,7,7,10-tetramethyltricyclo[6.4.0.01,3]dodecane

    Directory of Open Access Journals (Sweden)

    Abdoullah Bimoussa

    2014-04-01

    Full Text Available The title compound, C16H26O, was synthesized by treating (1S,3S,8R-3,7,7,10-tetramethyltricyclo[6.4.0.01,3]dodec-9-ene with metachloroperbenzoic acid. The molecule is built up from two fused six- and seven-membered rings. The six-membered ring has a half-chair conformation, whereas the seven-membered ring displays a boat conformation. In the crystal, there are no significant intermolecular interactions present.

  14. Joint German/French S4-Analytical Report

    International Nuclear Information System (INIS)

    Miemczyk, H.

    1979-03-01

    A joint German/French program was initiated to investigate in detail the behaviour of artificially defected fuel pins in a sodium loop of the SILOE reactor at Grenoble/France. Three irradiation experiments have been conducted in SILOE on representative SNR-type fuel pins (mixed oxide, low density, stainless steel cladding, external diameter 6 mm). The first experiment, S2, had been an unirradiated pin with a large interstitial defect (machined slit of 30x1 mm). The two following pins, S4 and S3, have been pre-irradiated in RAPSODIE (365 efpd, 10.6 % burnup). The main results of the S4-experiment are described and evaluated in the present report. They concern the following important aspects: sodium-uranate/plutonate formation and its kinetics, fuel loss, fission product release and fuel behaviour

  15. CephFS: a new generation storage platform for Australian high energy physics

    Science.gov (United States)

    Borges, G.; Crosby, S.; Boland, L.

    2017-10-01

    This paper presents an implementation of a Ceph file system (CephFS) use case at the ARC Center of Excellence for Particle Physics at the Terascale (CoEPP). CoEPP’s CephFS provides a posix-like file system on top of a Ceph RADOS object store, deployed on commodity hardware and without single points of failure. By delivering a unique file system namespace at different CoEPP centres spread across Australia, local HEP researchers can store, process and share data independently of their geographical locations. CephFS is also used as the back-end file system for a WLCG ATLAS user area at the Australian Tier-2. Dedicated SRM and XROOTD services, deployed on top of CoEPP’s CephFS, integrates it in ATLAS data distributed operations. This setup, while allowing Australian HEP researchers to trigger data movement via ATLAS grid tools, also enables local posix-like read access providing greater control to scientists of their data flows. In this article we will present details on CoEPP’s Ceph/CephFS implementation and report performance I/O metrics collected during the testing/tuning phase of the system.

  16. EST Table: FS748350 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available PREDICTED: similar to fetal alzheimer antigen, falz [Nasonia vitripennis] 10/09/08 37 %/193 aa FBpp0290563|E...811424.1| PREDICTED: similar to fetal alzheimer antigen, falz [Tribolium castaneum] FS748350 caL- ...

  17. EST Table: FS869999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS869999 E_FL_fner_41G01_R_0 10/09/28 90 %/258 aa ref|NP_001037132.1| ribosomal pro...6-PB 10/08/29 38 %/244 aa R151.3#CE00744#WBGene00004417#locus:rpl-6#Ribosomal protein ML16#status:Confirmed#UniProt:P4799

  18. EST Table: FS911308 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911308 E_FL_fufe_22N11_F_0 11/12/09 n.h 10/09/28 53 %/286 aa ref|XP_002092266.1| GE14...094 [Drosophila yakuba] gb|EDW91978.1| GE14094 [Drosophila yakuba] 10/09/12 53 %/286 aa FBpp0259104|DyakGE14

  19. An integral metallic-fueled and lead-cooled reactor concept for the 4th generation reactor

    International Nuclear Information System (INIS)

    Santos, Adimir dos; Nascimento, Jamil Alves do

    2002-01-01

    An Integral Lead Reactor (ILR) concept is proposed for the 4th generation reactor to be used in the future. The ILR is loaded with metallic fuel and cooled by lead. It was evaluated in the 300-1500 MWe power range with the Japanese Fast Set 2 cross sections library. This set was tested against several fast benchmarks and the criticality uncertainty was found to be 0.51 %Δk. The reactor is started with U-Zr and changes to the U-TRU-Zr-RE fuel in a stepwise way. In the equilibrium cycle, the burnup reactivity is less than β eff for a core of the order of 300 MWe, pin diameter of 10.4 mm and a pin-pinch to diameter ratio of 1.308. The lead void reactivity is negative for reactor power less than 750 MWe. There is a need to improve the nuclear data for the major actinides. (author)

  20. An integral metallic-fueled and lead-cooled reactor concept for the 4th generation reactor

    International Nuclear Information System (INIS)

    Santos, A. dos; Nascimento, J.A. do

    2002-01-01

    An Integral Lead Reactor (ILR) concept is proposed for the 4th generation reactor to be used in the future. The ILR is loaded with metallic fuel and cooled by lead. It was evaluated in the 300-1500 MWe power range with the Japanese Fast Set 2 cross sections library. This set was tested against several fast benchmarks and the criticality uncertainty was found to be 0.51 % Δk. The reactor is started with U-Zr and changes to the U-TRU-Zr-RE fuel in a stepwise way. In the equilibrium cycle, the burnup reactivity is less than β eff for a core of the order of 300 MWe, pin diameter of 10.4 mm and a pin-pitch to diameter ratio of 1.308. The lead void reactivity is negative for reactor power less than 750 MWe. There is a need to improve the nuclear data for the major actinides. (author)

  1. InterProScan Result: FS817458 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS817458 FS817458_1_ORF1 B27ECCF086D27F4E PFAM PF00067 p450 3.1e-28 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  2. InterProScan Result: FS865512 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS865512 FS865512_4_ORF2 5E2A7F9124D73F34 PRINTS PR00385 P450 1.7e-09 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  3. InterProScan Result: FS783911 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS783911 FS783911_6_ORF1 F4FB77A4630C2DCB PRINTS PR00385 P450 8.8e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  4. EST Table: FS796494 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 38 aa ref|XP_001945612.1| PREDICTED: similar to glucocerebrosidase, partial [Acyr...9/10 42 %/261 aa gi|91087345|ref|XP_975608.1| PREDICTED: similar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS796494 ffbm ...

  5. Dispersion management for a sub-10-fs, 10 TW optical parametric chirped-pulse amplifier.

    Science.gov (United States)

    Tavella, Franz; Nomura, Yutaka; Veisz, Laszlo; Pervak, Vladimir; Marcinkevicius, Andrius; Krausz, Ferenc

    2007-08-01

    We report the amplification of three-cycle, 8.5 fs optical pulses in a near-infrared noncollinear optical parametric chirped-pulse amplifier (OPCPA) up to energies of 80 mJ. Improved dispersion management in the amplifier by means of a combination of reflection grisms and a chirped-mirror stretcher allowed us to recompress the amplified pulses to within 6% of their Fourier limit. The novel ultrabroad, ultraprecise dispersion control technology presented in this work opens the way to scaling multiterawatt technology to even shorter pulses by optimizing the OPCPA bandwidth.

  6. Design of a 10-bit 100 MSamples/s BiCMOS D/A converter

    DEFF Research Database (Denmark)

    Jørgensen, Ivan Harald Holger; Tunheim, S. A.

    1995-01-01

    A 10-bit 100 MSamples/s current-steering D/A converter (DAC) has been designed and processed in a 0.8 μm BiCMOS process. The DAC is intended for applications using direct digital synthesis, and focus has been set on achieving a high spurious free dynamic range (SFDR). The main part of the DAC...... current cell to steer the current. At a generated frequency of fg≈0.3·fs (fs=100 MSamples/s), the simulated SFDR is larger than 60 dB. The DAC operates at 5 V, and has a power consumption of approximately 650 mW. The area of the chip-core is 2.2 mm×2.2 mm. Furthermore a measure to estimate the SFDR...... for the DAC based on short term simulations is presented. This measure seems to correspond very well with SFDR for long term simulations...

  7. EST Table: FS914945 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS914945 E_FL_fufe_33M09_F_0 10/09/28 36 %/210 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  8. EST Table: FS918359 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS918359 E_FL_fufe_44C07_F_0 10/09/28 37 %/227 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  9. EST Table: FS891235 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS891235 E_FL_ftes_02B20_R_0 11/12/09 GO hit GO:0003779(actin binding)|GO:0007010(cytoskeleton... organization)|GO:0015629(actin cytoskeleton)|GO:0030036(actin cytoskeleton organization) 10/09/2

  10. Development of a helical-coil double wall tube steam generator for 4S reactor

    International Nuclear Information System (INIS)

    Kitajima, Yuko; Maruyama, Shigeki; Jimbo, Noboru; Hino, Takehisa; Sato, Katsuhiko

    2011-01-01

    The 4S, Super-Safe Small and Simple, is a small-sized sodium-cooled fast reactor. A fast reactor usually uses sodium as a coolant to transfer heat from core to turbine/generator system. The heat of the intermediate heat transport system and that of the water stream systems are exchanged by the steam generator (SG) tubes. If the tube failure occurs, a sodium/water reaction could be occurred. To prevent the reaction and enhance safety, a helical-coil-type double wall tube with wire mesh interlayer and continuous monitoring systems of tube failure are applied to the SG of the 4S. The development and general features of this type double wall tube were described in Ref. 1) and Ref. 2). Those paper summarized following results; The tubes studied in these references were straight type. To establish this SG, development of manufacturing method of helical-coil-type double wall tube and validation of the tube failure monitoring system are needed. In this study, three demonstration tests have been performed; welding test of the double wall tube to manufacture the tubes with 70-80m length, assembling test of the helical-coil tube, and confirmation test of the tube processing system using the fabricated helical-coil tubes. As a result, following technologies have been successfully established. (1) Development of the welding techniques for manufacturing of the helical-coil-type double wall tube with wire mesh interlayer. (2) The confirmation test for manufacturing the helical coil tube of the SG. (author)

  11. Safety features of the MAPLE-X10 reactor design

    International Nuclear Information System (INIS)

    Lee, A.G.; Bishop, W.E.; Heeds, W.

    1990-01-01

    This paper reports on the MAPLE-X10 reactor D 2 O-reflected, H 2 O-cooled and -moderated pool- type reactor, under construction at the Chalk River Nuclear Laboratories. This 10-MW will produce key medical and industrial radioisotopes such as 99 Mo, 125 I, and 192 Ir. The prototype for the MAPLE research reactor concept, the reactor incorporates diverse safety features both inherent in the design and in the added engineered systems. The safety requirements are analogous to those of the Canadian CANDU power reactor as standards for the licensing of new research reactors have not been developed by the licensing authority in Canada

  12. EST Table: FS884513 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS884513 E_FL_ftes_30F14_F_0 10/09/28 31 %/166 aa ref|XP_002572677.1| nuclear movement... protein related [Schistosoma mansoni] emb|CAZ28909.1| nuclear movement protein related [Schistosoma mans

  13. EST Table: FS758854 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS758854 E_FL_fcaL_09I20_F_0 10/09/28 35 %/195 aa ref|XP_001842174.1| sensitized chromosome inheritance... modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance m

  14. EST Table: FS805970 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available milar to xaa-pro dipeptidase app(e.coli) [Nasonia vitripennis] 10/09/09 47 %/178 aa FBpp0123641|DanaGF20449-...PREDICTED: similar to xaa-pro dipeptidase app(e.coli) [Tribolium castaneum] FS727105 fmgV ...

  15. EST Table: FS916089 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916089 E_FL_fufe_37E08_F_0 10/09/28 43 %/186 aa ref|XP_001843810.1| mediator comp...lex [Culex quinquefasciatus] gb|EDS34592.1| mediator complex [Culex quinquefasciatus] 10/09/12 36 %/187 aa F...1082463|ref|XP_971521.1| PREDICTED: similar to mediator complex [Tribolium castaneum] BJ984999 fufe ...

  16. Steady-state chlorophyll fluorescence (Fs) as a tool to monitor plant heat and drought stress

    Science.gov (United States)

    Cendrero Mateo, M.; Carmo-Silva, A.; Salvucci, M.; Moran, S. M.; Hernandez, M.

    2012-12-01

    Crop yield decreases when photosynthesis is limited by heat or drought conditions. Yet farmers do not monitor crop photosynthesis because it is difficult to measure at the field scale in real time. Steady-state chlorophyll fluorescence (Fs) can be used at the field level as an indirect measure of photosynthetic activity in both healthy and physiologically-perturbed vegetation. In addition, Fs can be measured by satellite-based sensors on a regular basis over large agricultural regions. In this study, plants of Camelina sativa grown under controlled conditions were subjected to heat and drought stress. Gas exchange and Fs were measured simultaneously with a portable photosynthesis system under light limiting and saturating conditions. Results showed that Fs was directly correlated with net CO2 assimilation (A) and inversely correlated with non-photochemical quenching (NPQ). Analysis of the relationship between Fs and Photosynthetically Active Radiation (PAR) revealed significant differences between control and stressed plants that could be used to track the status, resilience, and recovery of photochemical processes. In summary, the results provide evidence that Fs measurements, even without normalization, are an easy means to monitor changes in plant photosynthesis, and therefore, provide a rapid assessment of plant stress to guide farmers in resource applications. Figure1. Net CO2 assimilation rate (A) of Camelina sativa plants under control conditions and after heat stress exposure for 1 or 3 days (1d-HS and 3d-HS, respectively) (right) and control, drought and re-watering conditions (left). Conditions for infra-red gas analysis were: reference CO2 = 380 μmol mol-1, PPFD = 500 μmol m-2 s-1 and Tleaf set to 25°C (control, drought and re-water) or 35°C (HS). Different letters denote significant differences at the α=0.05 level. Values are means±SEM (n=10). Figure 2. Stable chlorophyll fluorescence (Fs) of Camelina sativa plants under control conditions and

  17. EST Table: FS772438 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 0040007(growth) 10/09/28 30 %/138 aa ref|XP_966819.1| PREDICTED: similar to myostatin [Tribolium castaneum] ... 30 %/138 aa gi|91085397|ref|XP_966819.1| PREDICTED: similar to myostatin [Tribolium castaneum] FS772438 fcaL ...

  18. U.S. and foreign breeder reactors

    International Nuclear Information System (INIS)

    Hill, E.H.

    1977-01-01

    The running battle between Congress and the Administration over the Clinch River Breeder Reactor Plant (CRBRP) Project has provoked an increased interest in domestic and foreign breeder reactor programs. Perhaps an understanding of the history of breeders here and abroad will serve to place the CRBRP in perspective and allow some analysis of how the U.S. appears on the global canvas. Breeder reactor technology has, for the most part, settled down to concentration on the liquid metal fast breeder reactor (LMFBR). This is the result of 32 years of experience with reactors employing a fast neutron flux and even longer experience with liquid metal coolants. However, a number of U.S. utilities are sponsoring a gas cooled fast reactor program as an alternative technology to the LMFBR. This development program is supported by the U.S. Department of Energy

  19. Test reactor: basic to U.S. breeder reactor development

    International Nuclear Information System (INIS)

    Miller, B.J.; Harness, A.J.

    1975-01-01

    Long-range energy planning in the U. S. includes development of a national commercial breeder reactor program. U. S. development of the LMFBR is following a conservative sequence of extensive technology development through use of test reactors and demonstration plants prior to construction of commercial plants. Because materials and fuel technology development is considered the first vital step in this sequence, initial U. S. efforts have been directed to the design and construction of a unique test reactor. The Fast Flux Test Facility, FFTF, is a 400 MW(t) reactor with driver fuel locations, open test locations, and closed loops for higher risk experiments. The FFTF will provide a prototypic LMFBR core environment with sufficient instrumentation for detailed core environmental characterization and a testing capability substituted for breeder capability. The unique comprehensive fuel and materials testing capability of the FFTF will be key to achieving long-range objectives of increased power density, improved breeding gain and shorter doubling times. (auth)

  20. The status of the PIK reactor

    Energy Technology Data Exchange (ETDEWEB)

    Petrov, Yu V [Academy of Sciences of Russia, Petersburg Nuclear Physics Institute, Gatchina, St. Petersburg (Russian Federation)

    1992-07-01

    This report describes the 100 MW research reactor PIK which is now under construction. The thermal neutron flux in the heavy water reflector exceeds 10{sup 15} cm{sup -2}s{sup -1}; in the light water trap, it is about 4{center_dot}10{sup 15} cm{sup -2}s{sup -1}. The replaceable core vessel allows to vary the parameters of the core over a wide range. The reactor provides sources of hot, cold and ultracold neutrons for 10 horizontal, 6 inclined neutron beams, and 8 neutron guides. At the ends of the beam tubes, the neutron flux is 10{sup 10} - 10{sup 11} cm{sup -2}s{sup -1}. The flux of the long wave neutrons exceeds 10{sup 9} cm{sup -2}s{sup -1}. To ensure precise measurements, the experimental hall is protected against vibrations. The project meets all modern safety requirements. The calculated parameters of the reactor were verified using a full-scale mock-up. Seventy percent of the reactor construction and installation were completed in the beginning of 1992. (author)

  1. EST Table: FS911502 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available eritance modifier 19 [Culex quinquefasciatus] gb|EDS39679.1| sensitized chromosome inheritance...FS911502 E_FL_fufe_23G14_F_0 11/12/09 n.h 10/09/28 35 %/234 aa ref|XP_001842174.1| sensitized chromosome inh

  2. Remedial Investigation/Feasibility Study (RI/FS) process, elements and techniques guidance

    Energy Technology Data Exchange (ETDEWEB)

    1993-12-01

    This manual provides detailed guidance on Remedial Investigation/Feasibility Studies (RI/FSs) conducted pursuant to the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) at Department of Energy (DOE) facilities. The purpose of the RI/FS, to assess the risk posed by a hazardous waste site and to determine the best way to reduce that risk, and its structure (site characterization, risk assessment, screening and detailed analysis of alternatives, etc.) is defined in the National Oil and Hazardous Substances Pollution Contingency Plan (NCP) and further explained in the Environmental Protection Agency`s (EPA`s) Guidance for Conducting Remedial Investigations and Feasibility Studies Under CERCLA (Interim Final) 540/G-89/004, OSWER Directive 9355.3-01, October 1988. Though issued in 1988, the EPA guidance remains an excellent source of information on the conduct and structure of an RI/FS. This document makes use of supplemental RI/FS-related guidance that EPA has developed since its initial document was issued in 1988, incorporates practical lessons learned in more than 12 years of experience in CERCLA hazardous site remediation, and drawing on those lessons, introduces the Streamlined Approach For Environmental Restoration (SAFER), developed by DOE as a way to proceed quickly and efficiently through the RI/FS process at DOE facilities. Thus as its title implies, this guidance is intended to describe in detail the process and component elements of an RI/FS, as well as techniques to manage the RI/FS effectively.

  3. EST Table: FS920882 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available DICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimida...|91091890|ref|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ... ...zoles 3 [Tribolium castaneum] 10/09/13 61 %/256 aa FBpp0282833|DpseGA20454-PA 10/08

  4. Comparative Genome Analyses of Serratia marcescens FS14 Reveals Its High Antagonistic Potential

    Science.gov (United States)

    Li, Pengpeng; Kwok, Amy H. Y.; Jiang, Jingwei; Ran, Tingting; Xu, Dongqing; Wang, Weiwu; Leung, Frederick C.

    2015-01-01

    S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs) in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens. PMID:25856195

  5. Comparative genome analyses of Serratia marcescens FS14 reveals its high antagonistic potential.

    Science.gov (United States)

    Li, Pengpeng; Kwok, Amy H Y; Jiang, Jingwei; Ran, Tingting; Xu, Dongqing; Wang, Weiwu; Leung, Frederick C

    2015-01-01

    S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs) in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens.

  6. Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3

    Energy Technology Data Exchange (ETDEWEB)

    Lin, Hsien-Chuan, E-mail: linsc@iner.org.tw [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China); Yaur, Shung-Jung; Lin, Tzung-Yi; Kuo, Weng-Sheng; Shiue, Jin-Yih; Huang, Yu-Lung [Nuclear Engineering Division, Institute of Nuclear Energy Research, 1000, Wenhua Rd., Jiaan Village, Longtan Township, Taoyuan County 32546, Taiwan (China)

    2012-12-15

    Highlights: Black-Right-Pointing-Pointer Studsvik's core management system (CMS) was applied to Taiwan Power Company's pressurized water reactor. Black-Right-Pointing-Pointer Advanced calculation model of shutdown cooling, B-10 depletion and integrated pin exposure were introduced. Black-Right-Pointing-Pointer Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated to measurement data. Black-Right-Pointing-Pointer The uncertainty of each item was quantified. - Abstract: This paper presents the validation of Studsvik core management system (CMS) for application to the Maanshan units 1 and 2 reactor core physics analysis (Huang and Yang, 1994). The methodology was validated by demonstrating the ability to obtain accurate and reliable results for various conditions and applications. Core characteristic parameters such as boron letdown, low power physics test (LPPT) predictions, and reaction rate were validated. Analytical results have been compared to measured data and reliability factors of the method have been quantified.

  7. CORRELATIONS BETWEEN HOMOLOGUE CONCENTRATIONS OF PCDD/FS AND TOXIC EQUIVALENCY VALUES IN LABORATORY-, PACKAGE BOILER-, AND FIELD-SCALE INCINERATORS

    Science.gov (United States)

    The toxic equivalency (TEQ) values of polychlorinated dibenzo-p-dioxins and polychlorinated dibenzofurans (PCDD/Fs) are predicted with a model based on the homologue concentrations measured from a laboratory-scale reactor (124 data points), a package boiler (61 data points), and ...

  8. EST Table: FS789999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS789999 E_FL_ffbm_02F05_F_0 10/09/28 42 %/246 aa ref|XP_971541.1| PREDICTED: simil...ar to AGAP008392-PA [Tribolium castaneum] gb|EFA09946.1| hypothetical protein TcasGA2_TC012099 [Tribolium ca

  9. Emission of PCDD/Fs and dioxin-like PCBs from metallurgy industries in S. Korea.

    Science.gov (United States)

    Yu, Byeong-Woon; Jin, Guang-Zhu; Moon, Young-Hoon; Kim, Min-Kwan; Kyoung, Jong-Dai; Chang, Yoon-Seok

    2006-01-01

    The metallurgy industry and municipal waste incinerators are considered the main sources of polychlorinated dibenzo-p-dioxin and dibenzofurans (PCDD/Fs) in many countries. This study investigated the emission factors and total emissions of PCDD/Fs and dioxin-like polychlorinated biphenyls (PCBs) emitted from metallurgy industries (including ferrous and nonferrous foundries) in Korea. The toxic equivalency (TEQ) emission factor of PCDD/Fs was the highest for secondary copper production, at 24451 ng I-TEQ/ton. The total estimated emissions of PCDD/Fs from these sources were 35.259 g I-TEQ/yr, comprising 0.088 g I-TEQ/yr from ferrous foundries, 31.713 g I-TEQ/yr from copper production, 1.716 g I-TEQ/yr from lead production, 0.111 g I-TEQ/yr from zinc production, and 1.631 g I-TEQ/yr from aluminum production. The total estimated annual amounts of dioxin-like PCBs emitted from these sources were 13.260 g WHO-TEQ/yr, comprising 0.014 g WHO-TEQ/yr from ferrous foundries, 12.675 g WHO-TEQ/yr from copper production, 0.170 g WHO-TEQ/yr from lead production, 0.017 g WHO-TEQ/yr from zinc production, and 0.384 g WHO-TEQ/yr from aluminum production. The highest emission factor was found for secondary copper smelting, at 9770 ng WHO-TEQ/ton.

  10. Economical and neutronic performance of HYLIFE-II with mixture of 90% flibe + 10% UF4 (or ThF4)

    International Nuclear Information System (INIS)

    Uenalan, Sebahattin

    2004-01-01

    This work investigated the neutronics behavior and the economics of the HYLIFE-II reactor with ThF 4 and UF 4 , which produces an electrical power of 1 GW from the fusion power of 2.857 GW during the operation period of 30 years. The use of ThF 4 and UF 4 is realized by a mixture zone consisted of 90% flibe (Li 2 BeF 4 ) and 10% fuel, instead of 100% flibe coolant. The mixture compositions are selected as 90% flibe + 10% UF 4 , 90% flibe + 10% ThF 4 and 90% flibe + 5% UF 4 + 5% ThF 4 . The capacity factor of the reactor is 0.75. The mixtures, with zone thickness of 65 cm were circulated with periods of 20.22, 19.89 and 20.11 s during the operation period of 30 years, respectively. In addition, for flibe + UF 4 , power stabilization by means of plutonium separation from the mixture was applied. The use of fuel materials in the HYLIFE-II reactor resulted in high energy production, sufficient tritium breeding, significant fissile fuel breeding and low radiation damage in the first wall. The average values of tritium breeding ratio over 30 years are between 1.08 and 1.12, higher than 1.0 indicating sufficient tritium breeding. Generally, the mixtures with ThF 4 show better performance than the mixture with UF 4 in terms of more energy production and significant fissile fuel breeding. The neutronic performance of the reactor increases with the operational period. However, the stabilization process performed after operation for 6 years causes all neutronic values to remain nearly constant during the followed operation time. At the 6th year of operation, the power production, which is ∼1540 MW(electric) at startup, reached the electrical power of 2 GW for flibe + UF 4 . The power production without the separation process reached ∼3500 MW(electric) for the mixtures with ThF 4 and ∼3000 MW(electric) for the mixture with UF 4 . At the end of the operation period, helium production values in the first wall, made of Hastelloy, are calculated as 590 ppm without the

  11. Infrared Observations of FS CMa Stars

    Science.gov (United States)

    Sitko, Michael L.; Russell, R. W.; Lynch, D. K.; Grady, C. A.; Hammel, H. B.; Beerman, L. C.; Day, A. N.; Huelsman, D.; Rudy, R. J.; Brafford, S. M.; Halbedel, E. M.

    2009-01-01

    A subset of non-supergiant B[e] stars has recently been recognized as forming a fairly unique class of objects with very strong emission lines, infrared excesses, and locations not associated with star formation. The exact evolutionary state of these stars, named for the prototype FS CMa, is uncertain, and they have often been classified as isolated Herbig AeBe stars. We present infrared observations of two of these stars, HD 45677 (FS CMa), HD 50138 (MWC 158), and the candidate FS CMa star HD 190073 (V1295 Aql) that span over a decade in time. All three exhibit an emission band at 10 microns due to amorphous silicates, confirming that much (if not all) of the infrared excess is due to dust. HD 50138 is found to exhibit 20% variability between 3-13 microns that resembles that found in pre-main sequence systems (HD 163296 and HD 31648). HD 45677, despite large changes at visual wavelengths, has remained relatively stable in the infrared. To date, no significant changes have been observed in HD 190073. This work is supported in part by NASA Origins of Solar Systems grant NAG5-9475, NASA Astrophysics Data Program contract NNH05CD30C, and the Independent Research and Development program at The Aerospace Corporation.

  12. The nuclear design of the MAPLE-X10 reactor

    International Nuclear Information System (INIS)

    Heeds, W.; Lebenhaft, J.R.; Lee, A.G.; Carlson, P.A.; McIlvain, H.; Lidstone, R.F.

    1995-01-01

    AECL is currently building the 10-MW MAPLE-X10 reactor at the Chalk River Laboratories to operate as a dedicated producer of commercial-scale quantities of key medical and industrial radioisotopes and as a demonstration of the MAPLE reactor design. In support of the safety and licensing analyses, static physics calculations have been performed to determine the neutronic performance and safety characteristics of the MAPLE-X10 reactor. This report summarizes results from the static physics calculations for several core conditions prior to commencing radioisotope production. (author)

  13. EST Table: FS880151 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available to DNA mismatch repair protein pms2 [Acyrthosiphon pisum] 10/09/11 63 %/127 aa FBpp0252351|DwilGK23208-PA 1...aa gi|91079030|ref|XP_974934.1| PREDICTED: similar to DNA mismatch repair protein pms2 [Tribolium castaneum] FS880151 ftes ...

  14. EST Table: FS895236 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available match repair)|GO:0030983(mismatched DNA binding) 10/09/28 68 %/141 aa ref|XP_001663861.1| DNA mismatch repair protein pms2... [Aedes aegypti] gb|EAT34048.1| DNA mismatch repair protein pms2 [Aedes aegypti] 10/09/12 62 %...1 %/140 aa gi|91079030|ref|XP_974934.1| PREDICTED: similar to DNA mismatch repair protein pms2 [Tribolium castaneum] FS895236 ftes ...

  15. Adaptation of the S-5-S Pendulím Seismometer for Measurement of Rotational Ground Motion

    Czech Academy of Sciences Publication Activity Database

    Knejzlík, Jaromír; Kaláb, Zdeněk; Rambouský, Zdeněk

    2012-01-01

    Roč. 16, č. 4 (2012), s. 649-656 ISSN 1383-4649 Institutional support: RVO:68145535 Keywords : rotation al ground motion * experimental measurement * mining induced seismicity * S-5-S seismometer Subject RIV: DC - Siesmology, Volcanology, Earth Structure Impact factor: 1.388, year: 2012 http://link.springer.com/article/10.1007%2Fs10950-012-9279-6

  16. Functional analysis of Waardenburg syndrome-associated PAX3 and SOX10 mutations: report of a dominant-negative SOX10 mutation in Waardenburg syndrome type II.

    Science.gov (United States)

    Zhang, Hua; Chen, Hongsheng; Luo, Hunjin; An, Jing; Sun, Lin; Mei, Lingyun; He, Chufeng; Jiang, Lu; Jiang, Wen; Xia, Kun; Li, Jia-Da; Feng, Yong

    2012-03-01

    Waardenburg syndrome (WS) is an auditory-pigmentary disorder resulting from melanocyte defects, with varying combinations of sensorineural hearing loss and abnormal pigmentation of the hair, skin, and inner ear. WS is classified into four subtypes (WS1-WS4) based on additional symptoms. PAX3 and SOX10 are two transcription factors that can activate the expression of microphthalmia-associated transcription factor (MITF), a critical transcription factor for melanocyte development. Mutations of PAX3 are associated with WS1 and WS3, while mutations of SOX10 cause WS2 and WS4. Recently, we identified some novel WS-associated mutations in PAX3 and SOX10 in a cohort of Chinese WS patients. Here, we further identified an E248fsX30 SOX10 mutation in a family of WS2. We analyzed the subcellular distribution, expression and in vitro activity of two PAX3 mutations (p.H80D, p.H186fsX5) and four SOX10 mutations (p.E248fsX30, p.G37fsX58, p.G38fsX69 and p.R43X). Except H80D PAX3, which retained partial activity, the other mutants were unable to activate MITF promoter. The H80D PAX3 and E248fsX30 SOX10 were localized in the nucleus as wild type (WT) proteins, whereas the other mutant proteins were distributed in both cytoplasm and nucleus. Furthermore, E248fsX30 SOX10 protein retained the DNA-binding activity and showed dominant-negative effect on WT SOX10. However, E248fsX30 SOX10 protein seems to decay faster than the WT one, which may underlie the mild WS2 phenotype caused by this mutation.

  17. New class of compact diode pumped sub 10 fs lasers for biomedical applications

    DEFF Research Database (Denmark)

    Le, T.; Mueller, A.; Sumpf, B.

    2016-01-01

    Diode-pumping Ti: sapphire lasers promises a new approach to low-cost femtosecond light sources. Thus in recent years much effort has been taken just to overcome the quite low power and low beam qualities of available green diodes to obtain output powers of several hundred milliwatts from a fs-la...

  18. FS65 Disposition Option Report

    Energy Technology Data Exchange (ETDEWEB)

    Wenz, Tracy R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-09-25

    This report outlines the options for dispositioning the MOX fuel stored in FS65 containers at LANL. Additional discussion regarding the support equipment for loading and unloading the FS65 transport containers is included at the end of the report.

  19. U.S. Domestic Reactor Conversion Programs

    International Nuclear Information System (INIS)

    Woolstenhulme, Eric

    2008-01-01

    The Conversion Projects Include: the revision of the facilities safety basis documents and supporting analysis, the fabrication of new LEU fuel, the change-out of the reactor core, and the removal of the used HEU fuel (by INL University Fuels Program or DOE-NE). The major entities involved are: the U.S. Nuclear Regulatory Commission, the University reactor department, the fuel and hardware fabricators, the Spent fuel receipt facilities, the Spent fuel shipping services, and the U.S. Department of Energy and their subcontractors. Three major Reactor Conversion Program milestones have been accomplished since 2006: the conversion of the TRIGA reactor at Texas A and M University Nuclear Science Center, the conversion of the University of Florida Training Reactor, and the conversion of the Purdue University Reactor. Four Reactor Conversion Program milestones yet to be accomplished in 2008 and 2009: the Washington State University Nuclear Radiation Center reactor, the Oregon State University TRIGA Reactor, the University of Wisconsin Nuclear Reactor, and the Neutron Radiography Reactor Facility. NNSA is committed to doing things cheaper, better, smarter, safer through a 'Lessons Learned' process. The conversion team assessed each major activity grouping: Project Initiation, Conversion Proposal Development, Fuel Fabrication and Hardware, Core Conversion, and Spent Nuclear Fuel Removal. Issues were identified and recommendations were given

  20. In vitro effects of PCDDs/Fs on NK-like cell activity of Eisenia andrei earthworms

    Directory of Open Access Journals (Sweden)

    Hayet Belmeskine

    2012-02-01

    Full Text Available In this study, we assessed in vitro the effects of PCDD/Fs on the NK-like cell activity in Eisenia andrei earthworms using flow cytometry for analysis. NK-like coelomocytes isolated from E. andrei and used as effectors were exposed to various concentrations of PCDDs/Fs mixture, C1 (6.25x10-3 ng 2378- TCDD/mL, C2 (12.5x10-3 ng 2378-TCDD/mL and C3 (25x10-3 ng 2378-TCDD/mL, before adding them to human tumoral cells (K562 used as targets. We evaluated the percentage of targets lysed by Nk-like cells. The results showed a significant stimulation of the NKlike activity at C3 when PCDD/Fs were not removed from effectors before contact with targets, while no effects were noted when the effectors were washed (PCDD/Fs removed or fixed. Assessment of the viability of the targets (K562, exposed alone and separately from effectors, to the three concentrations of PCDD/Fs, C1, C2 and C3, showed that all these concentrations were cytotoxic for K562. Results suggest that PCDD/Fs concentrations tested in this assay may be considered too low to induce suppressive effects on the immune function such as the NK-like activity in E. andrei earthworms.

  1. Comparative genome analyses of Serratia marcescens FS14 reveals its high antagonistic potential.

    Directory of Open Access Journals (Sweden)

    Pengpeng Li

    Full Text Available S. marcescens FS14 was isolated from an Atractylodes macrocephala Koidz plant that was infected by Fusarium oxysporum and showed symptoms of root rot. With the completion of the genome sequence of FS14, the first comprehensive comparative-genomic analysis of the Serratia genus was performed. Pan-genome and COG analyses showed that the majority of the conserved core genes are involved in basic cellular functions, while genomic factors such as prophages contribute considerably to genome diversity. Additionally, a Type I restriction-modification system, a Type III secretion system and tellurium resistance genes are found in only some Serratia species. Comparative analysis further identified that S. marcescens FS14 possesses multiple mechanisms for antagonism against other microorganisms, including the production of prodigiosin, bacteriocins, and multi-antibiotic resistant determinants as well as chitinases. The presence of two evolutionarily distinct Type VI secretion systems (T6SSs in FS14 may provide further competitive advantages for FS14 against other microbes. To our knowledge, this is the first report of comparative analysis on T6SSs in the genus, which identifies four types of T6SSs in Serratia spp.. Competition bioassays of FS14 against the vital plant pathogenic bacterium Ralstonia solanacearum and fungi Fusarium oxysporum and Sclerotinia sclerotiorum were performed to support our genomic analyses, in which FS14 demonstrated high antagonistic activities against both bacterial and fungal phytopathogens.

  2. EST Table: FS799999 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS799999 E_FL_fmgV_02M15_F_0 10/09/28 100 %/197 aa ref|NP_001036966.1| lipase-1 [Bo...mbyx mori] dbj|BAC00960.1| lipase-1 [Bombyx mori] gb|AAZ66799.1| lipase [Samia cynthia ricini] gb|ABB90967.1

  3. EST Table: FS773562 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available /09/28 91 %/214 aa ref|NP_001036831.1| saposin-related [Bombyx mori] dbj|BAA23126.1| BmP109 [Bombyx mori] 10...0 38 %/197 aa gi|91077504|ref|XP_966852.1| PREDICTED: similar to saposin isoform 1 [Tribolium castaneum] FS773562 fcaL ...

  4. Preliminary studies on fast particle diagnostics for the future fs-laser facility at PALS

    Czech Academy of Sciences Publication Activity Database

    Margarone, Daniele; Krása, Josef; Láska, Leoš; Velyhan, Andriy; Mocek, Tomáš; Torrisi, L.; Ando, L.; Gammino, S.; Prokůpek, J.; Krouský, Eduard; Pfeifer, Miroslav; Ullschmied, Jiří; Rus, Bedřich

    2010-01-01

    Roč. 165, 6-10 (2010), s. 419-428 ISSN 1042-0150 R&D Projects: GA AV ČR IAA100100715 Institutional research plan: CEZ:AV0Z10100523; CEZ:AV0Z20430508 Keywords : fs-laser plasma * electron streams * ion streams * electron spectrometer * ion collectors Subject RIV: BL - Plasma and Gas Discharge Physics Impact factor: 0.660, year: 2010

  5. Spectrally narrowed emissions in 2,5-bis(4-biphenylyl)thiophene crystals pumped by fs laser pulse

    International Nuclear Information System (INIS)

    Kobayashi, S.; Sasaki, F.; Yanagi, H.; Hotta, S.; Ichikawa, M.; Taniguchi, Y.

    2005-01-01

    Spectrally narrowed emission (SNE) in 2,5-bis(4-biphenylyl)thiophene (BP1T) crystals is investigated using fs laser pulse. Two different types of narrowing are observed at different vibronic emission bands with increasing pump intensities. Based on their pump intensity dependence and illumination area dependence, we assign the SNE at 20,200 cm -1 (β-band) to amplified spontaneous emission (ASE) and the SNE at 21,600 cm -1 (α-band) to superfluorescence rather than ASE

  6. Displacement sensor for measurement of fuel rod elongation in the LOFT reactors

    International Nuclear Information System (INIS)

    Billeter, T.R.

    1979-09-01

    Qualification tests conducted for a period of 700 hours of each of three displacement measuring (LVDT) sensors confirmed applicability of the design for use in the Loss-of-Fluid-Test (LOFT) reactor. Operationally, the sensor satisfies all specified requirements for LOFT. Even for imposed temperature transients at rates up to 100 0 F/s, the indicated displacement remained within the allowed maximum error band of +- 10% of reading. The 0.6-inch O.D. by 5.5-inch long sensor exhibited a linearly related signal output variation for displacement variations of up to 1-inch range. Long term operation at temperatures of 100 0 F to 800 0 F caused no perceptible permanent change of operating characteristics

  7. [Study on secondary metabolites of marine fungus Penicillium sp. FS60 from the South China Sea].

    Science.gov (United States)

    Zhang, Ling; Li, Dong-Li; Chen, Yu-Chan; Tao, Mei-Hua; Zhang, Wei-Min

    2012-07-01

    To study the secondary metabolites of the marine fungus Penicillium sp. FS60 from the South China Sea and their cytotoxicities. The compounds were isolated from the culture of strain FS60 by various chromatographic methods (silica gel, reverse silica gel, Sephadex-LH20, preparative TLC, HPLC and PTLC) and recrystallization. Their structures were identified by extensive analysis of their spectroscopic data. Compounds were tested for their cytotoxicities against SF-268, MCF-7, and NCI-H460 cell lines by SRB method. While, Compounds were tested for their antibacterial activities against S. aureus, E. coli and P. aeruginosa. Seven compounds were isolated from the culture and identified as methyl 2,4-dihydroxy-3,5,6-trimethylbenzoate (1), 4-hydroxyacetophenone (2), 5-hydroxymethyl-furoic acid (3), isochromophilones VIII (4), ergosterol (5), ergosterol peroxide (6), and cerevisterol (7). Compound 1 is isolated from the genus Penicillium for the first time. Compound 3 is demonstrated to have significant inhibition against S. aureus and P. aeruginosa. Compound 4 is demonstrated to have significant inhibition against the three cell lines.

  8. Biodegradation of Jet Fuel-4 (JP-4) in Sequencing Batch Reactors

    Science.gov (United States)

    1992-06-01

    nalw~eo %CUMENTATION PAGE__ _ _ _ _ _ _ _ _O 74S Ab -A258 020 L AW POi~W6 DATI .~ TYP AIMqm ,-& 0 U. glbs A~ I ma"&LFUN Mu BIODEGRADATION OF JET FUEL...Specific Objectives of This Proposal Are: 1. To assess the ability of C. resinae , P. chrysosporium and selected bacterial consortia to degrade individual...chemical components of JP-4. 2. To develop a sequencing batch reactor that utilizes C. resinae to degrade chemical components of JP-4 in contaminated

  9. Recent U.S. reactor operating experience

    International Nuclear Information System (INIS)

    Stello, V. Jr.

    1977-01-01

    A qualitative assessment of U.S. and foreign reactor operating experience is provided. Recent operating occurrences having potentially significant safety impacts on power operation are described. An evaluation of the seriousness of each of these issues and the plans for resolution is discussed. A quantitative report on U.S. reactor operational experience is included. The details of the NRC program for evaluating and applying operating reactor experience in the regulatory process is discussed. A review is made of the adequacy of operating reactor safety and environmental margins based on actual operating experience. The Regulatory response philosophy to operating reactor experiences is detailed. This discussion indicates the NRC emphasis on the importance of a balanced action plan to provide for the protection of public safety in the national interest

  10. Nielsen: Aladdin-Suite, FS89. Maskarade-Overture / Robert Layton

    Index Scriptorium Estoniae

    Layton, Robert

    1996-01-01

    Uuest heliplaadist "Nielsen: Aladdin-Suite, FS89. Maskarade-Overture, Prelude, Act 2. The Cockerels' Dance. Rhapsody Overture: An imaginary journey to the Faroe Islands, FS123. Helios Overture, FS32. Saga-Drom, FS46. Pan and Syrinx, FS87. Gothenburg Symphony Orchestra, Neeme Järvi" DG 447 757-2GH (72 minutes: DDD)

  11. Steam producing plant concept of 4S for oil sand extraction

    International Nuclear Information System (INIS)

    Matsuyama, Shinichiro; Nishiguchi, Youhei; Sakashita, Yoshiaki; Kasuga, Shoji; Kawashima, Masatoshi

    2009-01-01

    Plant concept of small fast reactor '4S' applying to continuous steam production for recovery of crude oil from oil sands was investigated. Assuming typical steam assisted gravity drainage (SAGD) plant whose production scale is 120,000 barrels per day of a crude oil, concept of nuclear steam supply system consisting of eight reactor modules for steam production and three reactor modules for electric generation of the 4S with a thermal rating of 135 MWt was established without any essential or significant design change from the preceding 4S with a thermal rating of 30 MWt. The 4S, provided for an oil sand extraction, will reduce greenhouse gas emission significantly, and has not much burden for development and licensing and has economic competitiveness. (author)

  12. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  13. Examination policy concerning the additional installation of No. 3 and No. 4 reactors in Takahama Nuclear Power Station and No. 3 and No. 4 reactors in Fukushima No. 2 Nuclear Power Station

    International Nuclear Information System (INIS)

    1980-01-01

    The Nuclear Safety Commission decided the annual examination policy on the modification of reactor installation in Takahama Nuclear Power Station to construct No. 3 and No. 4 reactors inquired under date of November 26, 1979, by the Minister of International Trade and Industry, so that the examination results of the accident in Three Mile Island nuclear power station are reflected to the examination for the purpose of improving reactor safety. The examination results of the accident in Three Mile Island power station are being investigated by the Committee on Examination of Reactor Safety, based on the policy shown in ''On the second report of the special committee examining the accident in a nuclear power station in the U.S.'' determined by the Nuclear Safety Commission under date of September 13, 1979. Though the Committee will further clarify the past guideline about the items concerning the criteria, design and operation management, the Committee decided the tentative policy to reflect it to safety examination. Further, a table is attached, in which 52 items to be reflected to the security measures are classified from the viewpoint of necessity to reflect them to the final examination. This table includes 13 items of criteria and examination, 7 items related to design, 10 items related to operation management, 10 antidisaster items, and 12 items related to safety research. (Wakatsuki, Y.)

  14. ''Sleeping reactor'' irradiations: Shutdown reactor determination of short-lived activation products

    International Nuclear Information System (INIS)

    Jerde, E.A.; Glasgow, D.C.

    1998-01-01

    At the High-Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory, the principal irradiation system has a thermal neutron flux (φ) of ∼ 4 x 10 14 n/cm 2 · s, permitting the detection of elements via irradiation of 60 s or less. Irradiations of 6 or 7 s are acceptable for detection of elements with half-lives of as little as 30 min. However, important elements such as Al, Mg, Ti, and V have half-lives of only a few minutes. At HFIR, these can be determined with irradiation times of ∼ 6 s, but the requirement of immediate counting leads to increased exposure to the high activity produced by irradiation in the high flux. In addition, pneumatic system timing uncertainties (about ± 0.5 s) make irradiations of 9 Be(γ,n) 8 Be, the gamma rays principally originating in the spent fuel. Upon reactor SCRAM, the flux drops to ∼ 1 x 10 10 n/cm 2 · s within 1 h. By the time the fuel elements are removed, the flux has dropped to ∼ 6 x 10 8 . Such fluxes are ideal for the determination of short-lived elements such as Al, Ti, Mg, and V. An important feature of the sleeping reactor is a flux that is not constant

  15. Radiological protection of the staff during the decommissioning operations of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Ene, D.C.

    2002-01-01

    Dose rate estimates for periods of 100 days and 6, 10, 25, 100 years after the shut down of the Romanian VVR-S reactor are presented in this paper for some foreseen decommissioning activities which include: i) cutting the water pipe in the pump room and the reactor sealing operations; ii) extracting reactor components; and iii) handling and dismantling the internal structures taken of from the reactor. For the reactor components extracted from the reactor, the considered calculation points were placed in the central plan of the items, on the surface and at distances from the surface which correspond to +0.2m, +1m, +2m, +8m, and +10m. Time dependence of the resulted dose rates are presented and discussed. Qualitative comparison with the measured values from other VVR-S reactors is done. The obtained results assist to develop working procedures that must be observed during the decommissioning activities. (author)

  16. SeaWiFS Third Anniversary Global Biosphere

    Science.gov (United States)

    2002-01-01

    September 18,2000 is the third anniversary of the start of regular SeaWiFS operations of this remarkable planet called Earth. This SeaWiFS image is of the Global Biosphere depicting the ocean's long-term average phytoplankton chlorophyll concentration acquired between September 1997 and August 2000 combined with the SeaWiFS-derived Normalized Difference Vegetation Index (NDVI) over land during July 2000.

  17. G4-STORK: A Geant4-based Monte Carlo reactor kinetics simulation code

    International Nuclear Information System (INIS)

    Russell, Liam; Buijs, Adriaan; Jonkmans, Guy

    2014-01-01

    Highlights: • G4-STORK is a new, time-dependent, Monte Carlo code for reactor physics applications. • G4-STORK was built by adapting and expanding on the Geant4 Monte Carlo toolkit. • G4-STORK was designed to simulate short-term fluctuations in reactor cores. • G4-STORK is well suited for simulating sub- and supercritical assemblies. • G4-STORK was verified through comparisons with DRAGON and MCNP. - Abstract: In this paper we introduce G4-STORK (Geant4 STOchastic Reactor Kinetics), a new, time-dependent, Monte Carlo particle tracking code for reactor physics applications. G4-STORK was built by adapting and expanding on the Geant4 Monte Carlo toolkit. The toolkit provides the fundamental physics models and particle tracking algorithms that track each particle in space and time. It is a framework for further development (e.g. for projects such as G4-STORK). G4-STORK derives reactor physics parameters (e.g. k eff ) from the continuous evolution of a population of neutrons in space and time in the given simulation geometry. In this paper we detail the major additions to the Geant4 toolkit that were necessary to create G4-STORK. These include a renormalization process that maintains a manageable number of neutrons in the simulation even in very sub- or supercritical systems, scoring processes (e.g. recording fission locations, total neutrons produced and lost, etc.) that allow G4-STORK to calculate the reactor physics parameters, and dynamic simulation geometries that can change over the course of simulation to illicit reactor kinetics responses (e.g. fuel temperature reactivity feedback). The additions are verified through simple simulations and code-to-code comparisons with established reactor physics codes such as DRAGON and MCNP. Additionally, G4-STORK was developed to run a single simulation in parallel over many processors using MPI (Message Passing Interface) pipes

  18. SeaWiFS: North Pacific Storm

    Science.gov (United States)

    2002-01-01

    An extratropical storm can be seen swirling over the North Pacific just south of Alaska. This SeaWiFS image was collected yesterday at 23:20 GMT. Credit: Provided by the SeaWiFS Project, NASA/Goddard Space Flight Center, and ORBIMAGE

  19. MANHATTAN PROJECT B REACTOR HANFORD WASHINGTON [HANFORD'S HISTORIC B REACTOR (12-PAGE BOOKLET)

    Energy Technology Data Exchange (ETDEWEB)

    GERBER MS

    2009-04-28

    The Hanford Site began as part of the United States Manhattan Project to research, test and build atomic weapons during World War II. The original 670-square mile Hanford Site, then known as the Hanford Engineer Works, was the last of three top-secret sites constructed in order to produce enriched uranium and plutonium for the world's first nuclear weapons. B Reactor, located about 45 miles northwest of Richland, Washington, is the world's first full-scale nuclear reactor. Not only was B Reactor a first-of-a-kind engineering structure, it was built and fully functional in just 11 months. Eventually, the shoreline of the Columbia River in southeastern Washington State held nine nuclear reactors at the height of Hanford's nuclear defense production during the Cold War era. The B Reactor was shut down in 1968. During the 1980's, the U.S. Department of Energy began removing B Reactor's support facilities. The reactor building, the river pumphouse and the reactor stack are the only facilities that remain. Today, the U.S. Department of Energy (DOE) Richland Operations Office offers escorted public access to B Reactor along a designated tour route. The National Park Service (NPS) is studying preservation and interpretation options for sites associated with the Manhattan Project. A draft is expected in summer 2009. A final report will recommend whether the B Reactor, along with other Manhattan Project facilities, should be preserved, and if so, what roles the DOE, the NPS and community partners will play in preservation and public education. In August 2008, the DOE announced plans to open B Reactor for additional public tours. Potential hazards still exist within the building. However, the approved tour route is safe for visitors and workers. DOE may open additional areas once it can assure public safety by mitigating hazards.

  20. Human factors engineering evaluation of the UTR-10 Reactor

    International Nuclear Information System (INIS)

    Lahti, D.; Nilius, D.; Heithoff, D.; Roche, G.; Sage, S.

    1982-01-01

    This paper is a description of a student design team's review and evaluation of Iowa State University's University Test Reactor (UTR-10). The review was based on how well the control room of the UTR-10 measured up to selected portions of NUREG-0800, chapter 18, Human Factor Engineering/Standard Review Plan Development. The review was conducted by inspecting the reactor and interviewing reactor operators. The control room workspace, instrumentation controls and other equipment were evaluated from a human factors engineering point of view that takes into account both system demands and operator capabilities. Identification, assessment, and suggestion for control room design modifications that correct inadequate or unsuitable items was made

  1. Determination of neutron flux densities in WWR-S reactor core

    International Nuclear Information System (INIS)

    Tomasek, F.

    1989-04-01

    The method is described of determining neutron flux densities and neutron fluences using activation detectors. The basic definitions and relations for determining reaction rates, fluence and neutron flux as well as the characteristics of some reactions and of sitable activation detectors are reported. The flux densities were determined of thermal and fast neutrons and of gamma quanta in the WWR-S reactor core. The data measured in the period 1984-1987 are tabulated. Cross sections for the individual reactions were determined from spectra measurements processed using program SAND-II and cross section library ENDF-B IV. Neutron flux densities were also measured for the WWR-S reactor vertical channels. (E.J.). 10 figs., 8 tabs., 111 refs

  2. Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

    2017-03-01

    This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

  3. Calculations of fuel burn-up and radionuclide inventory in the syrian miniature neutron source reactor using the WIMSD4 code

    International Nuclear Information System (INIS)

    Khattab, K.

    2005-01-01

    Calculations of the fuel burn up and radionuclide inventory in the Miniature Neutron Source Reactor after 10 years (the reactor core expected life) of the reactor operating time are presented in this paper. The WIMSD4 code is used to generate the fuel group constants and the infinite multiplication factor versus the reactor operating time for 10, 20, and 30 kW operating power levels. The amounts of uranium burnt up and plutonium produced in the reactor core, the concentrations and radioactivities of the most important fission product and actinide radionuclides accumulated in the reactor core, and the total radioactivity of the reactor core are calculated using the WIMSD4 code as well

  4. LHCb: Measurement of the relative yields of the decay modes $B_{d,s} \\to D^{\\pm}_{(s)}\\pi^{\\mp}$ and $B_{d,s} \\to D^{\\pm}_{(s)} K^{\\pm}$ and determination of $f_d /f_s$ for 7 TeV $pp$ collisions

    CERN Multimedia

    David, P; Morawski, P; Witek, M; Akiba, K; Serra, N; Storaci, B; Tuning, N; Williams, M; Easo, S; Carson, L; Poluektov, A

    2011-01-01

    A fit to the invariant mass distributions is used to determine the relative abundances of the four decay modes $B_{d,s} \\to D^{\\pm}_{(s)}\\pi^{\\mp}$ and $B_{d,s} \\to D^{\\pm}_{(s)} K^{\\mp}$ for $B_{d,s}$ mesons produced in 7 TeV $pp$ collisions at the LHC. From these, the relative branching fractions of the kaon modes with respect to the pion modes, and the value of $f_d /f_s$, are determined.

  5. Characteristics of particle-bound polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) in atmosphere used in carbon black feeding process at a tire manufacturing plant.

    Science.gov (United States)

    Chuang, Kuen-Yuan; Lai, Chia-Hsiang; Peng, Yen-Ping; Yen, Ting-Yu

    2015-12-01

    Concentrations of polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) were estimated for different particle size distributions in a carbon black feeding process at a tire manufacturing plant on 15 days in March and April of 2014. A total of 75 integrated air samples were collected using a micro-orifice uniform deposition impactor (MOUDI). Particle-bound PCDD/Fs were analyzed using a high-resolution gas chromatograph/high-resolution mass spectrometer (HRGC/HRMS). Concentrations of thoracic particles and total particles produced in the carbon black feeding process of a tire manufacturing plant were measured in ranges of 0.19-2.61 and 0.28-4.22 mg/m(3), respectively. On all sampling days, the three most abundant species of PCDD/Fs were OCDD, 1,2,3,4,6,7,8-HpCDF, and OCDF. The mean concentrations of total PCDD/Fs were 0.74-6.83 pg/m(3) within five particle size ranges. Total I-TEQ in particulate matter (PM)18 and PM2.5-10, respectively. However, the total I-TEQ of thoracic PM contributed approximately 74 % of the total I-TEQ of total PM. The assessment of health risk indicates that exposure to fractions of thoracic PM by inhalation poses a significant cancer risk (>10(-6)).

  6. Evaluation of PCDD/Fs characterization in animal feed and feed additives.

    Science.gov (United States)

    Kim, MeeKyung; Kim, Sooyeon; Yun, Seon Jong; Kwon, Jin-Wook; Son, Seong-Wan

    2007-09-01

    Safety control of feed and feed additives is necessary to have safe food of animal origin. Based on media reports, nine incidents regarding dioxins and/or PCBs contaminations occurred worldwide during the last decade. Korea is a country which imports feed and feed additives. In this study, various kinds of feed and feed additives were analyzed to monitor the contamination level of dioxins. The level of PCDD/Fs in fish oil was the highest with a concentration of 23.33ngkg(-1), which is equivalent to a toxicological concentration of 4.68ngWHO-TEQ/kg. Feed from animals origin such as chicken meal, animal fat, fish meal, fish oil, and shell powder showed relatively higher concentrations of PCDD/Fs. Feed from plants origin, minerals, and additives ranged from non-detects for bit pulp and ethoxyquin to 8.28ngkg(-1) for dl-methionine. From a toxicological point of view, the highest concentration in vitamins was 0.08ngWHO-TEQ/kg among the feed additives. 2,3,4,7,8-PeCDF was the dominant congener in samples of fish oil, fish meal, and shell powder. Animal fat showed that the pattern of PCDD/Fs depends on the sources of contamination. A sample of animal fat showed 1,2,3,4,7,8-HxCDF and the other sample showed 1,2,3,4,7,8-HxCDD as a primary congener. Generally, low levels of PCDDs were detected in feed additives. Patterns of PCDD/Fs in choline chloride were different with that in choline chloride from an incident in Europe in 2000.

  7. U.S. Nuclear Power Reactor Plant Status

    Data.gov (United States)

    Nuclear Regulatory Commission — Demographic data on U.S. commercial nuclear power reactors, including: plant name/unit number, docket number, location, licensee, reactor/containment type, nuclear...

  8. Measurement of the $B^0_s-\\overline{B}^0_s$ oscillation frequency $\\Delta m_s$ in $B^0_s \\to D^-_s (3)\\pi$ decays

    CERN Document Server

    INSPIRE-00258707; Adeva, B.; Adinolfi, M.; Adrover, C.; Affolder, A.; Ajaltouni, Z.; Albrecht, J.; Alessio, F.; Alexander, M.; Alkhazov, G.; Alvarez Cartelle, P.; Alves Jr, A.A.; Amato, S.; Amhis, Y.; Anderson, J.; Appleby, R.B.; Aquines Gutierrez, O.; Archilli, F.; Arrabito, L.; Artamonov, A.; Artuso, M.; Aslanides, E.; Auriemma, G.; Bachmann, S.; Back, J.J.; Bailey, D.S.; Balagura, V.; Baldini, W.; Barlow, R.J.; Barschel, C.; Barsuk, S.; Barter, W.; Bates, A.; Bauer, C.; Bauer, Th.; Bay, A.; Bediaga, I.; Belous, K.; Belyaev, I.; Ben-Haim, E.; Benayoun, M.; Bencivenni, G.; Benson, S.; Benton, J.; Bernet, R.; Bettler, M.O.; van Beuzekom, M.; Bien, A.; Bifani, S.; Bizzeti, A.; Bjornstad, P.M.; Blake, T.; Blanc, F.; Blanks, C.; Blouw, J.; Blusk, S.; Bobrov, A.; Bocci, V.; Bondar, A.; Bondar, N.; Bonivento, W.; Borghi, S.; Borgia, A.; Bowcock, T.J.V.; Bozzi, C.; Brambach, T.; van den Brand, J.; Bressieux, J.; Brett, D.; Brisbane, S.; Britsch, M.; Britton, T.; Brook, N.H.; Brown, H.; Buchler-Germann, A.; Burducea, I.; Bursche, A.; Buytaert, J.; Cadeddu, S.; Caicedo Carvajal, J.M.; Callot, O.; Calvi, M.; Calvo Gomez, M.; Camboni, A.; Campana, P.; Carbone, A.; Carboni, G.; Cardinale, R.; Cardini, A.; Carson, L.; Carvalho Akiba, K.; Casse, G.; Cattaneo, M.; Charles, M.; Charpentier, Ph.; Chiapolini, N.; Ciba, K.; Cid Vidal, X.; Ciezarek, G.; Clarke, P.E.L.; Clemencic, M.; Cliff, H.V.; Closier, J.; Coca, C.; Coco, V.; Cogan, J.; Collins, P.; Constantin, F.; Conti, G.; Contu, A.; Cook, A.; Coombes, M.; Corti, G.; Cowan, G.A.; Currie, R.; D'Almagne, B.; D'Ambrosio, C.; David, P.; De Bonis, I.; De Capua, S.; De Cian, M.; De Lorenzi, F.; de Miranda, J.M.; De Paula, L.; De Simone, P.; Decamp, D.; Deckenhoff, M.; Degaudenzi, H.; Deissenroth, M.; Del Buono, L.; Deplano, C.; Deschamps, O.; Dettori, F.; Dickens, J.; Dijkstra, H.; Diniz Batista, P.; Donleavy, S.; Dosil Suarez, A.; Dossett, D.; Dovbnya, A.; Dupertuis, F.; Dzhelyadin, R.; Eames, C.; Easo, S.; Egede, U.; Egorychev, V.; Eidelman, S.; van Eijk, D.; Eisele, F.; Eisenhardt, S.; Ekelhof, R.; Eklund, L.; Elsasser, Ch.; d'Enterria, D.G.; Esperante Pereira, D.; Esteve, L.; Falabella, A.; Fanchini, E.; Farber, C.; Fardell, G.; Farinelli, C.; Farry, S.; Fave, V.; Fernandez Albor, V.; Ferro-Luzzi, M.; Filippov, S.; Fitzpatrick, C.; Fontana, M.; Fontanelli, F.; Forty, R.; Frank, M.; Frei, C.; Frosini, M.; Furcas, S.; Gallas Torreira, A.; Galli, D.; Gandelman, M.; Gandini, P.; Gao, Y.; Garnier, J-C.; Garofoli, J.; Garra Tico, J.; Garrido, L.; Gaspar, C.; Gauvin, N.; Gersabeck, M.; Gershon, T.; Ghez, Ph.; Gibson, V.; Gligorov, V.V.; Gobel, C.; Golubkov, D.; Golutvin, A.; Gomes, A.; Gordon, H.; Grabalosa Gandara, M.; Graciani Diaz, R.; Granado Cardoso, L.A.; Grauges, E.; Graziani, G.; Grecu, A.; Gregson, S.; Gui, B.; Gushchin, E.; Guz, Yu.; Gys, T.; Haefeli, G.; Haen, C.; Haines, S.C.; Hampson, T.; Hansmann-Menzemer, S.; Harji, R.; Harnew, N.; Harrison, J.; Harrison, P.F.; He, J.; Heijne, V.; Hennessy, K.; Henrard, P.; Hernando Morata, J.A.; van Herwijnen, E.; Hicks, E.; Hofmann, W.; Holubyev, K.; Hopchev, P.; Hulsbergen, W.; Hunt, P.; Huse, T.; Huston, R.S.; Hutchcroft, D.; Hynds, D.; Iakovenko, V.; Ilten, P.; Imong, J.; Jacobsson, R.; Jaeger, A.; Jahjah Hussein, M.; Jans, E.; Jansen, F.; Jaton, P.; Jean-Marie, B.; Jing, F.; John, M.; Johnson, D.; Jones, C.R.; Jost, B.; Kandybei, S.; Karacson, M.; Karbach, T.M.; Keaveney, J.; Kerzel, U.; Ketel, T.; Keune, A.; Khanji, B.; Kim, Y.M.; Knecht, M.; Koblitz, S.; Koppenburg, P.; Kozlinskiy, A.; Kravchuk, L.; Kreplin, K.; Kreps, M.; Krocker, G.; Krokovny, P.; Kruse, F.; Kruzelecki, K.; Kucharczyk, M.; Kukulak, S.; Kumar, R.; Kvaratskheliya, T.; La Thi, V.N.; Lacarrere, D.; Lafferty, G.; Lai, A.; Lambert, D.; Lambert, R.W.; Lanciotti, E.; Lanfranchi, G.; Langenbruch, C.; Latham, T.; Le Gac, R.; van Leerdam, J.; Lees, J.P.; Lefevre, R.; Leflat, A.; Lefrancois, J.; Leroy, O.; Lesiak, T.; Li, L.; Li Gioi, L.; Lieng, M.; Liles, M.; Lindner, R.; Linn, C.; Liu, B.; Liu, G.; Lopes, J.H.; Lopez Asamar, E.; Lopez-March, N.; Luisier, J.; Machefert, F.; Machikhiliyan, I.V.; Maciuc, F.; Maev, O.; Magnin, J.; Malde, S.; Mamunur, R.M.D.; Manca, G.; Mancinelli, G.; Mangiafave, N.; Marconi, U.; Marki, R.; Marks, J.; Martellotti, G.; Martens, A.; Martin, L.; Martin Sanchez, A.; Martinez Santos, D.; Massafferri, A.; Mathe, Z.; Matteuzzi, C.; Matveev, M.; Maurice, E.; Maynard, B.; Mazurov, A.; McGregor, G.; McNulty, R.; Mclean, C.; Meissner, M.; Merk, M.; Merkel, J.; Messi, R.; Miglioranzi, S.; Milanes, D.A.; Minard, M.N.; Monteil, S.; Moran, D.; Morawski, P.; Mountain, R.; Mous, I.; Muheim, F.; Muller, K.; Muresan, R.; Muryn, B.; Musy, M.; Mylroie-Smith, J.; Naik, P.; Nakada, T.; Nandakumar, R.; Nardulli, J.; Nasteva, I.; Nedos, M.; Needham, M.; Neufeld, N.; Nguyen-Mau, C.; Nicol, M.; Nies, S.; Niess, V.; Nikitin, N.; Oblakowska-Mucha, A.; Obraztsov, V.; Oggero, S.; Ogilvy, S.; Okhrimenko, O.; Oldeman, R.; Orlandea, M.; Otalora Goicochea, J.M.; Owen, P.; Pal, B.; Palacios, J.; Palutan, M.; Panman, J.; Papanestis, A.; Pappagallo, M.; Parkes, C.; Parkinson, C.J.; Passaleva, G.; Patel, G.D.; Patel, M.; Paterson, S.K.; Patrick, G.N.; Patrignani, C.; Pavel-Nicorescu, C.; Pazos Alvarez, A.; Pellegrino, A.; Penso, G.; Pepe Altarelli, M.; Perazzini, S.; Perego, D.L.; Perez Trigo, E.; Perez-Calero Yzquierdo, A.; Perret, P.; Perrin-Terrin, M.; Pessina, G.; Petrella, A.; Petrolini, A.; Pie Valls, B.; Pietrzyk, B.; Pilar, T.; Pinci, D.; Plackett, R.; Playfer, S.; Plo Casasus, M.; Polok, G.; Poluektov, A.; Polycarpo, E.; Popov, D.; Popovici, B.; Potterat, C.; Powell, A.; du Pree, T.; Prisciandaro, J.; Pugatch, V.; Puig Navarro, A.; Qian, W.; Rademacker, J.H.; Rakotomiaramanana, B.; Rangel, M.S.; Raniuk, I.; Raven, G.; Redford, S.; Reid, M.M.; dos Reis, A.C.; Ricciardi, S.; Rinnert, K.; Roa Romero, D.A.; Robbe, P.; Rodrigues, E.; Rodrigues, F.; Rodriguez Perez, P.; Rogers, G.J.; Roiser, S.; Romanovsky, V.; Rouvinet, J.; Ruf, T.; Ruiz, H.; Sabatino, G.; Saborido Silva, J.J.; Sagidova, N.; Sail, P.; Saitta, B.; Salzmann, C.; Sannino, M.; Santacesaria, R.; Santinelli, R.; Santovetti, E.; Sapunov, M.; Sarti, A.; Satriano, C.; Satta, A.; Savrie, M.; Savrina, D.; Schaack, P.; Schiller, M.; Schleich, S.; Schmelling, M.; Schmidt, B.; Schneider, O.; Schopper, A.; Schune, M.H.; Schwemmer, R.; Sciubba, A.; Seco, M.; Semennikov, A.; Senderowska, K.; Sepp, I.; Serra, N.; Serrano, J.; Seyfert, P.; Shao, B.; Shapkin, M.; Shapoval, I.; Shatalov, P.; Shcheglov, Y.; Shears, T.; Shekhtman, L.; Shevchenko, O.; Shevchenko, V.; Shires, A.; Coutinho, R.Silva; Skottowe, H.P.; Skwarnicki, T.; Smith, A.C.; Smith, N.A.; Sobczak, K.; Soler, F.J.P.; Solomin, A.; Soomro, F.; Souza De Paula, B.; Spaan, B.; Sparkes, A.; Spradlin, P.; Stagni, F.; Stahl, S.; Steinkamp, O.; Stoica, S.; Stone, S.; Storaci, B.; Straticiuc, M.; Straumann, U.; Styles, N.; Subbiah, V.K.; Swientek, S.; Szczekowski, M.; Szczypka, P.; Szumlak, T.; T'Jampens, S.; Teodorescu, E.; Teubert, F.; Thomas, C.; Thomas, E.; van Tilburg, J.; Tisserand, V.; Tobin, M.; Topp-Joergensen, S.; Tran, M.T.; Tsaregorodtsev, A.; Tuning, N.; Ukleja, A.; Urquijo, P.; Uwer, U.; Vagnoni, V.; Valenti, G.; Vazquez Gomez, R.; Vazquez Regueiro, P.; Vecchi, S.; Velthuis, J.J.; Veltri, M.; Vervink, K.; Viaud, B.; Videau, I.; Vilasis-Cardona, X.; Visniakov, J.; Vollhardt, A.; Voong, D.; Vorobyev, A.; Voss, H.; Wacker, K.; Wandernoth, S.; Wang, J.; Ward, D.R.; Webber, A.D.; Websdale, D.; Whitehead, M.; Wiedner, D.; Wiggers, L.; Wilkinson, G.; Williams, M.P.; Williams, M.; Wilson, F.F.; Wishahi, J.; Witek, M.; Witzeling, W.; Wotton, S.A.; Wyllie, K.; Xie, Y.; Xing, F.; Yang, Z.; Young, R.; Yushchenko, O.; Zavertyaev, M.; Zhang, L.; Zhang, W.C.; Zhang, Y.; Zhelezov, A.; Zhong, L.; Zverev, E.; Zvyagin, A.

    2012-01-01

    The $B^0_s$-$\\overline{B}^0_s$ oscillation frequency $\\Delta m_s$ is measured with 36 pb$^{-1}$ of data collected in $pp$ collisions at $\\sqrt{s}$ = 7 TeV by the LHCb experiment at the Large Hadron Collider. A total of 1381 $B^0_s \\rightarrow D_s^- \\pi^+$ and $B^0_s \\rightarrow D_s^- \\pi^+\\pi^-\\pi^+$ signal decays are reconstructed, with average decay time resolutions of 44~fs and 36~fs, respectively. An oscillation signal with a statistical significance of 4.6\\,$\\sigma$ is observed. The measured oscillation frequency is $\\Delta m_s$ = 17.63 $\\pm$ 0.11 (stat) $\\pm$ 0.02 (syst)~ps$^{-1}$.

  9. (4bS,8aS-1-Isopropyl-4b,8,8-trimethyl-4b,5,6,7,8,8a,9,10-octahydrophenanthren-2-yl acetate

    Directory of Open Access Journals (Sweden)

    Radouane Oubabi

    2014-03-01

    Full Text Available The hemisynthesis of the title compound, C22H32O2, was carried out through direct acetylation reaction of the naturally occurring diterpene totarol [systematic name: (4bS,8aS-4b,8,8-trimethyl-1-propan-2-yl-5,6,7,8a,9,10-hexahydrophenanthren-2-ol]. The molecule is built up from three fused six membered rings, one saturated and two unsaturated. The central unsaturated ring has a half-chair conformation, whereas the other unsaturated ring displays a chair conformation. The absolute configuration is deduced from the chemical pathway. The value of the Hooft parameter [−0.10 (6] allowed this absolute configuration to be confirmed.

  10. Current status of feasibility studies on commercialized fuel cycle system for Fast Breeder Reactor

    International Nuclear Information System (INIS)

    Ojima, Hisao; Nagaoki, Yoshihiro

    2000-01-01

    A 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' is underway at the Japan Nuclear Cycle Development Institute (JNC). The study will select the promising concepts with their R and D tasks in order to commercialize the fast breeder reactor (FBR) cycle system. The feasibility studies (F/S) have to present surveyed and screened various relevant technologies, and defined the design requirement of the commercialized fuel cycle system for FBR. The promising technical options are being evaluated and conceptual designs are being examined. At the end of JFY2000, several candidate concepts of the commercialized FBR cycle system will be proposed. (author)

  11. Dosimetry aspects of the new Canadian MAPLE-X10 reactor

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Wilkin, G.B.

    1994-01-01

    Atomic Energy of Canada Limited is building the 10-MW t MAPLE-X10 reactor facility as a dedicated producer of medical and industrial radioisotopes. Dosimetry aspects of the MAPLE-X10 nuclear design include the calculated thermal and fast neutron flux distributions throughout the reactor assembly and the rate of heat generation in reactor materials and components. Examples of the resolution of design issues are also presented, such as the use of fission counters and ion chambers to provide diverse methods of detecting neutron flux levels and the use of the difference between photon and neutron signals to guard against the effects of downgrading of the heavy-water reflector. Computer codes employed in the calculations include MCNP, ONEDANT, WIMS-AECL, and 3DDT

  12. Summary of IEA-R1 research a reactor licensing related to its power increase from 2 to 10 MW

    International Nuclear Information System (INIS)

    1989-04-01

    This work is a summary of IEA-R1 research reactor licensing related to its power increase from 2 to 10 MW. It reports also safety requirements, fuel elements, and reactor control modifications inherent to power increase. (A.C.A.S.)

  13. Radiobiological aspects of application of BR-10 reactor neutrons for radiotherapy of malignant tumours

    International Nuclear Information System (INIS)

    Ul'yanenko, S.E.; Kuznetsova, M.N.; Obaturov, G.M.

    1992-01-01

    Possibilities to increase the factor of therapeutical gain (FTG) by optimizing irradiation conditions and using hyperglycemia were studied. It is shown that relative biological effectiveness (RBE) of neutrons in fission spectrum of the BR-10 reactor in the dose range from 10 Gy used one time is 4.2-4.5 for tumours and 4.0-4.2 for normal skin; in case of fractionated irradiation by neutrons (1-8 fractions in the range of 6-10 Gy) RBE increases practically 1.5 fold; employment of neutron beam filters and hyperglycemia in conditions of combined gamma-neutron procedures of irradiation permits a considerable increase in FTG. 3 refs

  14. Corneal Biomechanical Properties after FS-LASIK with Residual Bed Thickness Less Than 50% of the Original Corneal Thickness

    Directory of Open Access Journals (Sweden)

    Haixia Zhang

    2018-01-01

    Full Text Available Background. The changes in corneal biomechanical properties after LASIK remain an unknown but important topic for surgical design and prognostic evaluation. This study aims to observe the postoperative corneal biomechanical properties one month after LASIK with amount of corneal cutting (ACC greater than 50% of the central corneal thickness (CCT. Methods. FS-LASIK was performed in 10 left rabbit eyes with ACC being 60% (L60 and 65% (L65 of the CCT, while the right eyes (R were the control. After 4 weeks, rabbits were executed and corneal strip samples were prepared for uniaxial tensile tests. Results. At the same strain, the stresses of L65 and L60 were larger than those of R. The elastic moduli of L60 and L65 were larger than those of R when the stress was 0.02 MPa, while they began to be less than those of R when stress exceeds the low-stress region. After 10s relaxation, the stress of specimens L65, L60, and R increased in turn. Conclusion. The elastic moduli of the cornea after FS-LASIK with ACC greater than 50% of the CCT do not become less under normal rabbit IOP. The limit stress grows with the rise of ACC when relaxation becomes stable.

  15. Waste generated by the future decommissioning of the Magurele VVR-S Research Reactor

    International Nuclear Information System (INIS)

    Dragolici, F.; Turcanu, C.N.; Dragolici, A.C.

    2001-01-01

    Nuclear Research Reactor WWR-S from the National Institute of Research and Development for Physics and Nuclear Engineering 'Horia Hulubei', Bucharest-Magurele, was commissioned in July 1957 and it was shut down in December 1997. At the moment the reactor is in conservation state. During its operation this reactor worked at an average power of 2MW, almost 3216 h/year, producing a total thermal power of 230 x 10 3 MWh. No major modifications or improvements were made during the 40 years of operation to the essential parts of the reactor, respective to the primary cooling system, reactor vessel, active core and electronic devices. So, all components of the measure, control and protection systems are old, generally at the technical level of the 1950s, therefore a reason why in December 1997 the operation was ceased. At present, the reactor can be considered, by IAEA definition in the first stage (reactor shut down, but the vital functions are maintained and monitored). The survey is related to the second stage - restrictive use of the area. To develop a real decommissioning project, it was first necessary to evaluate the volume and the characteristics of the radioactive waste which will be generated. Radioactive waste generated during the decommissioning of Magurele WR-S research reactor may be classified as: Activated wastes (internal structures, horizontal channels and thermal column, biological shield); Contaminated wastes (primary circuit non-activated components, hot cells, some technological rooms as main hall, pumps room, radioactive material transfer areas, ventilation building and stack); Possibly contaminated materials from any area of reactor building and ventilation building. After 40 years of nuclear research activities, all such areas are suspected of contamination. The volume of wastes that will result from WWR-S Research Reactor decommissioning is summarized

  16. EST Table: FS920530 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920530 E_FL_fufe_50K23_F_0 11/12/09 GO hit GO:0047800(cysteamine dioxygenase acti...090992|ref|XP_974899.1| PREDICTED: similar to 2-aminoethanethiol (cysteamine) dioxygenase [Tribolium castaneum] FS920530 fufe ...

  17. PCDD/Fs and dioxin-like PCBs in the Tone River, Japan

    Energy Technology Data Exchange (ETDEWEB)

    Watanabe, Eiki; Heesoo, Eun; Koji, Baba; Tomohito, Arao; Shozo, Endo [National Institute for Agro-Environmental Sciences, Tsukuba (Japan); Tadashi, Sekino [Environmental Research Center, Tsukuba (Japan)

    2004-09-15

    Environmental pollution by PCDD/Fs has arisen exclusively from human activities, and for example, they are inadvertently produced from various combustion sources and manufacturing processes, such as municipal solid waste incineration steel production processes and chemical production processes. In Japan, it is well known that the environmental pollution has close relation to agricultural operation, that is, some PCDD/Fs are contained as impurities in a kind of pesticide. The Tone River is the largest basin area (about 16,900 km{sup 2}) in Japan, and after the Shinano River, is the second longest river (about 322 km). The river has many tributaries (about 800 rivers), and the rivers taking the Kokai River, the Kinu River, the Edo River, and the Watarase River as objects of the present study are also representative tributaries. Since the Tone River basin corresponding to about 4.5% of the total area of Japan leads about twelve million population corresponding to about 10% of the gross population in Japan, it plays an important part in a supply of water for human activities. Not only some residential zones near Tokyo and industrial zones but also representative agricultural zones in Japan expand in the basin expands, and especially the lower basin leads a leading granary. The objective of our effort is to investigate the levels of PCDD/Fs and PCBs in surface sediment and water samples from the Tone River and some related tributaries, and to assess their distribution and origin using congener-specific characterization approach.

  18. Design and safety considerations for the 10 MW(t) multipurpose TRIGA reactor in Thailand

    International Nuclear Information System (INIS)

    Razvi, J.; Bolin, J.M.; Saurwein, J.J.; Whittemore, W.L.; Proongmuang, S.

    1999-01-01

    General Atomics (GA) is constructing the Ongkharak Nuclear Research Center (ONRC) near Bangkok, Thailand for the Office of Atomic Energy for Peace. The ONRC complex includes the following: A multipurpose 10 MW(t) research reactor; An Isotope Production Facility; Centralized Radioactive Waste Processing and Storage Facilities. The Center is being built 60-km northeast of Bangkok, with a 10 MW(t) TRIGA type research reactor as the centerpiece. Facilities are included for neutron transmutation doping of silicon, neutron capture therapy neutron beam research and for production of a variety of radioisotopes. The facility will also be utilized for applied research and technology development as well as training in reactor operations, conduct of experiments and in reactor physics. The multipurpose, pool-type reactor will be fueled with high-density (45 wt%), low-enriched (19.7 wt%) uranium-erbium-zirconium-hydride (UErZrH) fuel rods, cooled and moderated by light water, and reflected by beryllium and heavy water. The general arrangement of the reactor and auxiliary pool structure allows irradiated targets to be transferred entirely under water from their irradiation locations to the hot cell, then pneumatically transferred to the adjacent Isotope Production Facility for processing. The core configuration includes 4 x 4 array standard TRIGA fuel clusters, modified clusters to serve as fast-neutron irradiation facilities, control rods and an in-core Ir-192 production facility. The active core is reflected on two sides by beryllium and on the other two sides by D 2 O. Additional irradiation facilities are also located in the beryllium reflector blocks and the D 2 O reflector blanket. The fuel provides the fundamental safety feature of the ONRC reactor, and as a result of all the well established accident-mitigating characteristics of the UErZrH fuel itself (large prompt negative temperature coefficient of reactivity, fission product retention and chemical stability), a

  19. EST Table: FS737333 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS737333 E_FL_bmmt_08I09_R_0 10/09/28 68 %/182 aa ref|NP_059479.1| ATP synthase F0 ...subunit 6 [Bombyx mori] gb|AAF73768.1|AF149768_12 ATPase 6 [Bombyx mori] gb|AAK85722.1| ATPase subunit 6 [Bo....1| ATP synthase F0 subunit 6 [Bombyx mori] gb|ADE18460.1| ATP synthase F0 subunit 6 [Bombyx mori] gb|ADE18473

  20. Advances in U.S. reactor physics standards

    International Nuclear Information System (INIS)

    Cokinos, Dimitrios

    2008-01-01

    The standards for Reactor Design, widely used in the nuclear industry, provide guidance and criteria for performing and validating a wide range of nuclear reactor calculations and measurements. Advances, over the past decades in reactor technology, nuclear data and infrastructure in the data handling field, led to major improvements in the development and application of reactor physics standards. A wide variety of reactor physics methods and techniques are being used by reactor physicists for the design and analysis of modern reactors. ANSI (American National Standards Institute) reactor physics standards, covering such areas as nuclear data, reactor design, startup testing, decay heat and fast neutron fluence in the pressure vessel, are summarized and discussed. These standards are regularly undergoing review to respond to an evolving nuclear technology and are being successfully used in the U.S and abroad contributing to improvements in reactor design, safe operation and quality assurance. An overview of the overall program of reactor physics standards is presented. New standards currently under development are also discussed. (authors)

  1. 48 CFR 15.403-4 - Requiring certified cost or pricing data (10 U.S.C. 2306a and 41 U.S.C. 254b).

    Science.gov (United States)

    2010-10-01

    ... or pricing data (10 U.S.C. 2306a and 41 U.S.C. 254b). 15.403-4 Section 15.403-4 Federal Acquisition Regulations System FEDERAL ACQUISITION REGULATION CONTRACTING METHODS AND CONTRACT TYPES CONTRACTING BY NEGOTIATION Contract Pricing 15.403-4 Requiring certified cost or pricing data (10 U.S.C. 2306a and 41 U.S.C...

  2. Differentiation between grade 3 and grade 4 articular cartilage defects of the knee: Fat-suppressed proton density-weighted versus fat-suppressed three-dimensional gradient-echo MRI

    Energy Technology Data Exchange (ETDEWEB)

    Lee, So Yeon; Jee, Won-Hee; Kim, Sun Ki (Dept. of Radiology, Seoul St Mary' s Hospital, Catholic Univ. of Korea, Seoul (Korea)), e-mail: whjee@catholic.ac.kr; Koh, In-Jun (Dept. of Joint Reconstruction Center, Seoul National Univ. Bundang Hospital, Seoul (Korea)); Kim, Jung-Man (Dept. of Orthopedic Surgery, Seoul St Mary' s Hospital, Catholic Univ. of Korea, Seoul (Korea))

    2010-05-15

    Background: Fat-suppressed (FS) proton density (PD)-weighted magnetic resonance imaging (MRI) and FS three-dimensional (3D) gradient-echo imaging such as spoiled gradient-recalled (SPGR) sequence have been established as accurate methods for detecting articular cartilage defects. Purpose: To retrospectively compare the diagnostic efficacy between FS PD-weighted and FS 3D gradient-echo MRI for differentiating between grade 3 and grade 4 cartilage defects of the knee with arthroscopy as the standard of reference. Material and Methods: Twenty-one patients who had grade 3 or 4 cartilage defects in medial femoral condyle at arthroscopy and knee MRI were included in this study: grade 3, >50% cartilage defects; grade 4, full thickness cartilage defects exposed to the bone. Sagittal FS PD-weighted MR images and FS 3D gradient-echo images with 1.5 T MR images were independently graded for the cartilage abnormalities of medial femoral condyle by two musculoskeletal radiologists. Statistical analysis was performed by Fisher's exact test. Inter-observer agreement in grading of cartilage was assessed using ? coefficients. Results: Arthroscopy revealed grade 3 defects in 17 patients and grade 4 defects in 4 patients in medial femoral condyles. For FS 3D gradient-echo images grade 3 defects were graded as grade 3 (n=15) and grade 4 (n=2), and all grade 4 defects (n=4) were correctly graded. However, for FS PD-weighted MR images all grade 3 defects were misinterpreted as grade 1 (n=1) and grade 4 (n=16), whereas all grade 4 defects (n=4) were correctly graded. FS 3D gradient-echo MRI could differentiate grade 3 from grade 4 defects (P=0.003), whereas FS PD-weighted imaging could not (P=1.0). Inter-observer agreement was substantial (?=0.70) for grading of cartilage using FS PD-weighted imaging, whereas it was moderate (?=0.46) using FS 3D gradient-echo imaging. Conclusion: FS 3D gradient-echo MRI is more helpful for differentiating between grade 3 and grade 4 cartilage

  3. MAPLE-X10 reactor safety assessment

    International Nuclear Information System (INIS)

    Cotnam, K.D.; Lounsbury, R.I.; Gillespie, G.E.

    1990-01-01

    This paper reports on the safety assessment of the 10 MW MAPLE-X10 reactor which has involved a substantial component of PSA analysis to supplement deterministic analysis. Initiating events are identified through the use of a master logic diagram. The events are then examined through event sequence diagrams, at the concept design stage, followed by a set of reliability analyses that are coordinated with the event sequence diagrams. Improvements identified through the reliability analyses are incorporated into the design to ensure that safety objectives are attained

  4. Evaluation of PCDD/Fs emissions during ceramic production: a laboratory study.

    Science.gov (United States)

    Lu, Mang; Luo, Yi-Jing; Zhang, Zhong-Zhi; Xiao, Meng; Zhang, Min

    2012-08-30

    Because of the ubiquity of polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) in kaolinitic clays, the ceramic industry is considered to be a potential source of PCDD/Fs. However, studies on the emission of PCDD/Fs from ceramic production are still very scarce. In this study, PCDD/Fs emissions during ceramic production were investigated in an electric laboratory batch kiln. The results showed that the PCDD/Fs were completely removed from the ceramic pieces after 30 min of firing at the peak temperature of 1200°C. Nevertheless, on the mass and international toxic equivalent basis, 27.5% and 46.2% of the total PCDD/Fs amount in the raw clay were released into the atmosphere during firing, respectively. These PCDD/Fs were emitted into the air before the temperature was elevated to a level high enough for their destruction. Dechlorination reactions generated a broad distribution within the PCDD/Fs congeners including a variety of non-2,3,7,8-substituted ones. The emission of PCDD/Fs was decreased to 16.3 wt.% of the total PCDD/Fs amount in the raw clay, when the initial kiln temperature was enhanced to 600°C. The emission of PCDD/Fs could be reduced significantly in the presence of a glaze coating on the ceramic test piece. These results indicated that ceramic production is an un-neglectable source of PCDD/Fs in the environment. Copyright © 2012 Elsevier B.V. All rights reserved.

  5. Multi-Robot Remote Interaction with FS-MAS

    Directory of Open Access Journals (Sweden)

    Yunliang Jiang

    2013-02-01

    Full Text Available The need to reduce bandwidth, improve productivity, autonomy and the scalability in multi-robot teleoperation has been recognized for a long time. In this article we propose a novel finite state machine mobile agent based on the network interaction service model, namely FS-MAS. This model consists of three finite state machines, namely the Finite State Mobile Agent (FS-Agent, which is the basic service module. The Service Content Finite State Machine (Content-FS, using the XML language to define workflow, to describe service content and service computation process. The Mobile Agent computation model Finite State Machine (MACM-FS, used to describe the service implementation. Finally, we apply this service model to the multi-robot system, the initial realization completing complex tasks in the form of multi-robot scheduling. This demonstrates that the robot has greatly improved intelligence, and provides a wide solution space for critical issues such as task division, rational and efficient use of resource and multi-robot collaboration.

  6. Utilization of RP-10 reactor for neutron therapy

    International Nuclear Information System (INIS)

    Paucar, R.; Nieto, M.; Parreno, F.; Vela, M.; Pozo, Z.

    1997-01-01

    In the Nuclear Energy Peruvian Institute, IPEN, a research area has established of Neutron Radiotherapy, know as NCT. This research joins the physics of particles (Neutrons and photons) and Medical Physics, and this one is an applied investigation where in considering the construction of a treatment hall in Huarangal (Peru) Reactor's irradiation facility, it can treat patients with brain tumors. In Neutron Therapy (NCT), it tries to use neutrons to destroy tumor cells where other therapeutic techniques are not effective. This process consist on to incise a neutrons beam of adequate characteristics over the tumor area of the patient. The neutrons used are of thermal energy and therefore irradiations are developed in experimental reactors. For this one, it is used horizontal channels prepared suitably. Before the irradiation, it is injected to the patient a substance which is absorbed by tumoral tissue. The substance components will be B-10, nuclide with an absorption cross section high to thermal neutrons (3837 b). The B-10 irradiate with thermal neutrons produce alpha particles of short reach (10 μm. on soft tissue) and with LET values (lineal energy transference) very high. The result is a cell preferential destruction which have absorbed the substance and it's next neighbors, like the cell size is 10 μm. This process as know as Boron Neutron Capture Therapy (BNCT). This work describes Peruvian RP-10 reactor and recently efforts to assess the design and feasibility of the medical neutron irradiation facility for NCT. (author). 22 refs., 6 tabs

  7. Parametric generation of high-energy 14.5-fs light pulses at 1.5 mum.

    Science.gov (United States)

    Nisoli, M; Stagira, S; De Silvestri, S; Svelto, O; Valiulis, G; Varanavicius, A

    1998-04-15

    High-energy light pulses that are tunable from 1.1 to 2.6 mum, with a duration as short as 14.5 fs were generated in a type II phase-matching beta-BaB(2)O(4) traveling-wave parametric converter pumped by 18-fs pulses obtained from a Ti:sapphire laser with chirped-pulse amplification, followed by a hollow-fiber compressor.

  8. Water absorption and biodegradation kinetics of highly filled EOC-FS biocomposites

    Science.gov (United States)

    Zykova, A. K.; Pantyukhov, P. V.; Platov, Yu. T.; Bobojonova, G. A.; Ramos, C. Chaverri; Popov, A. A.

    2017-12-01

    The paper analyzes the water absorption and biodegradation kinetics in highly filled biocomposites based on ethylene-octene copolymer (EOC) and oil flax straw (FS). It is shown that adding the filler to EOC increases the water absorption from 0 to 22%. The tendency can be explained both by the low interfacial adhesion of EOC to FS and by the hydrophilic nature of the filler. According to biodegradation tests (10 months), the mass of pure EOC remains unchanged, suggesting that it fails to biodegrade in the environment. Increasing the filler content increases the weight loss of the composites and the degree of microbiological contamination (fungi filaments, bacteria) as evidenced by optical microscopy.

  9. Development and applications of reactor noise analysis at Ontario Hydro`s CANDU reactors

    Energy Technology Data Exchange (ETDEWEB)

    Gloeckler, O [Ontario Hydro, Toronto, ON (Canada); Tulett, M V [Ontario Hydro, Pickering, ON (Canada). Pickering Generating Station

    1996-12-31

    In 1992 a program was initiated to establish reactor noise analysis as a practical tool for plant performance monitoring and system diagnostics in Ontario Hydro`s CANDU reactors. Since then, various CANDU-specific noise analysis applications have been developed and validated. The noise-based statistical techniques are being successfully applied as powerful troubleshooting and diagnostic tools to a wide variety of actual operational I and C problems. The dynamic characteristics of critical plant components, instrumentation and processes are monitored on a regular basis. Recent applications of noise analysis include (1) validating the dynamics of in-core flux detectors (ICFDS) and ion chambers, (2) estimating the prompt fraction ICFDs in noise measurements at full power and in power rundown tests, (3) identifying the cause of excessive signal fluctuations in certain flux detectors, (4) validating the dynamic coupling between liquid zone control signals, (5) detecting and monitoring mechanical vibrations of detector tubes induced by moderator flow, (6) estimating the dynamics and response time of RTD (Resistance Temperature Detector) temperature signals, (7) isolating the cause of RTD signal anomalies, (8) investigating the source of abnormal flow signal behaviour, (9) estimating the overall response time of flow and pressure signals, (10) detecting coolant boiling in fully instrumented fuel channels, (11) monitoring moderator circulation via temperature noise, and (12) predicting the performance of shut-off rods. Some of these applications are performed on an as-needed basis. The noise analysis program, in the Pickering-B station alone, has saved Ontario Hydro millions of dollars during its first three years. The results of the noise analysis program have been also reviewed by the regulator (Atomic Energy Control Board of Canada) with favorable results. The AECB have expressed interest in Ontario Hydro further exploiting the use of noise analysis technology. (author

  10. Thermophysical properties of Na2Th (MoO4)3 (s) and Na4Th (MoO4)4 (s)

    International Nuclear Information System (INIS)

    Dash, Smruti; Rakshit, S.K.; Singh, Ziley; Keskar, Meera; Dahale, N.D.

    2009-01-01

    The heat capacity of Na 2 Th (MoO 4 ) 3 (s) and Na 4 Th (MoO 4 ) 4 (s) have been measured by differential scanning calorimeter in the temperature range 318 to 845 K. The corresponding values are: C p,m (Na 2 Th (MoO 4 ) 3 ,s,T) (JK-1 mol-1) 368.710+ 1.0 10-1 (T/K) - 4950267 (K/T)2 (318 ≤ T (K) ≤ 845). C p,m (Na 4 Th (MoO 4 ) 4 ,s,T) (JK-1 mol-1) = 638.761+ 5.12 10-3 (T/K) - 12691691 (K/T)-2 (318 ≤ T (K) ≤ 845). Experimental heat capacity values for Na 2 Th (MoO 4 ) 3 (s) match reasonably well with that of additive oxide values. But C p,m (T) values of Na 4 Th (MoO 4 ) 4 (s) deviates substantially from the additive oxide values above 700 K. The uncertainty of the measurements reported in this study is calculated to be within 1 to 3 % . (author)

  11. Heat capacity measurement of CeNbO4(s)

    International Nuclear Information System (INIS)

    Bhojane, S.M.; Kulkarni, Jayanthi; Kulkarni, S.G.

    2012-01-01

    Molar heat capacity of CeNbO 4 (s) was determined using differential scanning calorimeter in the temperature range of 550 to 900 K. The molar heat capacity values were least squares analysed and the dependence of molar heat capacity with temperature for CeNbO 4 (s) can be given as, J K -1 mol -1 = 94.7320 + 0.0852T-1.6073 x 10 6 T -2 (550≤T(K)≤900) Cerium is commonly used as an inactive analogue to plutonium; also it is an important fission product with moderate yield. Various Nb alloys are used as cladding material in nuclear industry. Hosts of thermodynamic data are needed to understand the various phenomena that occur in a nuclear reactor. In the present study, the molar heat capacity of CeNbO 4 (s) has been determined using high temperature differential scanning calorimeter in temperature range 550 to 900 K. This is one of the important compounds in the ternary system of Ce-Nb-O

  12. Observation of excited state charge transfer with fs/ps-CARS

    Energy Technology Data Exchange (ETDEWEB)

    Blom, Alex Jason [Iowa State Univ., Ames, IA (United States)

    2009-01-01

    Excited state charge transfer processes are studied using the fs/ps-CARS probe technique. This probe allows for multiplexed detection of Raman active vibrational modes. Systems studied include Michler's Ketone, Coumarin 120, 4-dimethylamino-4'-nitrostilbene, and several others. The vibrational spectrum of the para di-substituted benzophenone Michler's Ketone in the first excited singlet state is studied for the first time. It is found that there are several vibrational modes indicative of structural changes of the excited molecule. A combined experimental and theoretical approach is used to study the simplest 7-amino-4-methylcoumarin, Coumarin 120. Vibrations observed in FTIR and spontaneous Raman spectra are assigned using density functional calculations and a continuum solvation model is used to predict how observed modes are affected upon inclusion of a solvent. The low frequency modes of the excited state charge transfer species 4-dimethylamino-4{prime}-nitrostilbene are studied in acetonitrile. Results are compared to previous work on this molecule in the fingerprint region. Finally, several partially completed projects and their implications are discussed. These include the two photon absorption of Coumarin 120, nanoconfinement in cyclodextrin cavities and sensitization of titania nanoparticles.

  13. Active Noise Control Using Modified FsLMS and Hybrid PSOFF Algorithm

    Directory of Open Access Journals (Sweden)

    Ranjan Walia

    2018-04-01

    Full Text Available Active noise control is an efficient technique for noise cancellation of the system, which has been defined in this paper with the aid of Modified Filtered-s Least Mean Square (MFsLMS algorithm. The Hybrid Particle Swarm Optimization and Firefly (HPSOFF algorithm are used to identify the stability factor of the MFsLMS algorithm. The computational difficulty of the modified algorithm is reduced when compared with the original Filtered-s Least Mean Square (FsLMS algorithm. The noise sources are removed from the signal and it is compared with the existing FsLMS algorithm. The performance of the system is established with the normalized mean square error for two different types of noises. The proposed method has also been compared with the existing algorithms for the same purposes.

  14. JENDL-4.0 benchmarking for fission reactor applications

    International Nuclear Information System (INIS)

    Chiba, Go; Okumura, Keisuke; Sugino, Kazuteru; Nagaya, Yasunobu; Yokoyama, Kenji; Kugo, Teruhiko; Ishikawa, Makoto; Okajima, Shigeaki

    2011-01-01

    Benchmark testing for the newly developed Japanese evaluated nuclear data library JENDL-4.0 is carried out by using a huge amount of integral data. Benchmark calculations are performed with a continuous-energy Monte Carlo code and with the deterministic procedure, which has been developed for fast reactor analyses in Japan. Through the present benchmark testing using a wide range of benchmark data, significant improvement in the performance of JENDL-4.0 for fission reactor applications is clearly demonstrated in comparison with the former library JENDL-3.3. Much more accurate and reliable prediction for neutronic parameters for both thermal and fast reactors becomes possible by using the library JENDL-4.0. (author)

  15. Anaerobic Digestion of Sugarcane Vinasse Through a Methanogenic UASB Reactor Followed by a Packed Bed Reactor.

    Science.gov (United States)

    Cabrera-Díaz, A; Pereda-Reyes, I; Oliva-Merencio, D; Lebrero, R; Zaiat, M

    2017-12-01

    The anaerobic treatment of raw vinasse in a combined system consisting in two methanogenic reactors, up-flow anaerobic sludge blanket (UASB) + anaerobic packed bed reactors (APBR), was evaluated. The organic loading rate (OLR) was varied, and the best condition for the combined system was 12.5 kg COD m -3 day -1 with averages of 0.289 m 3 CH 4  kg COD r -1 for the UASB reactor and 4.4 kg COD m -3 day -1 with 0.207 m 3 CH 4  kg COD r -1 for APBR. The OLR played a major role in the emission of H 2 S conducting to relatively stable quality of biogas emitted from the APBR, with H 2 S concentrations <10 mg L -1 . The importance of the sulphate to COD ratio was demonstrated as a result of the low biogas quality recorded at the lowest ratio. It was possible to develop a proper anaerobic digestion of raw vinasse through the combined system with COD removal efficiency of 86.7% and higher CH 4 and a lower H 2 S content in biogas.

  16. Identification of Chemical Reactor Plant’s Mathematical Model

    OpenAIRE

    Pyakullya, Boris Ivanovich; Kladiev, Sergey Nikolaevich

    2015-01-01

    This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  17. Modelling of HTR (High Temperature Reactor Pebble-Bed 10 MW to Determine Criticality as A Variations of Enrichment and Radius of the Fuel (Kernel With the Monte Carlo Code MCNP4C

    Directory of Open Access Journals (Sweden)

    Hammam Oktajianto

    2014-12-01

    Full Text Available Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention due to many desired characteristics such as inherent safety, modularity, relatively low cost, short construction period, and easy financing. High temperature reactor (HTR pebble-bed as one of type of gas-cooled reactor concept is getting attention. In HTR pebble-bed design, radius and enrichment of the fuel kernel are the key parameter that can be chosen freely to determine the desired value of criticality. This paper models HTR pebble-bed 10 MW and determines an effective of enrichment and radius of the fuel (Kernel to get criticality value of reactor. The TRISO particle coated fuel particle which was modelled explicitly and distributed in the fuelled region of the fuel pebbles using a Simple-Cubic (SC lattice. The pebble-bed balls and moderator balls distributed in the core zone using a Body-Centred Cubic lattice with assumption of a fresh fuel by the fuel enrichment was 7-17% at 1% range and the size of the fuel radius was 175-300 µm at 25 µm ranges. The geometrical model of the full reactor is obtained by using lattice and universe facilities provided by MCNP4C. The details of model are discussed with necessary simplifications. Criticality calculations were conducted by Monte Carlo transport code MCNP4C and continuous energy nuclear data library ENDF/B-VI. From calculation results can be concluded that an effective of enrichment and radius of fuel (Kernel to achieve a critical condition was the enrichment of 15-17% at a radius of 200 µm, the enrichment of 13-17% at a radius of 225 µm, the enrichments of 12-15% at radius of 250 µm, the enrichments of 11-14% at a radius of 275 µm and the enrichment of 10-13% at a radius of 300 µm, so that the effective of enrichments and radii of fuel (Kernel can be considered in the HTR 10 MW. Keywords—MCNP4C, HTR, enrichment, radius, criticality 

  18. First TREAT [Transient Reactor Test Facility] transient overpower tests on U-Pu-Zr fuel: M5 and M6

    International Nuclear Information System (INIS)

    Robinson, W.R.; Bauer, T.H.; Wright, A.E.; Rhodes, E.A.; Stanford, G.S.; Klickman, A.E.

    1987-01-01

    Transient Reactor Test Facility (TREAT) tests M5 and M6 were the first transient overpower (TOP) tests of the margin to cladding breach and prefailure elongation of metallic U-Pu-Zr ternary fuel, the reference fuel of the Integral Fast Reactor concept. Similar tests on U-Fs fueled EBR-II driver pins were previously performed and reported [1,2]. Results from these earlier tests indicated a margin to failure of about 4 times nominal power and significant axial elongation prior to failure, a feature that was very pronounced at low burnups. While these two fuel types are similar in many respects, the ternary alloy exhibits a much more complex physical structure and is typically irradiated at much higher temperatures. Thus, a prime motivation for performing M5 and M6 was to compare the safety related fuel performance characteristics of U-Fs and U-Pu-Zr. This report described conditions, results, and conclusions of testing of these fuel types

  19. Radiation Protection Practices during the Helium Circulator Maintenance of the 10 MW High Temperature Gas-Cooled Reactor-Test Module (HTR-10

    Directory of Open Access Journals (Sweden)

    Chengxiang Guo

    2016-01-01

    Full Text Available Current radiation protection methodology offers abundant experiences on light-water reactors, but very few studies on high temperature gas-cooled reactor (HTR. To fill this gap, a comprehensive investigation was performed to the radiation protection practices in the helium circulator maintenance of the Chinese 10 MW HTR test module (HTR-10 in this paper. The investigation reveals the unique behaviour of HTR-10s radiation sources in the maintenance as well as its radionuclide species and presents the radiation protection methods that were tailored to these features. Owing to these practices, the radioactivity level was kept low throughout the maintenance and only low-level radioactive waste was generated. The quantitative analysis further demonstrates that the decontamination efficiency was over 89% for surface contamination and over 34% for γ dose rate and the occupational exposure was much lower than both the limits of regulatory and the exposure levels in comparable literature. These results demonstrate the effectiveness of the reported radiation protection practices, which directly provides hands-on experience for the future HTR-PM reactor and adds to the completeness of the radiation protection methodology.

  20. 4s24p3--4s4p4 and 4s24p3--4s2fp25s transitions in Y VII, Zr VIII, Nb IX, and MoX

    International Nuclear Information System (INIS)

    Reader, J.; Acquista, N.

    1981-01-01

    Spectra of ionized Y, Zr, Nb, and Mo have been observed in sliding-spark and triggered-spark discharges on 10.7-m normal- and grazing-incidence spectrographs at the National Bureau of Standards in Washington, D. C. From these observations the 4s 2 4p 3 --4s4p 4 transitions in Y VII, Zr VIII, Nb IX, and Mo X have been identified. The 4s 2 4p 3 --4s 2 4p 2 5s transitions in Y VII-Mo X, previously identified by Rahimullah et al. [Phys. Scr. 14, 221--223 (1976); 18, 96--106 (1978)], have been confirmed. In Y VII the 4s 2 4p 3 --4s 2 4p 2 6s and 4s4p 4 --4p 5 transition also have been found. The parameters obtained from least-squares fits to the energy levels are compared with Hartree--Fock calculations. Preliminary values of the ionization energies have been determined as 110.02 +- 0.15 eV for Y VII, 133.7 +- 0.5 eV for Zr VIII, 159.2 +- 0.7 eV for Nb IX, and 186.4 +- 1.2 eV for Mo X

  1. Twenty years of Radiology in RP-10 nuclear reactor protection; Veinte anos de proteccion radiologica en el reactor nuclear RP-10

    Energy Technology Data Exchange (ETDEWEB)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano, E-mail: lzapata@ipen.gob.pe, E-mail: framos@ipen.gob.pe, E-mail: rarrieta@ipen.gob.pe, E-mail: mvela@ipen.gob.pe [Instituto Peruano de Energia Nuclear (IPEN), Lima (Peru)

    2013-07-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  2. Identification of Chemical Reactor Plant’s Mathematical Model

    Directory of Open Access Journals (Sweden)

    Pyakillya Boris

    2015-01-01

    Full Text Available This work presents a solution of the identification problem of chemical reactor plant’s mathematical model. The main goal is to obtain a mathematical description of a chemical reactor plant from experimental data, which based on plant’s time response measurements. This data consists sequence of measurements for water jacket temperature and information about control input signal, which is used to govern plant’s behavior.

  3. Design of SES-10 nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Cuttler, J.M.

    1991-03-01

    The SES-10 units are unpressurized, pool-type nuclear reactors of 10MW rating, designed for supplying energy to hot water district heating systems, economically and without pollution. Water for heat distribution is brought to a maximum temperature of 85 degrees C. Conventional heating units supplement the output from SES-10 units for peak load and during maintenance. The SES-10 is housed in a low-cost building, with a double-walled pool in the ground. A naturally circulating primary system and a pumped secondary system transport heat from the reactor to the distribution system. The unit is fully automated and easy to maintain. Because of the many active and passive safety features, it is feasible to license the SES-10 for operation in a city and easy to explain it to the public for their acceptance. The core lasts approximately 43 months at a capacity factor of 70%, and the cost of heat is expected to be 2 to 2.5 cents/kWh

  4. Fact reactor fuel alloys: Retrospective and prospective views

    International Nuclear Information System (INIS)

    Nevitt, M.V.

    1989-01-01

    The relationship between the physical metallurgy of the EBR-II metallic fuel, U-5% Fs, and its performance in the reactor are described. An understanding of these relationships, along with the optimal matching of fuel properties to fuel-element design, have been essential in the 23 year successful utilization of the fuel. The knowledge and experience gained are being employed in the current development of a new U-Pu-Zr metallic fuel for a proposed advanced reactor (orig./MM)

  5. 408-fs SESAM mode locked Cr:ZnSe laser

    Science.gov (United States)

    Bu, Xiangbao; Shi, Yuhang; Xu, Jia; Li, Huijuan; Wang, Pu

    2018-01-01

    We report self-starting femtosecond operation of a 127-MHz SESAM mode locked Cr:ZnSe laser around 2420 nm. A thulium doped double clad fiber laser at 1908 nm was used as the pumping source. In the normal dispersion regime, stable pulse pairs with constant phase differences in the multipulse regime were observed. The maximum output power was 342 mW with respect to incident pump power of 4.8 W and the corresponding slope efficiency was 10.4%. By inserting a piece of sapphire plate, dispersion compensation was achieved and the intra-cavity dispersion was moved to the anomalous regime. A maximum output power of 403 mW was obtained and the corresponding slope efficiency was 12.2%. Pulse width was measured to be 408 fs by a collinear autocorrelator using two-photon absorption in an InGaAs photodiode. The laser spectrum in multipulse operation showed a clear periodic modulation.

  6. SeaWiFS technical report series. Volume 11: Analysis of selected orbit propagation models for the SeaWiFS mission

    Science.gov (United States)

    Patt, Frederick S.; Hoisington, Charles M.; Gregg, Watson W.; Coronado, Patrick L.; Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Indest, A. W. (Editor)

    1993-01-01

    An analysis of orbit propagation models was performed by the Mission Operations element of the Sea-viewing Wide Field-of-View Sensor (SeaWiFS) Project, which has overall responsibility for the instrument scheduling. The orbit propagators selected for this analysis are widely available general perturbations models. The analysis includes both absolute accuracy determination and comparisons of different versions of the models. The results show that all of the models tested meet accuracy requirements for scheduling and data acquisition purposes. For internal Project use the SGP4 propagator, developed by the North American Air Defense (NORAD) Command, has been selected. This model includes atmospheric drag effects and, therefore, provides better accuracy. For High Resolution Picture Transmission (HRPT) ground stations, which have less stringent accuracy requirements, the publicly available Brouwer-Lyddane models are recommended. The SeaWiFS Project will make available portable source code for a version of this model developed by the Data Capture Facility (DCF).

  7. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license... 10 Energy 2 2010-01-01 2010-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF...

  8. SeaWiFS calibration and validation plan, volume 3

    International Nuclear Information System (INIS)

    Hooker, S.B.; Firestone, E.R.; Mcclain, C.R.; Esaias, W.E.; Barnes, W.; Guenther, B.; Endres, D.; Mitchell, B.G.; Barnes, R.

    1992-09-01

    The Sea-viewing Wide Field-of-view Sensor (SeaWiFS) will be the first ocean-color satellite since the Nimbus-7 Coastal Zone Color Scanner (CZCS), which ceased operation in 1986. Unlike the CZCS, which was designed as a proof-of-concept experiment, SeaWiFS will provide routine global coverage every 2 days and is designed to provide estimates of photosynthetic concentrations of sufficient accuracy for use in quantitative studies of the ocean's primary productivity and biogeochemistry. A review of the CZCS mission is included that describes that data set's limitations and provides justification for a comprehensive SeaWiFS calibration and validation program. To accomplish the SeaWiFS scientific objectives, the sensor's calibration must be constantly monitored, and robust atmospheric corrections and bio-optical algorithms must be developed. The plan incorporates a multi-faceted approach to sensor calibration using a combination of vicarious (based on in situ observations) and onboard calibration techniques. Because of budget constraints and the limited availability of ship resources, the development of the operational algorithms (atmospheric and bio-optical) will rely heavily on collaborations with the Earth Observing System (EOS), the Moderate Resolution Imaging Spectrometer (MODIS) oceans team, and projects sponsored by other agencies, e.g., the U.S. Navy and the National Science Foundation (NSF). Other elements of the plan include the routine quality control of input ancillary data (e.g., surface wind, surface pressure, ozone concentration, etc.) used in the processing and verification of the level-0 (raw) data to level-1 (calibrated radiances), level-2 (derived products), and level-3 (gridded and averaged derived data) products

  9. Operating history of U.S. nuclear power reactors

    International Nuclear Information System (INIS)

    1974-01-01

    The operating history of U. S. nuclear power plants through December 31, 1974 has been collected. Included are those nuclear reactor facilities which produce electricity, even if in token amounts, or which are part of a development program concerned with the generation of electricity through the use of a nuclear reactor as a heat source. The information is based on data furnished by facility operators. The charts are plotted in terms of cumulative thermal energy as a function of time. Since only those shutdowns of five days or more are shown, the charts do not give a detailed history of plant operation. They do, however, give an overview of the operating history of a variety of developmental and experimental nuclear power reactors. The data show the yearly gross generation of electricity for each U. S. nuclear plant and, for civilian power plants, information on reactor availability and plant capacity factor. (U.S.)

  10. Research about reactor operator's personability characteristics and performance

    Energy Technology Data Exchange (ETDEWEB)

    Wei Li; He Xuhong; Zhao Bingquan [Tsinghua Univ., Institute of Nuclear Energy Technology, Beijing (China)

    2003-03-01

    To predict and evaluate the reactor operator's performance by personality characteristics is an important part of reactor operator safety assessment. Using related psychological theory combined with the Chinese operator's fact and considering the effect of environmental factors to personality analysis, paper does the research about the about the relationships between reactor operator's performance and personality characteristics, and offers the reference for operator's selection, using and performance in the future. (author)

  11. [Atmospheric emission of PCDD/Fs from secondary aluminum metallurgy industry in the southwest area, China].

    Science.gov (United States)

    Lu, Yi; Zhang, Xiao-Ling; Guo, Zhi-Shun; Jian, Chuan; Zhu, Ming-Ji; Deng, Li; Sun, Jing; Zhang, Qin

    2014-01-01

    Five secondary aluminum metallurgy enterprises in the southwest area of China were measured for emissions of PCDD/Fs. The results indicated that the emission levels of PCDD/Fs (as TEQ) were 0.015-0.16 ng x m(-3), and the average was 0.093 ng x m(-3) from secondary aluminum metallurgy enterprises. Emission factors of PCDD/Fs (as TEQ) from the five secondary aluminum metallurgy enterprises varied between 0.041 and 4.68 microg x t(-1) aluminum, and the average was 2.01 microg x t(-1) aluminum; among them, PCDD/Fs emission factors from the crucible smelting furnace was the highest. Congener distribution of PCDD/F in stack gas from the five secondary aluminum metallurgies was very different from each other. Moreover, the R(PCDF/PCDD) was the lowest in the enterprise which was installed only with bag filters; the R(PCDF/PCDD) were 3.8-12.6 (the average, 7.7) in the others which were installed with water scrubbers. The results above indicated that the mechanism of PCDD/Fs formation was related to the types of exhaust gas treatment device. The results of this study can provide technical support for the formulation of PCDD/Fs emission standards and the best available techniques in the secondary aluminum metallurgy industry.

  12. Safety-related parameters for the MAPLE research reactor and a comparison with the IAEA generic 10-MW research reactor

    International Nuclear Information System (INIS)

    Carlson, P.A.; Lee, A.G.; Smith, H.J.; Ellis, R.J.

    1989-07-01

    A summary is presented of some of the principle safety-related physics parameters for the MAPLE Research Reactor, and a comparison with the IAEA Generic 10-MW Reactor is given. This provides a means to assess the operating conditions and fuelling requirements for safe operation of the MAPLE Research Reactor under accepted standards

  13. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:30 AM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011. Point de situation du mardi 15 mars 2011 a 10h30

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:30 AM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  14. Analysis of the DHCE experiment in the position A10 of the ATR reactor

    Energy Technology Data Exchange (ETDEWEB)

    Gomes, I.C.; Smith, D.L.; Tsai, H. [Argonne National Lab., IL (United States)

    1997-08-01

    Calculations were performed to assess the possibility of performing DHCE experiments in mixed spectrum fission reactors. Calculated values of key parameters were compared with limit values for each quantity. The values calculated were: He-4 production from the {sup 6}Li(n,t){sup 4}He reaction, tritium leakage, required tritium concentration in lithium, initial tritium charge per capsule, and helium to dpa ratio after 10 dpa of irradiation.

  15. Polybrominated dibenzo-p-dioxins and dibenzofurans (PBDD/Fs) in e-waste plastic in Nigeria.

    Science.gov (United States)

    Sindiku, O; Babayemi, J O; Tysklind, M; Osibanjo, O; Weber, R; Watson, A; Schlummer, M; Lundstedt, S

    2015-10-01

    Plastics from cathode ray tube (CRT) casings were sampled in Nigeria and analysed for their polybrominated dibenzo-p-dioxin and dibenzofuran (PBDD/F) content. PBDD/Fs, consisting mainly of PBDFs, were detected in BFR containing plastic with a median (mean) concentration of 18,000 ng/g (41,000 ng/g). The PBDD/Fs levels were highest in samples containing PBDEs, but the levels of PBDFs were two orders of magnitude higher than the levels reported in the technical PBDE mixtures and where frequently exceeding 1000 μg/g of PBDE content. These higher levels are likely to arise from additional transformation of PBDEs during production, use, recycling, or storage, but the processes responsible were not identified in this study. PBDD/Fs in CRT casings containing1,2-bistribromophenoxyethane (TBPE) were dominated by tetrabrominated dibenzo-p-dioxin (TBDDs) with concentrations around 10 μg/g of the TBPE content. The PBDD/Fs in CRT casings containing tetrabromobisphenol A (TBBPA) were found at concentrations around 0.1 μg/g of TBBPA levels. Casings treated with TBPE or TBBPA often contained PBDEs (and PBDF) as impurities-probably originating from recycled e-waste plastics. It was estimated that the 237,000 t of CRT casings stockpiled in Nigeria contain between 2 and 8 t of PBDD/Fs. The total PBDD/F contamination in polymers arising from total historic PBDE production/use is estimated in the order of 1000 t. TEQ values of CRT samples frequently exceeded the Basel Convention's provisional low POPs content of 15 ng TEQ/g. Due to the significant risks to health associated with PBDD/Fs, more detailed studies on the exposure routes from PBDD/Fs in stockpiles are needed.

  16. Removal of FePO4 and Fe3(PO4)2 crystals on the surface of passive fillers in Fe0/GAC reactor using the acclimated bacteria

    International Nuclear Information System (INIS)

    Lai, Bo; Zhou, Yuexi; Yang, Ping; Wang, Juling; Yang, Jinghui; Li, Huiqiang

    2012-01-01

    Highlights: ► Fe 3 (PO 4 ) 2 and FePO 4 crystals would weaken treatment efficiency of Fe 0 /GAC reactor. ► Fe 3 (PO 4 ) 2 and FePO 4 crystals could be removed by the acclimated bacteria. ► FeS and sulfur in the passive film would be removed by the sulfur-oxidizing bacteria. ► Develop a cost-effective bio-regeneration technology for the passive fillers. - Abstract: As past studies presented, there is obvious defect that the fillers in the Fe 0 /GAC reactor begin to be passive after about 60 d continuous running, although the complicated, toxic and refractory ABS resin wastewater can be pretreated efficiently by the Fe 0 /GAC reactor. During the process, the Fe 3 (PO 4 ) 2 and FePO 4 crystals with high density in the passive film are formed by the reaction between PO 4 3− and Fe 2+ /Fe 3+ . Meanwhile, they obstruct the formation of macroscopic galvanic cells between Fe 0 and GAC, which will lower the wastewater treatment efficiency of Fe 0 /GAC reactor. In this study, in order to remove the Fe 3 (PO 4 ) 2 and FePO 4 crystals on the surface of the passive fillers, the bacteria were acclimated in the passive Fe 0 /GAC reactor. According to the results, it can be concluded that the Fe 3 (PO 4 ) 2 and FePO 4 crystals with high density in the passive film could be decomposed or removed by the joint action between the typical propionic acid type fermentation bacteria and sulfate reducing bacteria (SRB), whereas the PO 4 3− ions from the decomposition of the Fe 3 (PO 4 ) 2 and FePO 4 crystals were released into aqueous solution which would be discharged from the passive Fe 0 /GAC reactor. Furthermore, the remained FeS and sulfur (S) in the passive film also can be decomposed or removed easily by the oxidation of the sulfur-oxidizing bacteria. This study provides some theoretical references for the further study of a cost-effective bio-regeneration technology to solve the passive problems of the fillers in the zero-valent iron (ZVI) or Fe 0 /GAC reactor.

  17. fs - kes ta on ja kust ta tuleb : [luuletused] / [Mesikepp, Indrek] fs

    Index Scriptorium Estoniae

    fs, pseud., 1971-

    2004-01-01

    Sisu: fs - kes ta on ja kust ta tuleb ; "töötasin arhiivis..." ; mustad puud mustas vees ; "on päev. on kylm. on öö..." ; "tead ju kyll..." ; "päiksest paistes päevad..." ; "mida sa teed kui on öö..."

  18. Effective management of regulator RI/FS comments

    International Nuclear Information System (INIS)

    Wolinsky, S.M.; Lojek, D.; George, R.D.; Houser, S.M.; Strimbu, M.J.

    1995-01-01

    This paper describes a successful strategy that facilitates regulatory approval of CERCLA documents required by compliance agreement and CERCLA, based on the experience of Operable Unit 1, Waste Storage Area, of the Fernald Environmental Management Project (FEMP). This strategy, which has become the site standard at the FEMP, was instrumental in obtaining regulator approval of the OU1 RI and FS, and early approval of the Record of Decision during a very tight compliance agreement-driven schedule. This strategy can be applied at any DOE Superfund site, especially where there is need to recover lost schedule, an incentive to meet milestones early, a need to improve the relationship between the DOE and the regulators, or where the regulatory agencies have historically provided a large volume of comments on CERCLA documents. The strategy focuses on early identification and resolution of issues relating to draft RI/FS documents, as raised in regulatory agency review comments. This pro-active strategy has the potential for schedule and cost savings, as well as for improved communication between DOE and the regulators. The strategy includes preparation of a separate comment response document, integration of comment responses with RI/FS documents, development of a database of agency comments and their resolution, and sharing lessons learned with preparers of subsequent RI/FS documents. The paper provides background on the FEMP and describes the FEMP comment response strategy; DOE and regulator interface; the Sitewide Comment Database; networked electronic file management; the process for classifying, analyzing, and responding to comments; integration with base RI/FS documents; and a conclusion

  19. Effective management of regulator RI/FS comments

    Energy Technology Data Exchange (ETDEWEB)

    Wolinsky, S.M.; Lojek, D.; George, R.D.; Houser, S.M.; Strimbu, M.J.

    1995-12-31

    This paper describes a successful strategy that facilitates regulatory approval of CERCLA documents required by compliance agreement and CERCLA, based on the experience of Operable Unit 1, Waste Storage Area, of the Fernald Environmental Management Project (FEMP). This strategy, which has become the site standard at the FEMP, was instrumental in obtaining regulator approval of the OU1 RI and FS, and early approval of the Record of Decision during a very tight compliance agreement-driven schedule. This strategy can be applied at any DOE Superfund site, especially where there is need to recover lost schedule, an incentive to meet milestones early, a need to improve the relationship between the DOE and the regulators, or where the regulatory agencies have historically provided a large volume of comments on CERCLA documents. The strategy focuses on early identification and resolution of issues relating to draft RI/FS documents, as raised in regulatory agency review comments. This pro-active strategy has the potential for schedule and cost savings, as well as for improved communication between DOE and the regulators. The strategy includes preparation of a separate comment response document, integration of comment responses with RI/FS documents, development of a database of agency comments and their resolution, and sharing lessons learned with preparers of subsequent RI/FS documents. The paper provides background on the FEMP and describes the FEMP comment response strategy; DOE and regulator interface; the Sitewide Comment Database; networked electronic file management; the process for classifying, analyzing, and responding to comments; integration with base RI/FS documents; and a conclusion.

  20. Limits and conditions for continuous operation of WWR-S reactor

    International Nuclear Information System (INIS)

    Pittermann, P.; Listik, E.

    1979-02-01

    The fundamental technological and nuclear characteristics of the WWR-S reactor, safety limits and concepts of technical surveillance with particular attention to radiation safety of staff and of neighbouring population are outlined. The rules are mandatory for the reactor staff and for the users. The material is part of safety documentation for the WWR-S reactor. (author)

  1. Design of SES-10 nuclear reactor for district heating

    International Nuclear Information System (INIS)

    Cuttler, J.M.

    1991-01-01

    The SES-10 units are unpressurized, pool-type nuclear reactors of 10 MW rating, designed for supplying energy to hot water district heating systems, economically and without pollution. Water for heat distribution is brought to a maximum temperature of 85 o C. Conventional heating units supplement the output from SES-10 units for peak load and during maintenance. The SES-10 is housed in a low-cost building, with a double-walled pool in the ground. A naturally circulating primary system and a pumped secondary system transport heat from the reactor to the distribution system. The unit is fully automated and easy to maintain. Because of the many active and passive safety features, it is feasible to license the SES-10 for operation in a city and easy to explain it to the public for their acceptance. The core lasts approximately 43 months at a capacity factor of 70%, and the cost of heat is expected to be 2 to 2.5 cents/kWh. (author) 8 figs

  2. Development of system analysis code for thermal-hydraulic simulation of integral reactor, Rex-10

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2010-10-15

    Rex-10 is an environment-friendly and economical small-scale nuclear reactor to provide the energy for district heating as well as the electric power in micro-grid. This integral reactor comprises several innovative concepts supported by advanced primary circuit components, low coolant parameters and natural circulation cooling. To evaluate the system performance and thermal-hydraulic behavior of the reactor, a system analysis code is being developed so that the new designs and technologies adopted in Rex-10 can be reflected. The research efforts are absorbed in programming the simple and fast-running thermal-hydraulic analysis software. The details of hydrodynamic governing equations component models and numerical solution scheme used in this code are presented in this paper. On the basis of one-dimensional momentum integral model, the models of point reactor neutron kinetics for thorium-fueled core, physical processes in the steam-gas pressurizer, and heat transfers in helically coiled steam generator are implemented to the system code. Implicit numerical scheme is employed to momentum and energy equations to assure the numerical stability. The accuracy of simulation is validated by applying the solution method to the Rex-10 test facility. Calculated natural circulation flow rate and coolant temperature at steady-state are compared to the experimental data. The validation is also carried out for the transients in which the sudden reduction in the core power or the feedwater flow takes place. The code's capability to predict the steady-state flow by natural convection and the qualitative behaviour of the primary system in the transients is confirmed. (Author)

  3. The feasibility study on commercialized fast reactor cycle system

    International Nuclear Information System (INIS)

    Noda, Hiroshi

    2002-01-01

    The feasibility study on commercialized Fast Reactor cycle system (FS) has been carried out by a joint team with the participation of all parties concerned in Japan since July, 1999. It aims to clarify various perspectives for commercialized fast reactor cycle system and also suggest development strategies to diverse social needs in the 21 st century. The FS consists of several phases. The phase 1 has progressed as planned and the highly feasible candidate concepts with innovative technologies have been screened out among a wide variety of concepts. During the phase 2, approximately five years after the phase 1, the in-depth design studies and engineering scale tests of key technologies are being conducted to verify and validate the feasibility of screened candidate concepts. At the end of the phase 2, a few promising concepts will be selected with their R and D tasks. The paper describes the results of the phase 1, the activities of the phase 2 and the new concept related to the fast reactor fuel cycle focusing on the reduction in environmental burden, which is one of key factors to sustain the nuclear power generation in the 21 st century

  4. Development of 4S and related technologies (7). Analytical evaluation of RVACS performance under loss of stacks condition

    International Nuclear Information System (INIS)

    Nishimura, Satoshi; Nishi, Yoshihisa; Ueda, Nobuyuki

    2009-01-01

    The 4S (Super-Safe, Small and Simple) reactor is a sodium-cooled fast reactor aiming at an application to dispersed energy source and multi-purpose use. An introduction of RVACS (Reactor Vessel Auxiliary Cooling System) can enhance the passive decay heat removal capability. In the present study, the RVACS performance in 4S reactor (10MWe, pool-type) was analytically evaluated under the functional loss of RVACS stack condition, which is considered as a beyond design basis event. A protected loss of heat sink accident was selected and simulated to evaluate the capability of RVACS to cool the plant under such an unusual condition. The three-dimensional thermal hydraulic analysis was conducted by PHOENICS code. Analytical results show that the functional loss of air outlet stack has more effect on RVACS performance than that of air inlet stack. The air flow rate in RVACS under the functional loss of one out of two outlet stacks decreases up to approximately 60% and the heat removal rate approximately 70%, comparing with those under the normal stack condition. However, the maximum hot plenum temperature is low enough to satisfy the safety criteria. (author)

  5. History of fast reactor development in U.S.A.-I

    International Nuclear Information System (INIS)

    Ninokata, Hisashi; Sasao, Nobuyki

    2007-01-01

    History and present state of fast reactor was reviewed in series. As a history of fast reactor development in U.S.A. - I, this third lecture presented the dawn of the fast reactor development in the USA. The first fast reactor was the Clementine reactor with plutonium fuels and mercury coolant. The LAMPRE-1 reactor was the first sodium cooled and molten plutonium reactor. Experimental breeder reactor (EBR-1) was the first reactor to produce electricity and four kinds of fuels were loaded. Zero-power reactors were constructed to conduct reactor physics experiments on fast reactors. Today there are renewed interests in fast reactors due to their ability to fission actinides and reduce radioactive wastes. (T. Tanaka)

  6. InterProScan Result: FS933294 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS933294 FS933294_3_ORF2 4539D97811267FB7 PFAM PF04695 Pex14_N NA ? IPR006785 unintegrated Cellular... Component: peroxisome (GO:0005777)|Cellular Component: membrane (GO:0016020) ...

  7. Calculation of the source term for a S1B-sequence at a VVER-1000 type reactor. Part 1

    International Nuclear Information System (INIS)

    Sdouz, G.

    1990-10-01

    The behaviour of the source term in a VVER-1000 type reactor is calculated using the 'Source Term Code Package' (STCP). The input data are based on the russian plant Zaporozhye-5. The selected accident sequence is a small break LOCA in the hot leg followed by loss offsite and onsite electric power (S 1 B-sequence). According to the course of the calculation the results are presented and analyzed for each program. Except for the noble gases all release fractions are lower than 10 -4 . 18 refs., 10 tabs. (Author)

  8. Posttest analysis of international standard problem 10 using RELAP4/MOD7

    International Nuclear Information System (INIS)

    Hsu, M.; Davis, C.B.; Peterson, A.C. Jr.; Behling, S.R.

    1981-01-01

    RELAP4/MOD7, a best estimate computer code for the calculation of thermal and hydraulic phenomena in a nuclear reactor or related system, is the latest version in the RELAP4 code development series. This paper evaluates the capability of RELAP4/MOD7 to calculate refill/reflood phenomena. This evaluation uses the data of International Standard Problem 10, which is based on West Germany's KWU PKL refill/reflood experiment K9A. The PKL test facility represents a typical West German four-loop, 1300 MW pressurized water reactor (PWR) in reduced scale while maintaining prototypical volume-to-power ratio. The PKL facility was designed to specifically simulate the refill/reflood phase of a hypothetical loss-of-coolant accident

  9. FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES&H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ``Alternative Teams,`` chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S&S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT`s analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option.

  10. The 10 MW multipurpose TRIGA reactor at Ongkharak Nuclear Research Center, Thailand

    International Nuclear Information System (INIS)

    Thurgood, B.E.; Razvi, J.; Whittemore, J.L.; Bhadrakom, K.

    1997-01-01

    General Atomics (GA), has been selected to lead a team of firms from the United States, Japan, Australia and Thailand to design, build and commission the Ongkharak Nuclear Research Center near Bangkok, Thailand, for the Office of Atomic Energy for Peace. The facilities to be provided comprise of: A Reactor Island, consisting of a 10 MW TRIGA reactor that takes full advantage of the inherent safety characteristics of uranium-zirconium hydride (UZrH) fuel; An Isotope Production Facility for the production of radioisotopes and radiopharmaceuticals using the TRIGA reactor; A Waste Processing and Storage Facility for the processing and storage of radioactive waste from the facility as well as other locations in Thailand. The centerpiece of the Center will be the TRIGA reactor, fueled with low-enriched UZrH fuel, cooled and moderated by light water, and reflected by beryllium and heavy water. The UZrH fueled reactor will have a rated steady state thermal power output of 10 MW, and will be capable of performing the following: Radioisotope production for medical, industrial and agricultural uses; Neutron transmutation doping of silicon; Beam experiments such as Neutron Scattering, Neutron Radiography (NR), and Prompt Gamma Neutron Activation Analysis (PGNAA); Medical therapy of patients using Boron Neutron Capture Therapy (BNCT); Applied research and technology development in the nuclear field; Training in principles of reactor operation, reactor physics, reactor experiments, etc. (author)

  11. Analytical evaluation of local fault in sodium cooled small fast reactor (4S). Preliminary evaluation of partial blockage in coolant channel

    International Nuclear Information System (INIS)

    Nishimura, Satoshi; Ueda, Nobuyuki

    2007-01-01

    Local faults are fuel failures that result from heat removal imbalance within a single subassembly especially in FBRs. Although the occurrence frequency of local faults is quite low, the licensing body required local faults evaluations in previous FBR plants to confirm the potential for the occurrence of severe fuel subassembly failure and its propagation. A conceptual design of 4S (Super-Safe, Small and Simple) is a sodium cooled fast reactor, which aims at an application to dispersed energy source and long core lifetime. It has a dense arrangement of fuel pins to achieve a long lifetime. Therefore, from the viewpoint of thermal hydraulics, the 4S reactor is considered to have more potential for coolant boiling and fuel pin failure caused by formation of local blockage, comparing these potential in the conventional FBRs. The objective of the present study is to evaluate the effect of local blockage on the coolant flow pattern and temperature rise in the 4S-type fuel subassembly under the normal operation condition. A series of three-dimensional thermal-hydraulic analysis in a single subassembly with local blockage was conducted by the commercialized CFD code 'PHOENICS'. Analytical results show that the peak coolant temperature behind the blockage rises with increasing the blockage area, however, the coolant boiling does not occur under the present analytical conditions. On the other hand, it is found that the liquid phase formation caused by eutectic reactions will occur between the metallic fuel and the cladding under the local blockage condition. However, the penetration rate of liquid phase at fuel-cladding interface is quit low. Therefore, it is expected that rapid fuel pin failure and its propagation to surrounding pins due to liquid phase formation will not occur. (author)

  12. Innovations and Enhancements for a Consortium of Big-10 University Research and Training Reactors. Final Report

    International Nuclear Information System (INIS)

    Brenizer, Jack

    2011-01-01

    The Consortium of Big-10 University Research and Training Reactors was by design a strategic partnership of seven leading institutions. We received the support of both our industry and DOE laboratory partners. Investments in reactor, laboratory and program infrastructure, allowed us to lead the national effort to expand and improve the education of engineers in nuclear science and engineering, to provide outreach and education to pre-college educators and students and to become a key resource of ideas and trained personnel for our U.S. industrial and DOE laboratory collaborators.

  13. InterProScan Result: FS775902 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS775902 FS775902_6_ORF1 74300360D38F371E PFAM PF05208 ALG3 NA ? IPR007873 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  14. Chernobyl: recovery operations and the entombment of Reactor 4

    International Nuclear Information System (INIS)

    Dalziel, S.P.C.

    1988-01-01

    The immediate actions taken following the accident at the Chernobyl-number 4 reactor in April 1986 are described. These included actions to put out the fires, initial medical aid and the dropping of sand, lead, dolomite and boron onto the reactor from helicopters. Following this the chamber below the damaged reactor core was filled with concrete to prevent any further explosions or meltdown. The reactor was subsequently entombed in steel and concrete. The evacuation of the surrounding area is also mentioned. (U.K.)

  15. InterProScan Result: FS835133 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS835133 FS835133_5_ORF2 844B4637600527DB PIR PIRSF017267 Sulfiredoxin 8.2e-48 T IPR016692 Sulfire...doxin Molecular Function: sulfiredoxin activity (GO:0032542)|Biological Process: oxidation reduction (GO:0055114) ...

  16. InterProScan Result: FS763011 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS763011 FS763011_3_ORF1 ADA83816196D1572 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 1.2e-07 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  17. Fundus oculi pigmentation studies simulating the fs-LASIK process Fundus oculi pigmentation studies simulating the fs-LASIK process

    Science.gov (United States)

    Sander, M.; Minet, O.; Zabarylo, U.; Müller, M.; Tetz, M. R.

    2012-06-01

    The femtosecond-laser in situ keratomileusis (fs-LASIK) technique has successfully entered the refractive surgery market to correct ametropia by cutting transparent corneal tissue with ultra-short laser pulses based on photodisruption. The laser pulses in the near infrared range (NIR) generate a laser-induced breakdown (LIOB) in the cornea. By propagating through the eye, a certain amount of the pulse is deposited in the cornea and the remaining energy interacts with the strong absorbing tissue behind. Due to the absorption by the retinal pigment epithelium and the transfer of the thermal energy to surrounding tissue, the transmitted energy can induce damage to the retina. The aim of this project was to find out the threshold influences concerning the tissue and the correlation between the results of the macroscopical appraisal and the fundus oculi pigmentation by simulating the fs-LASIK procedure with two various laser systems in the continuous wave (CW) and fs-regime. Therefore ex-vivo determinations were carried out macroscopically and histopathologically on porcine tissue.

  18. RA Research reactor Annual report 1982 - Part 1, Operation, maintenance and utilization of the RA reactor

    International Nuclear Information System (INIS)

    Sotic, O.; Martinc, R.; Kozomara-Maic, S.; Cupac, S.; Radivojevic, J.; Stamenkovic, D.; Skoric, M.; Miokovic, J.

    1982-12-01

    Reactor test operation started in September 1981 at 2 MW power with 80% enriched fuel continued during 1982 according to the previous plan. The initial reactor core was made of 44 fuel channel each containing 10 fuel slugs. The first half of 1982 was used for the needed measurements and analysis of operating parameters and functioning of reactor systems and equipment under operating conditions. Program concerned with the testing operation at higher power levels was started in the second half of this year. It was found that the inherent excess reactivity and control rod worths ensure safe operation according to the IAEA safety standards. Excess reactivity is high enough to enable higher power level of 4.7 MW during 4 monthly cycles each lasting 15-20 days. Favourable conditions for cooling exist for the initial core configuration. Effects of poisoning at startup on the reactivity and power density distribution were measured as well as initial spatial distribution of the neutron flux which was 3,9 10 13 cm -2 s -1 at 2 MW power. Modification of the calibration coefficient in the system for automated power level control was determined. All the results show that all the safety criteria and limitations concerned with fuel utilization are fulfilled if reactor power would be 4.7 MW. Additional testing operation at 3, 4, and 4.7 MW power levels will be needed after obtaining the licence for operating at nominal power. Transition from the initial core with 44 fuel channels to the equilibrium lattice configuration with 72 fuel channels each containing 10 fuel slugs, would be done gradually. Reactor was not operated in September because of the secondary coolant pipes were exchanged between Danube and the horizontal sedimentary. Control and maintenance of the reactor equipment was done regularly and efficiently dependent on the availability of the spare parts. Difficulties in maintenance of the reactor instrumentation were caused by unavailability of the outdated spare parts

  19. Broadband pump-probe spectroscopy with sub-10-fs resolution for probing ultrafast internal conversion and coherent phonons in carotenoids

    International Nuclear Information System (INIS)

    Polli, D.; Antognazza, M.R.; Brida, D.; Lanzani, G.; Cerullo, G.; De Silvestri, S.

    2008-01-01

    We use pump-probe spectroscopy with broadband detection to study electronic energy relaxation and coherent vibrational dynamics in carotenoids. A fast optical multichannel analyzer combined with a non-collinear optical parametric amplifier allows simultaneous acquisition of the differential transmission dynamics on the 500-700 nm wavelength range with sub-10-fs temporal resolution. The broad spectral coverage enables on the one hand a detailed study of the ultrafast bright-to-dark state internal conversion process; on the other hand, the tracking of the motion of the vibrational wavepacket launched on the ground state multidimensional potential energy surface. We present results on all-trans β-carotene and on a long-chain polyene in solution. The developed experimental setup enables the straightforward acquisition and analysis of coherent vibrational dynamics, highlighting time-frequency domain features with extreme resolution

  20. InterProScan Result: FS765894 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS765894 FS765894_3_ORF2 2218C53708677A45 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 7.9e-11 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  1. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  2. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PANTHER PTHR10082:SF12 INTEGRIN BETA-3 9e...7160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  3. InterProScan Result: FS874648 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874648 FS874648_2_ORF1 2CED241FB157BFCC PRINTS PR00309 ARRESTIN 7.8e-13 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  4. InterProScan Result: FS874648 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS874648 FS874648_2_ORF1 2CED241FB157BFCC PANTHER PTHR11792 ARRESTIN 1.9e-55 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  5. InterProScan Result: FS774270 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS774270 FS774270_5_ORF1 FB109746C115A036 PFAM PF04114 Gaa1 NA ? IPR007246 unintegrated Cellular... Component: integral to membrane (GO:0016021)|Cellular Component: GPI-anchor transamidase complex (GO:0042765) ...

  6. InterProScan Result: FS931761 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS931761 FS931761_2_ORF2 31D2C24B9731CAEC PFAM PF05753 TRAP_beta NA ? IPR008856 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  7. InterProScan Result: FS885591 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885591 FS885591_3_ORF2 718F710ADBEB9510 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.3e-13 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  8. InterProScan Result: FS880233 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS880233 FS880233_1_ORF2 88C10776BC024404 SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1.9e-07 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  9. A 20fs synchronization system for lasers and cavities in accelerators and FELs

    Science.gov (United States)

    Wilcox, R. B.; Byrd, J. M.; Doolittle, L. R.; Huang, G.; Staples, J. W.

    2010-02-01

    A fiber-optic RF distribution system has been developed for synchronizing lasers and RF plants in short pulse FELs. Typical requirements are 50-100fs rms over time periods from 1ms to several hours. Our system amplitude modulates a CW laser signal, senses fiber length using an interferometer, and feed-forward corrects the RF phase digitally at the receiver. We demonstrate less than 15fs rms error over 12 hours, between two independent channels with a fiber path length difference of 200m and transmitting S-band RF. The system is constructed using standard telecommunications components, and uses regular telecom fiber.

  10. Nuclear Reactor RA Safety Report, Vol. 4, Reactor

    International Nuclear Information System (INIS)

    1986-11-01

    RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

  11. Fast reactor safety testing in Transient Reactor Test (TREAT) in the 1980s

    International Nuclear Information System (INIS)

    Wright, A.E.; Dutt, D.S.; Harrison, L.J.

    1990-01-01

    Several series of fast reactor safety tests were performed in TREAT during the 1980s. These focused on the transient behavior of full-length oxide fuels (US reference, UK reference, and US advanced design) and on modern metallic fuels. Most of the tests addressed fuel behavior under transient overpower or loss-of-flow conditions. The test series were the PFR/TREAT tests; the RFT, TS, CDT, and RX series on oxide fuels; and the M series on metallic fuels. These are described in terms of their principal results and relevance to analyses and safety evaluation. 4 refs., 3 tabs

  12. InterProScan Result: FS848106 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS848106 FS848106_3_ORF3 48EA3AE107CE2860 PIR PIRSF017267 Sulfiredoxin 3.9e-13 T IPR016692 Sulfire...doxin Molecular Function: sulfiredoxin activity (GO:0032542)|Biological Process: oxidation reduction (GO:0055114) ...

  13. InterProScan Result: FS755117 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS755117 FS755117_5_ORF1 848EA0528A797D85 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 2.9e-76 T IPR008429 Cleft lip and palate transmembrane 1 ...

  14. InterProScan Result: FS742531 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS742531 FS742531_5_ORF1 83DE48A0149BB5E1 PANTHER PTHR23154 LEUCINE-RICH TRANSMEMBR...ANE PROTEINS 1.7e-16 T IPR000157 unintegrated Molecular Function: transmembrane receptor activity (GO:000488

  15. InterProScan Result: FS920349 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS920349 FS920349_1_ORF2 460BA22BB7066E3D PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 6e-44 T IPR008429 Cleft lip and palate transmembrane 1 ...

  16. InterProScan Result: FS756793 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS756793 FS756793_1_ORF2 CD4194218B70284D PRINTS PR01186 INTEGRINB 5.5e-17 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  17. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PRINTS PR01186 INTEGRINB 1.6e-17 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  18. InterProScan Result: FS885315 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS885315 FS885315_1_ORF2 BB16E7B6C4656671 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 6...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  19. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PANTHER PTHR10082:SF12 INTEGRIN BETA-3 3....007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  20. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_1_ORF2 2E2F43F4558B5288 PANTHER PTHR11792 ARRESTIN 2.6e-53 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  1. InterProScan Result: FS911973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS911973 FS911973_2_ORF3 FBDFC7C1F8C27366 PANTHER PTHR11792 ARRESTIN 6.3e-12 T IPR000698 Arrestin Biological... Process: signal transduction (GO:0007165)|Biological Process: sensory perception (GO:0007600) ...

  2. InterProScan Result: FS726027 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS726027 FS726027_2_ORF2 C7058CD552BC398B PFAM PF01545 Cation_efflux NA ? IPR002524 unintegrated Biological...nsporter activity (GO:0008324)|Cellular Component: membrane (GO:0016020)|Biological Process: transmembrane transport (GO:0055085) ...

  3. InterProScan Result: FS917145 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS917145 FS917145_2_ORF2 DB1A671B79D1A25B PFAM PF05208 ALG3 NA ? IPR007873 unintegrated Cellular... Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ...

  4. InterProScan Result: FS919781 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS919781 FS919781_2_ORF2 11D6928E8BA64F8F SUPERFAMILY SSF55194 Ribosome recycling f...actor, RRF 5.5e-35 T IPR002661 Ribosome recycling factor Biological Process: translation (GO:0006412) ...

  5. InterProScan Result: FS895314 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS895314 FS895314_5_ORF1 97DB8176F1361E8C SUPERFAMILY SSF51621 Phosphoenolpyruvate/pyruva...te domain 1e-21 T IPR015813 Pyruvate/Phosphoenolpyruvate kinase, catalytic core Molecular Function: catalytic activity (GO:0003824) ...

  6. Radiation resistant fiber Bragg grating in random air-line fibers for sensing applications in nuclear reactor cores.

    Science.gov (United States)

    Zaghloul, Mohamed A S; Wang, Mohan; Huang, Sheng; Hnatovsky, Cyril; Grobnic, Dan; Mihailov, Stephen; Li, Ming-Jun; Carpenter, David; Hu, Lin-Wen; Daw, Joshua; Laffont, Guillaume; Nehr, Simon; Chen, Kevin P

    2018-04-30

    This paper reports the testing results of radiation resistant fiber Bragg grating (FBG) in random air-line (RAL) fibers in comparison with FBGs in other radiation-hardened fibers. FBGs in RAL fibers were fabricated by 80 fs ultrafast laser pulse using a phase mask approach. The fiber Bragg gratings tests were carried out in the core region of a 6 MW MIT research reactor (MITR) at a steady temperature above 600°C and an average fast neutron (>1 MeV) flux >1.2 × 10 14 n/cm 2 /s. Fifty five-day tests of FBG sensors showed less than 5 dB reduction in FBG peak strength after over 1 × 10 20 n/cm 2 of accumulated fast neutron dose. The radiation-induced compaction of FBG sensors produced less than 5.5 nm FBG wavelength shift toward shorter wavelength. To test temporal responses of FBG sensors, a number of reactor anomaly events were artificially created to abruptly change reactor power, temperature, and neutron flux over short periods of time. The thermal sensitivity and temporal responses of FBGs were determined at different accumulated doses of neutron flux. Results presented in this paper reveal that temperature-stable Type-II FBGs fabricated in radiation-hardened fibers can survive harsh in-pile conditions. Despite large parameter drift induced by strong nuclear radiation, further engineering and innovation on both optical fibers and fiber devices could lead to useful fiber sensors for various in-pile measurements to improve safety and efficiency of existing and next generation nuclear reactors.

  7. Two novel tyrosine-containing peptides (Tyr4) of the adipokinetic hormone family in beetles of the families Coccinellidae and Silphidae

    Czech Academy of Sciences Publication Activity Database

    Gäde, G.; Šimek, Petr; Marco, H. G.

    2015-01-01

    Roč. 47, č. 11 (2015), s. 2323-2333 ISSN 0939-4451 R&D Projects: GA ČR GA13-18509S Institutional support: RVO:60077344 Keywords : Insects * beetles * Coccinellidae Subject RIV: CE - Biochemistry Impact factor: 3.196, year: 2015 http://link.springer.com/article/10.1007%2Fs00726-015-2011-4

  8. Revised reactor accident source terms in the U.S. and implementation for light water reactors

    International Nuclear Information System (INIS)

    Soffer, L.; Lee, J.Y.

    1992-01-01

    Current NRC reactor accident source terms used for licensing are contained in Regulatory Guides 1.3 and 1.4 and specify that 100 % of the core inventory of noble gases and 25 % of the iodine fission products are assumed to be instantaneously available for release from the containment. The chemical form of the iodine fission products is also assumed to be predominantly elemental (I 2 ) iodine. These assumptions have strongly affected present nuclear plant designs. Severe accident research results have confirmed that although the current source term is very substantial and has resulted in a very high level of plant capability, the present source term is no longer compatible with a realistic understanding of severe accidents. The NRC has issued a proposed revision of the reactor accident source terms as part of several regulatory activities to incorporate severe accident insights for future plants. A revision to 10 CFR 100 is also being proposed to specify site criteria directly and to eliminate source terms and doses for site evaluation. Reactor source terms will continue to be important in evaluating plant designs. Although intended primarily for future plants, existing and evolutionary power plants may voluntarily apply revised accident source term insights as well in licensing. The proposed revised accident source terms are presented in terms of fission product composition, magnitude, timing and iodine chemical form. Some implications for light water reactors are discussed. (author)

  9. A Shielding Analysis of Hot Cell for a 10 MW Research Reactor

    International Nuclear Information System (INIS)

    Alnajjar, Alaaddin; Park, Chang Je; Roh, Gyuhong; Lee, Byunchul

    2013-01-01

    In this paper, a shielding analysis has been performed for the hot cell in a 10 MW research reactor. Two kinds of shielding analysis code systems are used such as MCNPX2.7 and M-Shield7. The first one is Monte Carlo stochastic code and the second one is a deterministic point kernel code. The results are compared in this study. In order to obtain source term, the ORIGEN-S code is used for different kinds of source. Four kinds of sources are taken into consideration. From the simulation, it is also proposed that the proper thickness of shielding material and the maximum source capacity in the hot cell. This study shows preliminary analysis results of hot cell shielding for 10MW research reactor. Total four different source terms are considered such as spent fuel assembly, Ir-192, Mo-99, and I-131. For shielding material, general concrete, heavy concrete, and lead are used. MCNPX code is mainly used for a simplified hot cell model and the result are nearly consistent when compared with M-Shield code. Required shielding thickness and the hot cell capacity are also obtained for various criterion of surface dose rates

  10. Burnup measurements on spent fuel elements of the RP-10 research reactor

    Energy Technology Data Exchange (ETDEWEB)

    Vela Mora, Mariano; Gallardo Padilla, Alberto; Palomino, Jose Luis Castro, E-mail: mvela@ipen.gob.p [Instituto Peruano de Energia Nuclear (IPEN/Peru), Lima (Peru). Grupo de Calculo, Analisis y Seguridad de Reactores; Terremoto, Luis Antonio Albiac, E-mail: laaterre@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using {sup 137}Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%. (author)

  11. Burnup measurements on spent fuel elements of the RP-10 research reactor

    International Nuclear Information System (INIS)

    Vela Mora, Mariano; Gallardo Padilla, Alberto; Palomino, Jose Luis Castro

    2011-01-01

    This work describes the measurement, using nondestructive gamma-ray spectroscopy, of the average burnup attained by Material Testing Reactor (MTR) fuel elements irradiated in the RP-10 research reactor. Measurements were performed at the reactor storage pool area using 137 Cs as the only burnup monitor, even for spent fuel elements with cooling times much shorter than two years. The experimental apparatus was previously calibrated in efficiency to obtain absolute average burnup values, which were compared against corresponding ones furnished by reactor physics calculations. The mean deviation between both values amounts to 6%. (author)

  12. Design and construction of a preamplifier for research reactor control system using Russia’s neutron detectors

    International Nuclear Information System (INIS)

    Trinh Dinh Hai; Vo Van Tai; Le Van Diep; Nguyen Nhi Dien

    2016-01-01

    This paper presents the design and construction of a preamplifier device for Research Reactor Control System, using Russia’s Neutron Detectors of ionization and fission chambers. In this work, the preamplifier device which consists of a wide range Current to Frequency Converter block used with a compensation ionization chamber type KNK-3 to measure the thermal neutron flux in the range of 1x10"6 - 1x10"1"1 n/cm"2.s, a Pulse Preamplifier block used with a fission chamber type KNK-15 to measure the thermal neutron flux in the range of 1x10"0 - 1x10"6 n/cm"2.s, and a Power Supply block, was designed and tested in different conditions in the laboratory and at Dalat Nuclear Research Reactor (DNRR). Obtained results show that, the above blocks have almost design specifications as equivalent or better in comparison with the same function blocks of the DNRR Control System which were designed by the former Soviet Union. They also meet the utilization requirements as well as the experimental and training purposes. (author)

  13. InterProScan Result: FS907382 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS907382 FS907382_1_ORF2 1C0441A9D0DDEE80 SUPERFAMILY SSF47798 Barrier-to-autointegration... factor, BAF 1.3e-44 T IPR004122 Barrier- to-autointegration factor, BAF Molecular Function: DNA binding (GO:0003677) ...

  14. InterProScan Result: FS856416 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS856416 FS856416_5_ORF1 8BC932287F58E2D2 PANTHER PTHR21229 LUNG SEVEN TRANSMEMBRAN...E RECEPTOR 3.7e-48 T IPR009637 Transmembrane receptor, eukaryota Cellular Component: integral to membrane (GO:0016021) ...

  15. InterProScan Result: FS859736 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS859736 FS859736_6_ORF2 45B8287CF5DB2D42 PANTHER PTHR21347 CLEFT LIP AND PALATE ASSOCIATED TRANSME...MBRANE PROTEIN-RELATED 1.1e-92 T IPR008429 Cleft lip and palate transmembrane 1 ...

  16. InterProScan Result: FS875135 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875135 FS875135_2_ORF1 D56AE7CE71BA567E PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 8...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  17. InterProScan Result: FS875135 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS875135 FS875135_2_ORF1 D56AE7CE71BA567E PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  18. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 3...-matrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  19. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PROSITE PS00243 INTEGRIN_BETA NA T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  20. The U.S. Geological Survey's TRIGA® reactor

    Science.gov (United States)

    DeBey, Timothy M.; Roy, Brycen R.; Brady, Sally R.

    2012-01-01

    The U.S. Geological Survey (USGS) operates a low-enriched uranium-fueled, pool-type reactor located at the Federal Center in Denver, Colorado. The mission of the Geological Survey TRIGA® Reactor (GSTR) is to support USGS science by providing information on geologic, plant, and animal specimens to advance methods and techniques unique to nuclear reactors. The reactor facility is supported by programs across the USGS and is organizationally under the Associate Director for Energy and Minerals, and Environmental Health. The GSTR is the only facility in the United States capable of performing automated delayed neutron analyses for detecting fissile and fissionable isotopes. Samples from around the world are submitted to the USGS for analysis using the reactor facility. Qualitative and quantitative elemental analyses, spatial elemental analyses, and geochronology are performed. Few research reactor facilities in the United States are equipped to handle the large number of samples processed at the GSTR. Historically, more than 450,000 sample irradiations have been performed at the USGS facility. Providing impartial scientific information to resource managers, planners, and other interested parties throughout the world is an integral part of the research effort of the USGS.

  1. Nonsequential double ionization of D2 molecules with intense 20-fs pulses

    DEFF Research Database (Denmark)

    Sakai, H.; Larsen, J.J.; Wendt-Larsen, I.

    2003-01-01

    The kinetic-energy distribution of D+ fragments obtained from the ionization of D2 molecules with intense 20-fs pulses includes a high-energy component extending up to ˜10 eV. These fragments are only present for linearly, or slightly elliptically, polarized light. Both the maximum kinetic...

  2. Mark I 1/5-scale boiling water reactor pressure suppression experiment. Quick-look report for test numbers 1.0(a) and 1.0(b) performed on March 4 and 8, 1977

    International Nuclear Information System (INIS)

    McCauley, E.W.; Pitts, J.H.

    1977-01-01

    The experimental results obtained from pressure suppression experiment numbers 1.0(a) and 1.0(b) that were performed on the Lawrence Livermore Laboratory's 1 / 5 -scale boiling water reactor (BWR) Mark I pressure suppression experimental facility are summarized

  3. Characterization of a fast to thermal neutron spectrum converter on PROSPERO reactor

    Energy Technology Data Exchange (ETDEWEB)

    Jacquet, X.; Authier, N.; Casoli, P.; Combacon, S. [CEA, Valduc Center, 21120 Is sur Tille (France); Calzavarra, Y. [ILL, Institut Laue Langevin, 38000 Grenoble (France)

    2009-07-01

    The PROSPERO reactor is located at CEA Valduc Center in France. The reactor is composed of an internal core made of High Enriched Uranium metal alloy surrounded by a reflector of depleted uranium. The reactor is used as a fast neutron spectrum source and is operated in delayed critical state with a continuous and steady power for several hours, which can vary from 3 mW to 3 kW, which is the nominal power. The flux at nominal power varies from 5.10{sup +10} n.cm{sup -2}/s at the reflector surface to 10{sup +7} n.cm{sup -2}/s at 5 meters from reactor axis. It has been decided to build a neutron energy converter allowing the production of a neutron thermal spectrum. As the core produces fast neutrons spectrum, we built a hollow cubic box of 50 cm x 50 cm x 50 cm with 10-cm-thick polyethylene bricks and placed one meter away from central reactor axis to moderate as much as possible neutrons to lower energies (E<0.6 eV). Analysis of the moderated flux inside the converter was performed using different activation foils such as indium or gold. We have developed a model of the experiment in the Monte Carlo neutron transport code TRIPOLI-4. A non-analogous transport calculation scheme was necessary to reproduce properly the experimental activities. The results of the calculated activations are within 4% of the experimental measurements given with 10% uncertainty (2 sigma). We show that the converter realizes thermalization of 80 % of the PROSPERO reactor fast neutrons below the cadmium threshold of 0.6 eV. Epithermal neutrons represent 15% of the spectrum and only 5% are in the fast neutron range above 1 MeV. The total flux at the center of the converter is 1.4 10{sup +9} n.cm{sup -2}/s at 3000 W

  4. SeaWiFS data from oceanic waters around New Zealand: Validation and applications

    Science.gov (United States)

    Richardson, K.; Boyd, P.; Gall, M.; Pinkerton, M.

    Satellite observations of ocean colour are the only realistic way to measure phytoplankton abundance at regional and global scales. NASA's Sea-viewing Wide Field -o f-view Sensor (SeaWiFS) began operation in September 1997 and is still providing data today. The data are of particular value to New Zealand, which has the fourth largest Exclusive Economic Zone (EEZ) in the world (some 4 million km2 ). Analysis of moderate resolution (9 km) SeaWiFS monthly Standard Mapped Images has substantially increased knowledge of the dynamics of chlorophyll concentrations around New Zealand. SeaWiFS data over nearly three years shows that northern New Zealand Subtropical and Tasman Sea waters follow a classical cycle of spring and autumn chlorophyll blooms consistent with production being co-limited by nitrate and light. Subantarctic Waters south of New Zealand had a low-magnitude annual cycle of chlorophyll abundance that peaked in early autumn, consistent with production being principally iron-limited. Chlorophyll was generally highest in the Subtropical Front either side of New Zealand where Subtropical and Subantarctic waters mix. NIWA (National Institute of Water and Atmospheric Research) has been receiving and processing high resolution (1.1 km) SeaWiFS data for the NZ region since May 2000. In addition to this, extensive bio-optical data from a number of NIWA cruises are being used to validate the satellite data and assess the accuracy of the ocean products in New Zealand open ocean and coastal waters. The performance of the SeaWiFS chlorophyll-a algorithm (OC4v4) has been investigated by comparing high-precision in situ measurements of the underwater radiation field with measurements of phytoplankton pigment concentration. Analyses of these results suggest that the algorithm may be performing well in the open ocean for chlorophyll- a concentrations below 0.3-0.4 mg m-3 but overestimating by a factor of two or more at higher concentrations. NIWA believes that ocean colour

  5. InterProScan Result: FS860732 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS860732 FS860732_6_ORF1 0375CFA2D74CE0C2 PRINTS PR01186 INTEGRINB 3.7e-20 T IPR015812 Integri...0)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  6. InterProScan Result: FS773973 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS773973 FS773973_5_ORF1 95C70FFD3346651F PANTHER PTHR10082 INTEGRIN BETA SUBUNIT 9e-32 T IPR001169 Integri...atrix adhesion (GO:0007160)|Biological Process: integrin-mediated signaling pathway (GO:0007229)|Cellular Component: integrin complex (GO:0008305) ...

  7. InterProScan Result: FS783191 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS783191 FS783191_5_ORF1 072DBEF328F41109 PFAM PF04192 Utp21 5e-59 T IPR007319 Small-subunit process...ome, Utp21 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  8. Advanced 4S (super safe, small and simple) LMR

    International Nuclear Information System (INIS)

    Minato, A.; Handa, N.

    2000-01-01

    This paper describes a new nuclear power system which can be used for a greater variety of applications. The 4S liquid metal reactor has high inherent safety and passive safety characteristics. It is also easy to operate, maintain and inspect, faster to construct, more flexible in location, requires less initial investment, and is better suited to electrical grid management. The reactor offers a new route through which to expand the use of safe nuclear technology in the world. (author)

  9. Three-dimensional LASIK flap thickness variability: topographic central, paracentral and peripheral assessment, in flaps created by a mechanical microkeratome (M2 and two different femtosecond lasers (FS60 and FS200

    Directory of Open Access Journals (Sweden)

    Kanellopoulos AJ

    2013-04-01

    Full Text Available A John Kanellopoulos,1,2 George Asimellis1 1Laservision.gr Institute, Athens, Greece; 2NYU Medical School, New York, USA Purpose: To evaluate programmed versus achieved laser-assisted in situ keratomileusis (LASIK flap central thickness and investigate topographic flap thickness variability, as well as the effect of potential epithelial remodeling interference on flap thickness variability. Patients and methods: Flap thickness was investigated in 110 eyes that had had bilateral myopic LASIK several years ago (average 4.5 ± 2.7 years; range 2–7 years. Three age-matched study groups were formed, based on the method of primary flap creation: Group A (flaps made by the Moria Surgical M2 microkeratome [Antony, France], Group B (flaps made by the Abbott Medical Optics IntraLase™ FS60 femtosecond laser [Santa Ana, CA, USA], and Group C (flaps made by the Alcon WaveLight® FS200 femtosecond laser [Fort Worth, TX, USA]. Whole-cornea topographic maps of flap and epithelial thickness were obtained by scanning high-frequency ultrasound biomicroscopy. On each eye, topographic flap and epithelial thickness variability was computed by the standard deviation of thickness corresponding to 21 equally spaced points over the entire corneal area imaged. Results: The average central flap thickness for each group was 138.33 ± 12.38 µm (mean ± standard deviation in Group A, 128.46 ± 5.72 µm in Group B, and 122.00 ± 5.64 µm in Group C. Topographic flap thickness variability was 9.73 ± 4.93 µm for Group A, 8.48 ± 4.23 µm for Group B, and 4.84 ± 1.88 µm for Group C. The smaller topographic flap thickness variability of Group C (FS200 was statistically significant compared with that of Group A (M2 (P = 0.004, indicating improved topographic flap thickness consistency – that is, improved precision – over the entire flap area affected. Conclusions: The two femtosecond lasers produced a smaller flap thickness and reduced variability than the mechanical

  10. Mass balance and long-term fate of PCDD/Fs in a lagoon sediment and paddy soil, Niigata, Japan

    Energy Technology Data Exchange (ETDEWEB)

    Sakai, Mizuki [National Institute for Agro-Environmental Science, 3-1-3 Kannondai, Tsukuba, Ibaraki 305-8604 (Japan)], E-mail: mizukis@affrc.go.jp; Seike, Nobuyasu [National Institute for Agro-Environmental Science, 3-1-3 Kannondai, Tsukuba, Ibaraki 305-8604 (Japan)], E-mail: seike@niaes.affrc.go.jp; Kobayashi, Jun [National Institute for Environmental Studies, 16-2 Onogawa, Tsukuba, Ibaraki 305-8506 (Japan)], E-mail: kobayashi.jun@nies.go.jp; Kajihara, Hideo [National Institute of Advanced Industrial Science and Technology, 16-1 Tsukuba, Ibaraki 305-8569 (Japan)], E-mail: kajihara.hideo@aist.go.jp; Takahashi, Yukio [Academic Assembly Institute of Science and Technology, Niigata University, 2-8050 Ikarashi, Niigata City 950-2181 (Japan)], E-mail: yukitak@eng.niigata-u.ac.jp

    2008-12-15

    Polychlorinated dibenzo-p-dioxins (PCDDs) and polychlorinated dibenzofurans (PCDFs) in a sediment core and in samples of surface sediment and paddy soil collected from the Toyano lagoon and Kameda basin in Niigata, Japan, were analyzed to elucidate the temporal trends of their concentrations in the lagoon sediment and the relationship between the sediment and the paddy soil. The mass balance of these pollutants was also estimated to determine their long-term fate in surface waters. An analysis by chemical mass balance identified the agrochemicals pentachlorophenol and 2,4,6-trichlorophenyl 4-nitrophenyl ether as the major sources of PCDD/Fs. On the basis of the findings regarding the mass balance in the Kameda basin over the last 40 years, we estimate that more than half the input of PCDD/Fs to the Kameda basin has disappeared. We suggest that the PCDD/Fs that flowed out from the paddy fields have been transferred to the lower basin. - The long-term mass balance of PCDD/Fs in sediments from paddy soil is elucidated.

  11. 10 CFR 4.540 - Employment.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Employment. 4.540 Section 4.540 Energy NUCLEAR REGULATORY... Activities Conducted by the U.S. Nuclear Regulatory Commission § 4.540 Employment. No qualified handicapped person shall, on the basis of handicap, be subjected to discrimination in employment under any program or...

  12. InterProScan Result: FS916423 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS916423 FS916423_2_ORF2 B2940816BE6DE7BE PFAM PF04615 Utp14 2.7e-61 T IPR006709 Small-subunit process...ome, Utp14 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  13. InterProScan Result: FS917145 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available lular Component: endoplasmic reticulum (GO:0005783)|Cellular Component: integral to membrane (GO:0016021) ... ...FS917145 FS917145_2_ORF2 DB1A671B79D1A25B PFAM PF05208 ALG3 9e-110 T IPR007873 Glycosyltransferase, ALG3 Cel

  14. RESAR-3S. Reference safety analysis report, volume 1

    International Nuclear Information System (INIS)

    1975-01-01

    The nuclear steam supply system consists of a Westinghouse pressurized water reactor and closed reactor coolant loops connected in parallel to the reactor vessel. Each loop contains a reactor coolant pump and a steam generator. Also described are an electrically heated pressurizer and certain auxiliary systems. The thermal output of the system is 3425 MW(t) and the thermal output of the core is 3411 MW(t). (FS)

  15. Sub-100 fs high average power directly blue-diode-laser-pumped Ti:sapphire oscillator

    Science.gov (United States)

    Rohrbacher, Andreas; Markovic, Vesna; Pallmann, Wolfgang; Resan, Bojan

    2016-03-01

    Ti:sapphire oscillators are a proven technology to generate sub-100 fs (even sub-10 fs) pulses in the near infrared and are widely used in many high impact scientific fields. However, the need for a bulky, expensive and complex pump source, typically a frequency-doubled multi-watt neodymium or optically pumped semiconductor laser, represents the main obstacle to more widespread use. The recent development of blue diodes emitting over 1 W has opened up the possibility of directly diode-laser-pumped Ti:sapphire oscillators. Beside the lower cost and footprint, a direct diode pumping provides better reliability, higher efficiency and better pointing stability to name a few. The challenges that it poses are lower absorption of Ti:sapphire at available diode wavelengths and lower brightness compared to typical green pump lasers. For practical applications such as bio-medicine and nano-structuring, output powers in excess of 100 mW and sub-100 fs pulses are required. In this paper, we demonstrate a high average power directly blue-diode-laser-pumped Ti:sapphire oscillator without active cooling. The SESAM modelocking ensures reliable self-starting and robust operation. We will present two configurations emitting 460 mW in 82 fs pulses and 350 mW in 65 fs pulses, both operating at 92 MHz. The maximum obtained pulse energy reaches 5 nJ. A double-sided pumping scheme with two high power blue diode lasers was used for the output power scaling. The cavity design and the experimental results will be discussed in more details.

  16. Magellan/M2FS Spectroscopy of the Reticulum 2 Dwarf Spheroidal Galaxy

    Science.gov (United States)

    Walker, Matthew G.; Mateo, Mario; Olszewski, Edward W.; Bailey, John I., III; Koposov, Sergey E.; Belokurov, Vasily; Evans, N. Wyn

    2015-08-01

    We present results from spectroscopic observations with the Michigan/Magellan Fiber System (M2FS) of 182 stellar targets along the line of sight (LOS) to the newly discovered “ultrafaint” object Reticulum 2 (Ret 2). For 37 of these targets, the spectra are sufficient to provide simultaneous estimates of LOS velocity ({v}{los}, median random error {δ }{v{los}}=1.4 km s-1), effective temperature ({T}{eff}, {δ }{T{eff}}=478 K), surface gravity ({log}g, {δ }{logg}=0.63 dex), and iron abundance ([{Fe}/{{H}}], {δ }[{Fe/{{H}}]}=0.47 dex). We use these results to confirm 17 stars as members of Ret 2. From the member sample we estimate a velocity dispersion of {σ }{v{los}}= {3.6}-0.7+1.0 km s-1 about a mean of = {64.3}-1.2+1.2 km s-1 in the solar rest frame (˜ -90.9 km s-1 in the Galactic rest frame), and a metallicity dispersion of {σ }[{Fe/{{H}}]} = {0.49}-0.14+0.19 dex about a mean of = -{2.58}-0.33+0.34. These estimates marginalize over possible velocity and metallicity gradients, which are consistent with zero. Our results place Ret 2 on chemodynamical scaling relations followed by the Milky Way’s dwarf-galactic satellites. Under assumptions of dynamic equilibrium and negligible contamination from binary stars—both of which must be checked with deeper imaging and repeat spectroscopic observations—the estimated velocity dispersion suggests a dynamical mass of M({R}{{h}})≈ 5{R}{{h}}{σ }{v{los}}{}2/(2G) = {2.4}-0.8+1.4× {10}5 {M}⊙ enclosed within projected halflight radius {R}{{h}}˜ 32 pc, with mass-to-light ratio ≈ 2M({R}{{h}})/{L}V = {467}-168+286 in solar units. This paper presents data gathered with the Magellan Telescopes at Las Campanas Observatory, Chile.

  17. InterProScan Result: FS769068 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS769068 FS769068_2_ORF2 CC628FD86337D2E6 PFAM PF03998 Utp11 5.3e-70 T IPR007144 Small-subunit process...ome, Utp11 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  18. InterProScan Result: FS898120 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS898120 FS898120_5_ORF2 88A0F99A1A469778 PFAM PF03998 Utp11 6.1e-69 T IPR007144 Small-subunit process...ome, Utp11 Biological Process: rRNA processing (GO:0006364)|Cellular Component: small-subunit processome (GO:0032040) ...

  19. Manufacture of rings of 08Kh18N10T sheet for internal structures of WWER type reactors

    International Nuclear Information System (INIS)

    Fojta, A.; Nitka, B.

    1984-01-01

    Technology is presented of the manufacture of rings for the jacket, shaft, core catcher and shaft bottom of WWER-440 reactors produced by Vitkovice Steel Works. The rings are manufactured from sheets of austenitic steel 08Kh18N10T. The materials and technology problems are discussed of sheet production, ring welding technology and annealing following welding. The plastic properties are assessed of the welded joints and problems are outlined of ring production for WWER-1000 reactors. (B.S.)

  20. The Efficacy of the Quorum Sensing Inhibitor FS8 and Tigecycline in Preventing Prosthesis Biofilm in an Animal Model of Staphylococcal Infection

    Directory of Open Access Journals (Sweden)

    Andrea Giacometti

    2013-08-01

    Full Text Available We investigated the efficacy of tigecycline and FS8, alone or combined, in preventing prosthesis biofilm in a rat model of staphylococcal vascular graft infection. Graft infections were established in the back subcutaneous tissue of adult male Wistar rats by implantation of Dacron prostheses followed by topical inoculation with 2 x 107 colony-forming units of Staphylococcus aureus, strain Smith diffuse. The study included a control group, a contaminated group that did not receive any antibiotic prophylaxis, and three contaminated groups that received: (i intraperitoneal tigecycline, (ii FS8-soaked graft, and (iii tigecycline plus FS8-soaked graft, respectively. Each group included 15 animals. The infection burden was evaluated by using sonication and quantitative agar culture. Moreover, an in vitro binding-study was performed to quantify the how much FS8 was coated to the surface of the prosthesis. Tigecycline, combined with FS8, against the adherent bacteria showed MICs (2.00 mg/L and MBCs (4.00 mg/L four-fold lower with respect to tigecycline alone in in vitro studies. The rat groups treated with tigecycline showed the lowest bacterial numbers (4.4 x 104 ± 1.2 x 104 CFU/mL. The FS8-treated group showed a good activity and significant differences compared to control group with bacterial numbers of 6.8 x 104 ± 2.0 x 104 CFU/mL. A stronger inhibition of bacterial growth was observed in rats treated with a combined FS8 and tigecycline therapy than in those that were singly treated with bacterial numbers of 101 CFU/mL graft. In conclusion, the ability to affect biofilm formation as well, its property to be an antibiotic enhancer suggests FS8 as alternative or additional agent to use in conjunction with conventional antimicrobial for prevention of staphylococcal biofilm related infection.

  1. Nuclear energy. The innovations of the N4 reactor

    International Nuclear Information System (INIS)

    Anon.

    1998-01-01

    The coupling to the electric network of the two first units of N4 type reactors, on the site of Chooz in the Ardennes, marks the third great step of the French nuclear programme of PWR type reactors, after the realization of 34 units of 900 MWe and 20 units of 1300 M We. The nuclear boiler N4, realizes a new evolution in power, in performances and in reliability. (N.C.)

  2. Purification, cloning, characterization, and N-glycosylation analysis of a novel β-fructosidase from Aspergillus oryzae FS4 synthesizing levan- and neolevan-type fructooligosaccharides.

    Directory of Open Access Journals (Sweden)

    Li Xu

    Full Text Available β-Fructosidases are a widespread group of enzymes that catalyze the hydrolysis of terminal fructosyl units from various substrates. These enzymes also exhibit transglycosylation activity when they function with high concentrations of sucrose, which is used to synthesize fructooligosaccharides (FOS in the food industry. A β-fructosidase (BfrA with high transglycosylation activity was purified from Aspergillus oryzae FS4 as a monomeric glycoprotein. Compared with the most extensively studied Aspergillus spp. fructosidases that synthesize inulin-type β-(2-1-linked FOS, BfrA has unique transfructosylating property of synthesizing levan- and neolevan-type β-(2-6-linked FOS. The coding sequence (bfrAFS4, 1.86 kb of BfrA was amplified and expressed in Escherichia coli and Pichia pastoris. Both native and recombinant proteins showed transfructosylation and hydrolyzation activities with broad substrate specificity. These proteins could hydrolyze the following linkages: Glc α-1, 2-β Fru; Glc α-1, 3-α Fru; and Glc α-1, 5-β Fru. Compared with the unglycosylated E. coli-expressed BfrA (E.BfrA, the N-glycosylated native (N.BfrA and the P. pastoris-expressed BfrA (P.BfrA were highly stable at a wide pH range (pH 4 to 11, and significantly more thermostable at temperatures up to 50°C with a maximum activity at 55°C. Using sucrose as substrate, the Km and kcat values for total activity were 37.19±5.28 mM and 1.0016±0.039×104 s-1 for N.BfrA. Moreover, 10 of 13 putative N-glycosylation sites were glycosylated on N.BfrA, and N-glycosylation was essential for enzyme thermal stability and optima activity. Thus, BfrA has demonstrated as a well-characterized A. oryzae fructosidase with unique transfructosylating capability of synthesizing levan- and neolevan-type FOS.

  3. Measurement of the B{sub s}{sup 0}-B{sup Macron }{sub s}{sup 0} oscillation frequency {Delta}m{sub s} in B{sub s}{sup 0}{yields}D{sub s}{sup -}(3){pi} decays

    Energy Technology Data Exchange (ETDEWEB)

    Aaij, R. [Nikhef National Institute for Subatomic Physics, Amsterdam (Netherlands); Adeva, B. [Universidad de Santiago de Compostela, Santiago de Compostela (Spain); Adinolfi, M. [H.H. Wills Physics Laboratory, University of Bristol, Bristol (United Kingdom); Adrover, C. [CPPM, Aix-Marseille Universite, CNRS/IN2P3, Marseille (France); Affolder, A. [Oliver Lodge Laboratory, University of Liverpool, Liverpool (United Kingdom); Ajaltouni, Z. [Clermont Universite, Universite Blaise Pascal, CNRS/IN2P3, LPC, Clermont-Ferrand (France); Albrecht, J.; Alessio, F. [European Organization for Nuclear Research (CERN), Geneva (Switzerland); Alexander, M. [School of Physics and Astronomy, University of Glasgow, Glasgow (United Kingdom); Alkhazov, G. [Petersburg Nuclear Physics Institute (PNPI), Gatchina (Russian Federation); Alvarez Cartelle, P. [Universidad de Santiago de Compostela, Santiago de Compostela (Spain); Alves, A.A. [Sezione INFN di Roma La Sapienza, Roma (Italy); Amato, S. [Universidade Federal do Rio de Janeiro (UFRJ), Rio de Janeiro (Brazil); Amhis, Y. [Ecole Polytechnique Federale de Lausanne (EPFL), Lausanne (Switzerland); Anderson, J. [Physik-Institut, Universitaet Zuerich, Zuerich (Switzerland); Appleby, R.B. [School of Physics and Astronomy, University of Manchester, Manchester (United Kingdom); Aquines Gutierrez, O. [Max-Planck-Institut fuer Kernphysik (MPIK), Heidelberg (Germany); Archilli, F. [Laboratori Nazionali dell' INFN di Frascati, Frascati (Italy); European Organization for Nuclear Research (CERN), Geneva (Switzerland); Arrabito, L. [CC-IN2P3, CNRS/IN2P3, Lyon-Villeurbanne (France); Artamonov, A. [Institute for High Energy Physics (IHEP), Protvino (Russian Federation); and others

    2012-03-19

    The B{sub s}{sup 0}-B{sup Macron }{sub s}{sup 0} oscillation frequency {Delta}m{sub s} is measured with 36 pb{sup -1} of data collected in pp collisions at {radical}(s)=7 TeV by the LHCb experiment at the Large Hadron Collider. A total of 1381 B{sub s}{sup 0}{yields}D{sub s}{sup -}{pi}{sup +} and B{sub s}{sup 0}{yields}D{sub s}{sup -}{pi}{sup +}{pi}{sup -}{pi}{sup +} signal decays are reconstructed, with average decay time resolutions of 44 fs and 36 fs, respectively. An oscillation signal with a statistical significance of 4.6{sigma} is observed. The measured oscillation frequency is {Delta}m{sub s}=17.63{+-}0.11(stat){+-}0.02(syst) ps{sup -1}.

  4. Prevention of PCDD/Fs emission from a municipal wastewater sludge incinerator through enhanced control of copper aerosol

    Directory of Open Access Journals (Sweden)

    Peña, E.

    2012-10-01

    Full Text Available Municipal wastewater sludge incineration (MWSI leads to products of incomplete combustion, including chlorinated species such as dioxins and furans (PCDD/Fs. Other pollutants, such as heavy metals (HM, are released too as a consequence of feed traces, which depend on the specific activities of each area. The main aim of this work is to determine whether the early separation of the potential catalysts on the PCDD/Fs formation –HM as copper or zinc– offers a promising way to prevent the emission of these trace pollutants, considering that the current end-of-pipe measures don’t ensure their stable emission. Experimental results cover the size distributed target metal contents along the incineration line. These results show a high concentration of copper in the most penetrating aerosol size range of the electrostatic precipitator (0.6 μm - 1.0 μm, and how low emission values of both, total and metallic aerosol (mass basis, are compatible with irregular and unexplained outliers of PCDD/Fs emission.

    La incineración de lodos de aguas residuales urbanas acarrea la formación de compuestos derivados de combustiones incompletas, incluyendo especies cloradas como dioxinas y furanos (PCDD/Fs. Otros contaminantes, como metales pesados, se emiten como consecuencia de las trazas del lodo, las cuales dependen de las actividades del entorno. El objetivo principal es determinar si la separación de catalizadores potenciales en reacciones de formación de PCDD/Fs (cobre o zinc puede abrir vías para prevenir la emisión de contaminantes traza, considerando que ninguna de las técnicas de prevención actuales aseguran emisiones estables de metales pesados o PCDD/Fs. Se determinan concentraciones de metales pesados segregados por tamaño de partícula a lo largo de la línea de incineración. Los resultados muestran concentraciones elevadas de cobre en el aerosol de máxima penetración del electrofiltro (0,6 μm - 1,0 μm, y cómo concentraciones

  5. Superconformal geometry from the Grassmann and harmonic analyticities II: The N=4SU(2) conformal case

    International Nuclear Information System (INIS)

    Saidi, E.H.; Zakkari, M.

    1990-05-01

    N=4SU(2) conformal invariance is studied in harmonic superspace. It is shown that the N=4SU(2) conformal structure is equivalent to the harmonic analyticity. The solutions of the superconformal constraints are worked out in detail and the conformal properties of all objects of interests are given. A realization of the N=4 current in terms of the free (F.S.) hypermultiplet is obtained. (author). 10 refs

  6. Safety report on WWR-S reactor

    International Nuclear Information System (INIS)

    Horyna, J.; Kaisler, L.; Listik, E.

    1981-04-01

    The present Safety Report of the WWR-S reactor summarizes findings obtained during the trial and partially also permanent operation of the reactor after two stages of its reconstruction implemented between 1974 and 1976. Most data are presented necessary for assessing probable risks of possible accident conditions whose consequences pose health hazards to individuals of the population, radiation personnel and the facilities themselves. Attention is devoted to the description of the locality, to components and systems, heat removal from the core, design aspects, the quality of new and old parts of the technological circuits, the systems of protection and control, the emergency core cooling system, the problems of radiation safety, and to the safety analyses of the abnormal states envisaged. The Report was compiled with regard to IAEA and CMEA recommendations concerning safe operation of research reactors and to the recommendations and binding decisions of the Czechoslovak Atomic Energy Commission. (author)

  7. Spent nuclear fuel discharges from U.S. reactors 1994

    International Nuclear Information System (INIS)

    1996-02-01

    Spent Nuclear Fuel Discharges from US Reactors 1994 provides current statistical data on fuel assemblies irradiated at commercial nuclear reactors operating in the US. This year's report provides data on the current inventories and storage capacities at these reactors. Detailed statistics on the data are presented in four chapters that highlight 1994 spent fuel discharges, storage capacities and inventories, canister and nonfuel component data, and assembly characteristics. Five appendices, a glossary, and bibliography are also included. 10 figs., 34 tabs

  8. Beryllium and lithium resource requirements for solid blanket designs for fusion reactors

    International Nuclear Information System (INIS)

    Powell, J.R.

    1975-01-01

    The lithium and beryllium requirements are analyzed for an economy of 10 6 MW(e) CTR 3 capacity using solid blanket fusion reactors. The total lithium inventory in fusion reactors is only approximately 0.2 percent of projected U. S. resources. The lithium inventory in the fusion reactors is almost entirely 6 Li, which must be extracted from natural lithium. Approximately 5 percent of natural lithium can be extracted as 6 Li. Thus the total feed of natural lithium required is approximately 20 times that actually used in fusion reactors, or approximately 4 percent of U. S. resources. Almost all of this feed is returned to the U. S. resource base after 6 Li is extracted, however. The beryllium requirements are on the order of 10 percent of projected U. S. resources. Further, the present cost of lithium and the cost of beryllium extraction could both be increased tenfold with only minor effects on CTR capital cost. Such an increase should substantially multiply the economically recoverable resources of lithium and beryllium. It is concluded that there are no lithium or beryllium resource limitations preventing large-scale implementation of solid blanket fusion reactors. (U.S.)

  9. In-pile creep test technique for zirconium alloys examination in BR-10 reactor channels

    International Nuclear Information System (INIS)

    Pevchikh, Yu.M.; Kruglov, A.S.; Troyanov, V.M.

    2002-01-01

    The irradiation enhanced creep phenomenon was discovered in stainless steels as a specific physical process accompanying high-intensity neutron flux irradiation in fast reactors. IPPE is also experienced in irradiation creep test activities, studying different types of materials under irradiation in BR-10 fast reactor. Series of in-channel type test facilities were constructed and tested in BR-10 reactor's 'dry' channels in order to carry out full-scale instrumented examination regarded to in-pile creep behaviour of different reactor materials. As a result, a specific test technique, named 'Tensometric method', has been developed and experimentally proved to be power enough in order to investigate irradiation creep of materials right in situ under neutron irradiation. The main peculiarity of test facility, which is constructed to apply the tensometric method, consists in absence of any special deformation-measurement cell at all. The in-pile creep strain measurement technique developed at IPPE is based on the non-direct measurement of specimen's deformation (either linear tensile strain or angular twisting one), which directly affects the loaded draws' tension parameters. Starting from 1993, in-pile creep experiments to investigate in-reactor creep behaviour of E110 and E635 zirconium alloys were carried out in BR-10. Experimental results and data collected during more than 20-year of BR-10 in-reactor creep test experience can be assumed as a strong evidence that the tensometric technique is a powerful instrument, which can give a chance to study different irradiation effects on reactor materials directly under irradiation. (author)

  10. Results of FY 2002 of feasibility study on commercialized fast reactor cycle systems. Phase 2

    International Nuclear Information System (INIS)

    2003-06-01

    Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company (JAPC, that is the representative of the electric utilities in Japan) established a new organization to develop a commercialized fast reactor (FR) cycle system on July 1, 1999 and feasibility study (F/S) was undertaken in order to determine the promising concepts and to define the necessary R and D tasks. During Phase 1 (JFY 1999 and 2000), a number of candidate concepts were screened from various options, featuring innovative technologies. In the F/S, the options were evaluated and conceptual designs were examined considering the attainable perspectives for following: 1) ensuring safety, 2) economic competitiveness to future LWRs, 3) efficient utilization of resources, 4) reduction of environmental burden and 5) enhancement of nuclear non-proliferation. The F/S should also guide the necessary R and D to commercialize FR cycle system. To begin with the study of feasible candidate concepts screened in Phase I, Phase 2 started in the plan for five years in 2001. This aims at clarifying several feasible candidate concepts and deciding the research plan after Phase 3 as taking into consideration the innovative technology. As for this plan, an interim report will be carried out in 2003 as one pause and the prospect to clarify the feasible candidates will be expected. Furthermore, after the completion of this research and investigation program, research and development activities will be carried out under a rolling plan in which reviews will be carried out approximately every five years. The objective of these R and D activities is to make a proposal regarding highly attractive and competitive FR cycle system technology that assures safety by 2015. This report summarizes the results of F/S of Phase 2 in 2002. In 2002, the second year of Phase 2, the study was advanced along with the plan which was evaluated by the committee for the Evaluation. Then, in the study of FR system and fuel cycle

  11. Development of a 10-decade single-mode reactor flux monitoring system

    International Nuclear Information System (INIS)

    Valentine, K.H.; Shepard, R.L.; Falter, K.G.; Reese, W.B.

    1988-01-01

    Conventional wide-range neutron channels employ three optional modes to monitor the required flux range from source levels to full power (typically 10 or more decades). Difficult calibrations are necessary to provide a continuous output signal when such a system switches from counting mode in the source range to mean-square voltage mode in the midrange to dc current mode in the power range. In an ORNL proof-of-principle test, a method of extended range counting was implemented with a fission counter and conventional wide-band pulse processing electronics to provide a single-mode, monotonically increasing signal that spanned /approximately 10/ decades of neutron flux. Ongoing work includes design, fabrication, and testing of a comlpete neutron flux monitoring system suitable for advanced liquid metal reactor designs. 6 refs., 4 figs

  12. Depleted Reactor Analysis With MCNP-4B

    International Nuclear Information System (INIS)

    Caner, M.; Silverman, L.; Bettan, M.

    2004-01-01

    Monte Carlo neutronics calculations are mostly done for fresh reactor cores. There is today an ongoing activity in the development of Monte Carlo plus burnup code systems made possible by the fast gains in computer processor speeds. In this work we investigate the use of MCNP-4B for the calculation of a depleted core of the Soreq reactor (IRR-1). The number densities as function of burnup were taken from the WIMS-D/4 cell code calculations. This particular code coupling has been implemented before. The Monte Carlo code MCNP-4B calculates the coupled transport of neutrons and photons for complicated geometries. We have done neutronics calculations of the IRR-1 core with the WIMS and CITATION codes in the past Also, we have developed an MCNP model of the IRR-1 standard fuel for a criticality safety calculation of a spent fuel storage pool

  13. Extensions of the MCNP5 and TRIPOLI4 Monte Carlo Codes for Transient Reactor Analysis

    Science.gov (United States)

    Hoogenboom, J. Eduard; Sjenitzer, Bart L.

    2014-06-01

    To simulate reactor transients for safety analysis with the Monte Carlo method the generation and decay of delayed neutron precursors is implemented in the MCNP5 and TRIPOLI4 general purpose Monte Carlo codes. Important new variance reduction techniques like forced decay of precursors in each time interval and the branchless collision method are included to obtain reasonable statistics for the power production per time interval. For simulation of practical reactor transients also the feedback effect from the thermal-hydraulics must be included. This requires coupling of the Monte Carlo code with a thermal-hydraulics (TH) code, providing the temperature distribution in the reactor, which affects the neutron transport via the cross section data. The TH code also provides the coolant density distribution in the reactor, directly influencing the neutron transport. Different techniques for this coupling are discussed. As a demonstration a 3x3 mini fuel assembly with a moving control rod is considered for MCNP5 and a mini core existing of 3x3 PWR fuel assemblies with control rods and burnable poisons for TRIPOLI4. Results are shown for reactor transients due to control rod movement or withdrawal. The TRIPOLI4 transient calculation is started at low power and includes thermal-hydraulic feedback. The power rises about 10 decades and finally stabilises the reactor power at a much higher level than initial. The examples demonstrate that the modified Monte Carlo codes are capable of performing correct transient calculations, taking into account all geometrical and cross section detail.

  14. Extensions of the MCNP5 and TRIPOLI4 Monte Carlo codes for transient reactor analysis

    International Nuclear Information System (INIS)

    Hoogenboom, J.E.

    2013-01-01

    To simulate reactor transients for safety analysis with the Monte Carlo method the generation and decay of delayed neutron precursors is implemented in the MCNP5 and TRIPOLI4 general purpose Monte Carlo codes. Important new variance reduction techniques like forced decay of precursors in each time interval and the branch-less collision method are included to obtain reasonable statistics for the power production per time interval. For simulation of practical reactor transients also the feedback effect from the thermal-hydraulics must be included. This requires the coupling of the Monte Carlo code with a thermal-hydraulics (TH) code, providing the temperature distribution in the reactor, which affects the neutron transport via the cross section data. The TH code also provides the coolant density distribution in the reactor, directly influencing the neutron transport. Different techniques for this coupling are discussed. As a demonstration a 3*3 mini fuel assembly with a moving control rod is considered for MCNP5 and a mini core existing of 3*3 PWR fuel assemblies with control rods and burnable poisons for TRIPOLI4. Results are shown for reactor transients due to control rod movement or withdrawal. The TRIPOLI4 transient calculation is started at low power and includes thermal-hydraulic feedback. The power rises about 10 decades and finally stabilises the reactor power at a much higher level than initial. The examples demonstrate that the modified Monte Carlo codes are capable of performing correct transient calculations, taking into account all geometrical and cross section detail. (authors)

  15. Validation of SCALE4.4a for Calculation of Xe-Sm Transients After a Scram of the BR2 Reactor

    International Nuclear Information System (INIS)

    Kalcheva, S.; Ponsard, B.; Koonen, E.

    2007-01-01

    The aim of this report is to validate the computational modules system SCALE4.4a for evaluation of reactivity changes, macroscopic absorption cross sections and calculations of the positions of the Control Rods during their motion in Xe-Sm transient after a scram of the BR-2 reactor. The rapid shutting down of the reactor by inserting of negative reactivity by the Control Rods is known as a reactor scram. Following reactor scram, a large xenon and samarium buildup occur in the reactor, which may appreciably affect the multiplication factor of the core due to enormous neutron absorption. The validation of the calculations of Xe-Sm transients by SCALE4.4a has been performed on the measurements of the positions of the Control Rods during their motion in Xe-Sm transients of the BR-2 reactor and on comparison with the calculations by the standard procedure XESM, developed at the BR-2 reactor. A final conclusion is made that the SCALE4.4a modules system can be used for evaluation of Xe-Sm transients of the BR-2 reactor. The utilization of the code is simple, the computational time takes from few seconds.

  16. BiFS-based approaches to remote display for mobile thin clients

    Science.gov (United States)

    Mitrea, M.; Simoens, P.; Joveski, B.; Marshall, J.; Taguengayte, A.; Prêteux, F.; Dhoed, B.

    2009-08-01

    Under the framework of the FP-7 European MobiThin project, the present study addresses the issue of remote display representation for mobile thin client. The main issue is to design a compressing algorithm for heterogeneous content (text, graphics, image and video) with low-complex decoding. As a first step in this direction, we propose a novel software architecture, based on BiFS - Binary Format for Scenes (MPEG-4 Part 11). On the server side, the graphical content is parsed, converted and binary encoded into the BiFS format. This content is then streamed to the terminal, where it is played on a simple MPEG player. The viability of this solution is validated by comparing it to the most intensively used wired solutions, e.g. VNC - Virtual Network Computing.

  17. A Temperature Dependent Lumped-charge Model for Trench FS-IGBT

    DEFF Research Database (Denmark)

    Duan, Yaoqiang; Kang, Yong; Iannuzzo, Francesco

    2018-01-01

    Abstract: This paper proposes a temperature dependent lumped-charge model for FS-IGBT. Due to the evolution of the IGBT structure, the existing lumped-charge IGBT model established for NPT-IGBT is not suitable for the simulation of FS-IGBT. This paper extends the lumped-charge IGBT model including...... the field-stop (FS) structure and temperature characteristics. The temperature characteristics of the model are considered for both the bipolar part and unipolar part. In addition, a new PN junction model which can distinguish the collector structure is presented and validated by TCAD simulation. Finally...

  18. [Molecular pathogenesis of Waardenburg syndrome type II resulting from SOX10 gene mutation].

    Science.gov (United States)

    Zhang, Hua; Chen, Hongsheng; Feng, Yong; Qian, Minfei; Li, Jiping; Liu, Jun; Zhang, Chun

    2016-08-01

    To explore the molecular mechanism of Waardenburg syndrome type II (WS2) resulting from SOX10 gene mutation E248fs through in vitro experiment. 293T cells were transiently transfected with wild type (WT) SOX10 and mutant type (MT) E248fs plasmids. The regulatory effect of WT/MT SOX10 on the transcriptional activity of MITF gene and influence of E248fs on WT SOX10 function were determined with a luciferase activity assay. The DNA binding capacity of the WT/MT SOX10 with the promoter of the MITF gene was determined with a biotinylated double-stranded oligonucleotide probe containing the SOX10 binding sequence cattgtc to precipitate MITF and E248fs, respectively. The stability of SOX10 and E248fs were also analyzed. As a loss-of-function mutation, the E248fs mutant failed to transactivate the MITF promoter as compared with the WT SOX10 (P<0.01), which also showed a dominant-negative effect on WT SOX10. The WT SOX10 and E248fs mutant were also able to bind specifically to the cattgtc motif in the MITF promoter, whereas E248fs had degraded faster than WT SOX10. Despite the fact that the E248fs has a dominant-negative effect on SOX10, its reduced stability may down-regulate the transcription of MITF and decrease the synthesis of melanin, which may result in haploinsufficiency of SOX10 protein and cause the milder WS2 phenotype.

  19. InterProScan Result: FS906632 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS906632 FS906632_3_ORF2 2C529C8D33AE78A2 PFAM PF07962 Swi3 1e-25 T IPR012923 Replication fork protection...to DNA damage stimulus (GO:0006974)|Biological Process: cell cycle (GO:0007049)|Biological Process: replication fork protection (GO:0048478) ...

  20. InterProScan Result: FS932674 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS932674 FS932674_3_ORF2 C43825172FE72B67 PFAM PF00067 p450 0.00014 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  1. Enthalpy increment measurements of Sr3Zr2O7(s) and Sr4Zr3O10(s)

    International Nuclear Information System (INIS)

    Banerjee, A.; Dash, S.; Prasad, R.; Venugopal, V.

    1998-01-01

    Enthalpy increment measurements on Sr 3 Zr 2 O 7 (s) and Sr 4 Zr 3 O 10 (s) were carried out using a Calvet micro-calorimeter. The enthalpy increment values were least squares analyzed with the constraints that H 0 (T)-H 0 (298.15 K) at 298.15 K equals to zero and C p 0 (298.15 K) equals to the estimated value. The dependence of enthalpy increment with temperature is given. (orig.)

  2. High incidence of rainbow glare after femtosecond laser assisted-LASIK using the upgraded FS200 femtosecond laser.

    Science.gov (United States)

    Zhang, Yu; Chen, Yue-Guo

    2018-03-05

    To compare the incidence of rainbow glare (RG) after femtosecond laser assisted-LASIK (FS-LASIK) using the upgraded FS200 femtosecond laser with different flap cut parameter settings. A consecutive series of 129 patients (255 eyes) who underwent FS-LASIK for correcting myopia and/or astigmatism using upgraded WaveLight FS200 femtosecond laser with the original settings was included in group A. Another consecutive series of 129 patients (255 eyes) who underwent FS-LASIK using upgraded WaveLight FS200 femtosecond laser with flap cut parameter settings changed (decreased pulse energy, spot and line separation) was included in group B. The incidence and fading time of RG, confocal microscopic image and postoperative clinical results were compared between the two groups. There were no differences between the two groups in age, baseline refraction, excimer laser ablation depth, postoperative uncorrected visual acuity and refraction. The incidence rate of RG in group A (35/255, 13.73%) was significantly higher than that in group B (4/255, 1.57%) (P  0.05).The confocal microscopic images showed wider laser spot spacing in group A than group B. The incidence of RG was significantly correlated with age and grouping (P laser with original flap cut parameter settings could increase the incidence of RG. The narrower grating size and lower pulse energy could ameliorate this side effect.

  3. InterProScan Result: FS858611 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS858611 FS858611_5_ORF1 E15CFA5CC72259B8 PRINTS PR00385 P450 7.7e-06 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  4. InterProScan Result: FS828147 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828147 FS828147_5_ORF1 7B963168B4634A1D PRINTS PR00385 P450 2.3e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  5. InterProScan Result: FS828147 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS828147 FS828147_5_ORF1 7B963168B4634A1D PFAM PF00067 p450 1.3e-61 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  6. InterProScan Result: FS793798 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS793798 FS793798_2_ORF2 AF822AAC581E0462 PFAM PF00067 p450 1.8e-29 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  7. InterProScan Result: FS760705 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS760705 FS760705_3_ORF2 BCE542E7B7154334 PFAM PF00067 p450 6.5e-36 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  8. InterProScan Result: FS733119 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS733119 FS733119_3_ORF1 FBEF91F3CDA644D7 PRINTS PR00385 P450 1.7e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  9. Twenty years of Radiology in RP-10 nuclear reactor protection

    International Nuclear Information System (INIS)

    Zapata, Alejandro L.; Ramos, Fernando T.; Arrieta, Rolando W.B.; Vela Mora, Mariano

    2013-01-01

    In this report we present the results about radiation controls during 1990 - 2010, carried out in the Nuclear Reactor RP-10 of the Nuclear Center of Huarangal. These controls and radiological evaluation are of much utility for the radio personnel protection of this one and other reactors, since it allows to compares these variables with respect to the time. From the results obtained in monitoring and radiation controls, we conclude that in no case it has been reached the limits allowed by the Peruvian Regulating Authority. (author)

  10. Development of 4S and related technologies. (3) Statistical evaluation of safety performance of 4S on ULOF event

    International Nuclear Information System (INIS)

    Ishii, Kyoko; Matsumiya, Hisato; Horie, Hideki; Miyagi, Kazumi

    2009-01-01

    The purpose of this work is to evaluate quantitatively and statistically the safety performance of Super-Safe, Small, and Simple reactor (4S) by analyzing with ARGO code, a plant dynamics code for a sodium-cooled fast reactor. In this evaluation, an Anticipated Transient Without Scram (ATWS) is assumed, and an Unprotected Loss of Flow (ULOF) event is selected as a typical ATWS case. After a metric concerned with safety design is defined as performance factor a Phenomena Identification Ranking Table (PIRT) is produced in order to select the plausible phenomena that affect the metric. Then a sensitivity analysis is performed for the parameters related to the selected plausible phenomena. Finally the metric is evaluated with statistical methods whether it satisfies the given safety acceptance criteria. The result is as follows: The Cumulative Damage Fraction (CDF) for the cladding is defined as a metric, and the statistical estimation of the one-sided upper tolerance limit of 95 percent probability at a 95 percent confidence level in CDF is within the safety acceptance criterion; CDF < 0.1. The result shows that the 4S safety performance is acceptable in the ULOF event. (author)

  11. Preliminary assessment of an S.G.H.W. type research reactor

    International Nuclear Information System (INIS)

    Bicevskis, A.; Chapman, A.G.; Hesse, E.W.

    1970-08-01

    A preliminary design study has been made of a research reactor, based on the enriched S.G.H.W.R. concept, to be used for power reactor fuel irradiation, isotope production, basic research, and training in nuclear technology. A reactor physics assessment established a core size which would allow uninterrupted operation for the required irradiation period consistent with low capital and operating costs. A design was selected with 24 channels, a D 2 O calandria diameter of 2.7 m and an overall core height of 4.0 m. The capital cost was estimated as $750,000 for the fuel and $1,600,000 for the moderator, the refuelling cost being $340,000 per annum. A thermal design study showed that the fission heat of 65 MW could be transmitted to pressurised light water at 200 lb/in 2 abs. and rejected to sea water in two conventional U-tube heat exchangers. The basic design is flexible and can be adapted to meet many special requirements. (author)

  12. Immunohistochemical Localization of the Water Channels AQP4 and AQP5 in the Rat Pituitary Gland

    International Nuclear Information System (INIS)

    Matsuzaki, Toshiyuki; Inahata, Yuki; Sawai, Nobuhiko; Yang, Chun-Ying; Kobayashi, Makito; Takata, Kuniaki; Ozawa, Hitoshi

    2011-01-01

    The pituitary gland is composed of the adenohypophysis and neurohypophysis. The adenohypophysis contains endocrine cells, folliculo-stellate (FS) cells, and marginal layer cells, whereas the neurohypophysis mainly comprises axons and pituicytes. To understand the molecular nature of water transfer in the pituitary gland, we examined the immunohistochemical localization of the membrane water channels aquaporin-4 (AQP4) and AQP5 in rat tissue. Double immunofluorescence analysis of AQP4 and S100 protein, a known marker for FS cells, marginal layer cells, and pituicytes, clearly revealed that FS cells and marginal layer cells in the adenohypophysis and the pituicytes in pars nervosa are positive for AQP4. AQP5 was found to be localized at the apical membrane in some marginal layer cells surrounding the Rathke’s residual pouch, in which AQP4 was observed to be localized on the basolateral membranes. These results suggest the following possibilities: 1) FS cells especially require water for their functions and 2) transepithelial water transfer could occur between the lumen of Rathke’s residual pouch and the interstitial fluid in the adenohypophysis through the AQP4 and AQP5 channels in the marginal layer cells

  13. Scale analysis of decay heat removal system between HTR-10 and HTR-PM reactors under accidental conditions

    International Nuclear Information System (INIS)

    Roberto, Thiago D.; Alvim, Antonio C.M.

    2017-01-01

    The 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and accidental conditions. In addition, one of the systems responsible for ensuring the safe operation of this type of reactor is the passive decay heat removal system (DHRS), which operates using passive heat removal processes. A demonstration of the heat removal capacity of the DHRS under accidental conditions was analyzed based on a benchmark problem for design-based accidents on an HTR-10, i.e., the pressurized loss of forced cooling (PLOFC) described in technical reports produced by the International Atomic Energy Agency. In fact, the HTR-10 is also a proof-of-concept reactor for the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), which generates approximately 25 times more heat than the HTR-10, with a thermal power of 250 MW, thereby requiring a DHRS with a higher system capacity. Thus, because an HTR-10 is a prototype reactor for an HTR-PM, a scaling analysis of the heat transfer process from the reactor to the DHRS was carried out between the HTR-10 and HTR-PM systems to verify the distortions of scale and the differences between the main dimensionless numbers from the two projects. (author)

  14. Scale analysis of decay heat removal system between HTR-10 and HTR-PM reactors under accidental conditions

    Energy Technology Data Exchange (ETDEWEB)

    Roberto, Thiago D.; Alvim, Antonio C.M. [Coordenacao de Pos-Graduacao e Pesquisa de Engenharia (PEN/COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Nuclear; Lapa, Celso M.F., E-mail: thiagodbtr@gmail.com, E-mail: lapa@ien.gov.br, E-mail: alvim@nuclear.ufrj.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

    2017-07-01

    The 10 MW high-temperature gas-cooled test module (HTR-10) is a graphite-moderated and helium-cooled pebble bed reactor prototype that was designed to demonstrate the technical and safety feasibility of this type of reactor project under normal and accidental conditions. In addition, one of the systems responsible for ensuring the safe operation of this type of reactor is the passive decay heat removal system (DHRS), which operates using passive heat removal processes. A demonstration of the heat removal capacity of the DHRS under accidental conditions was analyzed based on a benchmark problem for design-based accidents on an HTR-10, i.e., the pressurized loss of forced cooling (PLOFC) described in technical reports produced by the International Atomic Energy Agency. In fact, the HTR-10 is also a proof-of-concept reactor for the high-temperature gas-cooled reactor pebble-bed module (HTR-PM), which generates approximately 25 times more heat than the HTR-10, with a thermal power of 250 MW, thereby requiring a DHRS with a higher system capacity. Thus, because an HTR-10 is a prototype reactor for an HTR-PM, a scaling analysis of the heat transfer process from the reactor to the DHRS was carried out between the HTR-10 and HTR-PM systems to verify the distortions of scale and the differences between the main dimensionless numbers from the two projects. (author)

  15. Calculations of fuel burn up and radionuclide inventories in the Syrian miniature neutron source reactor using the WIMSD4 and CITATION codes

    International Nuclear Information System (INIS)

    Khattab, K.

    2005-01-01

    The WIMSD4 code is used to generate the fuel group constants and the infinite multiplication factor as a function of the reactor operating time for 10, 20, and 30 k W operating power levels. The uranium burn up rate and burn up percentage, the amounts of the plutonium isotopes, the concentrations and radioactivities of the fission products and actinide radionuclides accumulated in the reactor core, and the total radioactivity of the reactor core are calculated using the WIMSD4 code as well. The CITATION code is used to calculate the changes in the effective multiplication factor of the reactor.(author)

  16. InterProScan Result: FS829494 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS829494 FS829494_5_ORF1 A59F385AE3D6656D PRINTS PR00385 P450 3.5e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  17. InterProScan Result: FS804057 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available FS804057 FS804057_2_ORF1 F65DFC6DB9EB6E59 PFAM PF00067 p450 1.6e-13 T IPR001128 Cytochrome P450 Molecular... Function: monooxygenase activity (GO:0004497)|Molecular Function: iron ion binding (GO:0005506)|Molecular... Function: electron carrier activity (GO:0009055)|Molecular Function: heme binding (GO:0020037) ...

  18. CFD for Nuclear Reactor Safety Applications (CFD4NRS-4) - Workshop Proceedings

    International Nuclear Information System (INIS)

    2014-01-01

    Following the CFD4NRS workshops held in Garching, Germany (Sept. 2006), Grenoble, France (Sep. 2008) and Washington D.C., USA (Sept. 2010), this Workshop is intended to extend the forum created for numerical analysts and experimentalists to exchange information in the application of CFD and CMFD to NRS issues and in guiding nuclear reactor design thinking. The workshop includes single-phase and multi-phase CFD applications, and offers the opportunity to present new experimental data for CFD validation. More emphasis has been given to the experiments, especially on two-phase flow, for advanced CMFD modelling for which sophisticated measurement techniques are required. Understanding of the physics has been depen before starting numerical analysis. Single-phase and multi-phase CFD simulations with a focus on validation were performed in areas such as: single-phase heat transfer, boiling flows, free-surface flows, direct contact condensation and turbulent mixing. These relate to NRS-relevant issues, such as pressurised thermal shock, critical heat flux, pool heat exchangers, boron dilution, hydrogen distribution in containments, thermal striping, etc. The use of systematic error quantification and the application of BPGs were strongly encouraged. Experiments providing data suitable for CFD or CMFD validation were also presented. These included local measurements using multi-sensor probes, laser-based techniques (LDV, PIV or LIF), hot-film/wire anemometry, imaging, or other advanced measuring techniques. There were over 150 registered participants at the CFD4NRS-4 workshop. The programme consisted of 48 technical papers. Of these, 44 were presented orally and 4 as posters. An additional 8 posters related to the OECD/NEA-KAERI sponsored CFD benchmark exercise on turbulent mixing in a rod bundle with spacers (MATiS-H) were presented and a special session was allocated for 6 video presentations. In addition, five keynote lectures were given by distinguished experts. The

  19. Relevant safety issues in designing the HTR-10 reactor

    International Nuclear Information System (INIS)

    Sun Yuliang; Xu Yuanghui

    2001-01-01

    The HTR-10 is a 10 MWth pebble bed high temperature gas cooled reactor being constructed as a research facility at the Institute of Nuclear Energy Technology. This paper discusses design issues of the HTR-10 which are related to safety. It addresses the safety criteria used in the development and assessment of the design, the safety important systems, and the safety classification of components. It also summarises the results of safety analysis, including the approach used for the radioactive source term, as well as the approach to containment design. (author)

  20. Effect of relative position of the control rods in the power calibration of the running chains of the RP-10 nuclear reactor

    International Nuclear Information System (INIS)

    Zuniga, Agustin; Arrieta, Rolando

    2014-01-01

    The monitoring of the thermal power levels of an experimental nuclear reactor, such as the RP-10 reactor is performed by current levels reported by the driving chains and their correlation with the power. The calibration curves for each channel will depend on the neutron distribution observed for the corresponding configuration. One way to modify this configuration is positioning the control rods that can be chosen according to the convenience of providing greater neutron flux in a given irradiation position. This article shows this variation, and consequently the current power curves corresponding thereto. We have chosen two relative positions of the control rods (BC1 and BC2), the first is the one that favors the production of radioisotopes (PPR) (Case 1) and the second favors the use of neutron activation (NAA) (Case 2). The used method was based on the record of the current (up camera, M4) by the acquisition system (SAD) of the reactor and the power from the digital reading of nitrogen 16, which was previously calibrated by thermal balance. The results for the nuclear configuration 30, M4 chain up were: Case 1: I M4 (A) = 2.95 x 10 -6 x P (MW) + 1.45 x 10 -6 R 2 = 9.99 x 10 -1 and Case 2: I M4 (A) = 2.39 x 10 -6 x P (MW) + 5.73 x 10 -7 , R 2 = 9.97 x 10 -1 . The dispersions of the data are in the order of 10 % for low power (under 2 MW), decreasing as the power rises to under 3 % (for values greater than 3 MW). (authors).

  1. Implementation of EAM and FS potentials in HOOMD-blue

    Science.gov (United States)

    Yang, Lin; Zhang, Feng; Travesset, Alex; Wang, Caizhuang; Ho, Kaiming

    HOOMD-blue is a general-purpose software to perform classical molecular dynamics simulations entirely on GPUs. We provide full support for EAM and FS type potentials in HOOMD-blue, and report accuracy and efficiency benchmarks, including comparisons with the LAMMPS GPU package. Two problems were selected to test the accuracy: the determination of the glass transition temperature of Cu64.5Zr35.5 alloy using an FS potential and the calculation of pair distribution functions of Ni3Al using an EAM potential. In both cases, the results using HOOMD-blue are indistinguishable from those obtained by the GPU package in LAMMPS within statistical uncertainties. As tests for time efficiency, we benchmark time-steps per second using LAMMPS GPU and HOOMD-blue on one NVIDIA Tesla GPU. Compared to our typical LAMMPS simulations on one CPU cluster node which has 16 CPUs, LAMMPS GPU can be 3-3.5 times faster, and HOOMD-blue can be 4-5.5 times faster. We acknowledge the support from Laboratory Directed Research and Development (LDRD) of Ames Laboratory.

  2. Etude de l'anémie chez les enfants séropositifs au VIH naïfs au traitement antirétroviral à Lubumbashi, République Démocratique du Congo

    Science.gov (United States)

    Mwadianvita, Costa Kazadi; Ilunga, Eric Kasamba; Djouma, Jackson; Wembonyama, Cecile Watu; Mutomb, Florence Mujing A; Ekwalanga, Michel Balaka; Kabongo, Joe; Mundongo, Henri; Mupoya, Kalombo; Wembonyama, Stanis; Kalenga Mwenze, Prosper; Nkoy, Albert Mwembo-Tambwe A

    2014-01-01

    Introduction Beaucoup d'enfants infectés par le VIH arrivent à la consultation dans un état d'anémie. Notre objectif était d’évaluer la prévalence et le typage de l'anémie chez ces enfants. Méthodes C'est une étude transversale réalisée dans 3 centres de prise en charge des Personnes Vivant avec le VIH à Lubumbashi de Mai 2010 à Mai 2011. La population d’étude était de 152 enfants, âgés de 6 à 180 mois, naïfs au traitement antirétroviral. Les statistiques descriptives usuelles ont été utilisées. Résultats La prévalence globale de l'anémie (définie comme l'hémoglobine < 11g/dl) était de 69,1% (n=105) et 11,4% avaient une anémie sévère (Hg < 7,0 g/dl). Parmi eux, 16% ont été transfusés au moins 1 fois. L'anémie sévère était positivement associée au stade clinique de la maladie (p=0,02). L'anémie microcytaire était majoritaire dans les deux tranches d’âge. Elle était plus hypochrome chez les enfants en âge préscolaire soit 9,5% et plus normochrome en âge scolaire soit 15,2%. L'anémie normocytaire était plus normochrome dans les deux tranches d’âge soit 12,4% en âge préscolaire et 6,7% en âge scolaire. L'anémie macrocytaire était rare. Conclusion Environ sept enfants sur dix, âgés de moins de 15 ans infectés par le VIH naïfs au traitement antirétroviral dans notre milieu sont anémiques. L'anémie est corrélée à la sévérité de la maladie. Il est important d'associer une prise en charge nutritionnelle et corriger l'anémie avant une trithérapie antirétrovirale. PMID:25018796

  3. U.S. activities related to fast reactors and ADS

    International Nuclear Information System (INIS)

    Finck, Phillip J.

    2001-01-01

    , lower cost, and improved safety and proliferation resistance; Innovative nuclear plant design, manufacturing, construction, operation, maintenance and decommissioning technologies; Advanced nuclear fuels; and Relevant areas of fundamental science. In 2000, the US Fast Reactor and ADS programs include the EBR-II Electrometallurgical Treatment program, FFTF activities in view of a decision whether to restart or deactivate the facility, several NERI awards, and the Advanced Accelerators Applications program. A 10 year R and D plan concentrated on defining the key technologies to be used for transmutation of nuclear waste (plutonium, minor actinides and long lived fission products). This activity includes fuels development and performance testing, development and testing of dedicated separation technologies, design of transmutation systems, and materials and physics research. It is expected that after 10 years, suitable technologies will have been demonstrated for practical waste transmutation demonstration. The Accelerator Driven Test Facility (ADTF) will be built over 10 years. It will consist of a large proton linear accelerator (600MeV, 13mA), coupled to two testing stations; the Target and Multiplier Test Station will consist of a large (8MW) spallation target surrounded by test loops for materials and small amounts of fuels; the Sub Critical Multiplier (SCM) will consist of a 100MW subcritical fast reactor driven by a 4MW spallation target and will be used to demonstrate the safe and efficient operations of accelerator driven systems, and will serve to irradiate experimental fuels. The ADTF will serve as the principal test station for a Proof of Performance series of tests, to demonstrate the safety and operations of Accelerator Driven Systems, and to demonstrate efficient transmutation and recycling of minor actinides and long lived fission products

  4. SeaWiFS technical report series. Volume 26: Results of the SeaWiFS Data Analysis Round-Robin, July 1994 (DARR-1994)

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Siegel, David A.; Obrien, Margaret C.; Sorensen, Jen C.; Konnoff, Daniel A.; Brody, Eric A.; Mueller, James L.; Davis, Curtiss O.; Rhea, W. Joseph

    1995-01-01

    The accurate determination of upper ocean apparent optical properties (AOP's) is essential for the vicarious calibration of the sea-viewing wide field-of-view sensor (SeaWiFS) instrument and the validation of the derived data products. To evaluate the role that data analysis methods have upon values of derived AOP's, the first Data Analysis Round-Robin (DARR-94) workshop was sponsored by the SeaWiFS Project during 21-23 July, 1994. The focus of this intercomparison study was the estimation of the downwelling irradiance spectrum just beneath the sea surface, E(sub d)(0(sup -), lambda); the upwelling nadir radiance just beneath the sea surface, L(sub u)(0(sup -), lambda); and the vertical profile of the diffuse attenuation coefficient spectrum, K(sub d)(z, lambda). In the results reported here, different methodologies from four research groups were applied to an identical set of 10 spectroradiometry casts in order to evaluate the degree to which data analysis methods influence AOP estimation, and whether any general improvements can be made. The overall results of DARR-94 are presented in Chapter 1 and the individual methods of the four groups are presented in Chapters 2-5. The DARR-94 results do not show a clear winner among data analysis methods evaluated. It is apparent, however, that some degree of outlier rejection is required in order to accurately estimate L(sub u)(0(sup -), lambda) or E(sub d)(0(sup -), lambda). Furthermore, the calculation, evaluation and exploitation of confidence intervals for the AOP determinations needs to be explored. That is, the SeaWiFS calibration and validation problem should be recast in statistical terms where the in situ AOP values are statistical estimates with known confidence intervals.

  5. Kartini Research Reactor prospective studies for neutron scattering application

    International Nuclear Information System (INIS)

    Widarto

    1999-01-01

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

  6. Multipurpose research reactors

    International Nuclear Information System (INIS)

    1988-01-01

    The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

  7. Nuclear reactors situation in Japan after the major earthquake of March 11, 2011. March 15, 2011, 10:00 PM status; Situation des reacteurs nucleaires au Japon suite au seisme majeur survenu le 11 mars 2011 (15 mars 2011 - point a 22h00 heures)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2011-07-01

    This situation note is established according to the information gained on March 15, 2011, at 10:00 PM, by the crisis centre of the French institute of radiation protection and nuclear safety (IRSN). The situation of the reactors No. 1, 2, 3 and 4 and of the spent fuel pools of reactors No. 4, 5 and 6 of the Fukushima I site (Dai-ichi), of the reactors No. 1, 2, 3 and 4 of the Fukushima II site (Daini), and of the Onagawa and Tokai power plants is briefly presented with the progress of the accident management actions. (J.S.)

  8. UCN sources at external beams of thermal neutrons. An example of PIK reactor

    International Nuclear Information System (INIS)

    Lychagin, E.V.; Mityukhlyaev, V.A.; Muzychka, A.Yu.; Nekhaev, G.V.; Nesvizhevsky, V.V.; Onegin, M.S.; Sharapov, E.I.; Strelkov, A.V.

    2016-01-01

    We consider ultracold neutron (UCN) sources based on a new method of UCN production in superfluid helium ("4He). The PIK reactor is chosen as a perspective example of application of this idea, which consists of installing "4He UCN source in the beam of thermal or cold neutrons and surrounding the source with moderator-reflector, which plays the role of cold neutron (CN) source feeding the UCN source. CN flux in the source can be several times larger than the incident flux, due to multiple neutron reflections from the moderator–reflector. We show that such a source at the PIK reactor would provide an order of magnitude larger density and production rate than an analogous source at the ILL reactor. We estimate parameters of "4He source with solid methane (CH_4) or/and liquid deuterium (D_2) moderator–reflector. We show that such a source with CH_4 moderator–reflector at the PIK reactor would provide the UCN density of ~1·10"5 cm"−"3, and the UCN production rate of ~2·10"7 s"−"1. These values are respectively 1000 and 20 times larger than those for the most intense UCN user source. The UCN density in a source with D_2 moderator-reflector would reach the value of ~2·10"5 cm"−"3, and the UCN production rate would be equal ~8·10"7 s"−"1. Installation of such a source in a beam of CNs would slightly increase the density and production rate.

  9. 10 years Institute for Reactor Development

    International Nuclear Information System (INIS)

    1975-05-01

    Ten years ago the Institute of Reactor Development was founded. This report contains a review about the research work of the institute in these past ten years. The work was mainly performed within the framework of the Fast Breeder Project, the Nuclear Safety Project and Computer Aided Design. Especially the following topics are discussed: design studies for different fast breeder reactors, development works for fast breeders, investigations of central safety problems of sodium cooled breeder reactors (such as local and integral coolant disturbances and hypothetical accident analysis), special questions of light water reactor safety (such as dynamic stresses in pressure suppression systems and fuel rod behaviour under loss of coolant conditions), and finally computer application in various engineering fields. (orig.) [de

  10. The Core Flight System (cFS) Community: Providing Low Cost Solutions for Small Spacecraft

    Science.gov (United States)

    McComas, David; Wilmot, Jonathan; Cudmore, Alan

    2016-01-01

    In February 2015 the NASA Goddard Space Flight Center (GSFC) completed the open source release of the entire Core Flight Software (cFS) suite. After the open source release a multi-NASA center Configuration Control Board (CCB) was established that has managed multiple cFS product releases. The cFS was developed and is being maintained in compliance with the NASA Class B software development process requirements and the open source release includes all Class B artifacts. The cFS is currently running on three operational science spacecraft and is being used on multiple spacecraft and instrument development efforts. While the cFS itself is a viable flight software (FSW) solution, we have discovered that the cFS community is a continuous source of innovation and growth that provides products and tools that serve the entire FSW lifecycle and future mission needs. This paper summarizes the current state of the cFS community, the key FSW technologies being pursued, the development/verification tools and opportunities for the small satellite community to become engaged. The cFS is a proven high quality and cost-effective solution for small satellites with constrained budgets.

  11. Probing α-3(10) transitions in a voltage-sensing S4 helix.

    Science.gov (United States)

    Kubota, Tomoya; Lacroix, Jérôme J; Bezanilla, Francisco; Correa, Ana M

    2014-09-02

    The S4 helix of voltage sensor domains (VSDs) transfers its gating charges across the membrane electrical field in response to changes of the membrane potential. Recent studies suggest that this process may occur via the helical conversion of the entire S4 between α and 310 conformations. Here, using LRET and FRET, we tested this hypothesis by measuring dynamic changes in the transmembrane length of S4 from engineered VSDs expressed in Xenopus oocytes. Our results suggest that the native S4 from the Ciona intestinalis voltage-sensitive phosphatase (Ci-VSP) does not exhibit extended and long-lived 310 conformations and remains mostly α-helical. Although the S4 of NavAb displays a fully extended 310 conformation in x-ray structures, its transplantation in the Ci-VSP VSD scaffold yielded similar results as the native Ci-VSP S4. Taken together, our study does not support the presence of long-lived extended α-to-310 helical conversions of the S4 in Ci-VSP associated with voltage activation. Copyright © 2014 Biophysical Society. Published by Elsevier Inc. All rights reserved.

  12. FMDP reactor alternative summary report: Volume 4, Evolutionary LWR alternative

    International Nuclear Information System (INIS)

    1996-09-01

    Significant quantities of weapons-usable fissile materials [primarily plutonium and highly enriched uranium (HEU)] have become surplus to national defense needs both in the United States and Russia. These stocks of fissile materials pose significant dangers to national and international security. The dangers exist not only in the potential proliferation of nuclear weapons but also in the potential for environmental, safety, and health (ES ampersand H) consequences if surplus fissile materials are not properly managed. The purpose of this report is to provide schedule, cost, and technical information that will be used to support the Record of Process (ROD). Following the screening process, DOE/MD via its national laboratories initiated a more detailed analysis activity to further evaluate each of the ten plutonium disposition alternatives that survived the screening process. Three ''Alternative Teams,'' chartered by DOE and comprised of technical experts from across the DOE national laboratory complex, conducted these analyses. One team was chartered for each of the major disposition classes (borehole, immobilization, and reactors). During the last year and a half, the Fissile Materials Disposition Program (FMDP) Reactor Alternative Team (RxAT) has conducted extensive analyses of the cost, schedule, technical maturity, S ampersand S, and other characteristics of reactor-based plutonium disposition. The results of the RxAT's analyses of the existing LWR, CANDU, and partially complete LWR alternatives are documented in Volumes 1-3 of this report. This document (Volume 4) summarizes the results of these analyses for the ELWR-based plutonium disposition option

  13. Evaluation of Continuous Stirred Tank Reactor Performance by Using Radioisotope Tracer

    International Nuclear Information System (INIS)

    Noor Anis Kundari; Djoko Marjanto; Ardhani Dyah W

    2009-01-01

    Research on performance evaluation of continuous stirred tank reactor (CSTR) using radioisotope tracer has been carried out. The aim of research is to assess a validity of assumption that stirring or mixing process in a CSTR is perfect. In order to follow the flow dynamics process of the fluid in the reactor, I-131 was used. The reactor was equipped with four baffles. The fluid/water leaving the reactor was sampled at 13 up to 1393 seconds and analysed its I-131 concentration. The performance of CSTR is expressed as dispersed number (D/uL) as function of retention time and Reynolds number under axial dispersed model. The experimental result show that the relation between the dispersion number and retention time is D/uL = 9X10 -4 (t s * ) 2 - 6.9X10 -1 (t s * ) + 148 and the dispersion number and Reynolds number is D/uL = 65.7 e 0.0003/Re . The dispersion number obtained were much higher than 0.01 that in between 11.08 up to 21.4. That mean the mixing process occurred in the CSTR can be assumed to be ideal. (author)

  14. Fuel cladding mechanical properties for transient analysis

    International Nuclear Information System (INIS)

    Johnson, G.D.; Hunter, C.W.; Hanson, J.E.

    1976-01-01

    Out-of-pile simulated transient tests have been conducted on irradiated fast-reactor fuel pin cladding specimens at heating rates of 10 0 F/s (5.6 0 K/s) and 200 0 F/s (111 0 K/s) to generate mechanical property information for use in describing cladding behavior during off-normal events. Mechanical property data were then analyzed, applying the Larson-Miller Parameter to the effects of heating rate and neutron fluence. Data from simulated transient tests on TREAT-tested fuel pins demonstrate that Plant Protective System termination of 3$/s transients prevents significant damage to cladding. The breach opening produced during simulated transient testing is shown to decrease in size with increasing neutron fluence

  15. Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

    International Nuclear Information System (INIS)

    Ene, D.; Cepraga, D.G.

    2002-01-01

    The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

  16. 10 CFR 4.510 - Self-evaluation.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Self-evaluation. 4.510 Section 4.510 Energy NUCLEAR... Programs or Activities Conducted by the U.S. Nuclear Regulatory Commission § 4.510 Self-evaluation. (a) The... representing handicapped persons, to participate in the self-evaluation process by submitting comments (both...

  17. Efficiency and safety of OctreotidLong FS therapy in acromegaly patients

    Directory of Open Access Journals (Sweden)

    A V Dreval’

    2013-03-01

    Full Text Available Aim of this study was to investigate efficiency and safety of OctreotidLong FS in patients with acromegaly. Materials and methods. 41 patients with acromegaly (8 – de novo and 33 patients after different somato statin analogs treatment was treated OctreotidLong FS one injection in 28 days. Growth hormone (GH, Insulin like Growth Factor 1 (IFG1, fasting glucose (FG and HbA1c were assess after 3, 6 and 12 month of therapy. Results. We found out the decreasing of GH and IGF1 from 12,8 (8,0–82,7 mU/ml to 3,8 (1,6–13,8 mU/ml ( p < 0,05 and %IGF1 increasing (% IGF1 from 231 (150–286% to 9,5 (−26–111% ( p < 0,05 in 8 de novo acromegalic patients. We also revealed that IGF1 didn’t change and GH decreased after 3 month (33 patients, 6 month (22 patients and 12 month (8 patients of OctreotidLong FS treatment. We didn’t observed negative effect of OctreotidLong FS treatment to carbohydrate metabolism in patients with acromegaly. Conclusion. The therapy of OctreotidLong FS leads to induce successful control of GH and IGFI in 50% de novo patients and didn’t change the number of patients with control of acromegaly after another somato statin analogs treatment. Carbohydrate metabolism also didn’t change after OctreotidLong FS treatment.

  18. Control Rods in high-Flux Swimming-Pool Reactors; Les Barres de Controle dans les Piles Piscines a Haut Flux; Reguliruyushchie sterzhni dlya reaktorov bassejnovogo tipa s vysokoj plotnost'yu nejtronnogo potoka; Las Barras de Control en los Reactores Tipo Piscina de Flujo Elevado

    Energy Technology Data Exchange (ETDEWEB)

    Ageroni, P.; Blum, P.; Denielou, G.; Denis, P.; Meunier, C. [Centre d' Etudes Nucleaires de Grenoble (France)

    1964-06-15

    etudes en cours sur les barres de controle des piles piscine a coeur ouvert fonctionnant dans la bande de 10 a 30 MW. (author) [Spanish] La memoria examina los problemas planteados por las barras de control en los reactores de investigacion de tipo piscina abierta, de alta potencia especifica y elevado flujo, basandose en calculos y experimentos efectuados durante la construccion del reactor SILOE. Expone asimismo la experiencia adquirida con las barras de control mientras el reactor funcionaba a 13 MW. Examina sucesivamente: a) Los balances de reactividad y los valores de esta para los diversos tipos de barras de control que se han ensayado (cadmio, B4C, tierras raras, y combinaciones de estas sustancias); b) los picos de flujo que la presencia de barras de control crea en el cuerpo del reactor, su influencia sobre la potencia especifica, los flujos rapidos que se pueden obtener y los medios para incrementarlos; c) los problemas tecnologicos planteados por la construccion de las barras; d) los problemas de refrigeracion, vibracion, deformacion y tiempo necesario para introducirlos en el reactor. Para terminar, describe someramente loe estudios que se estan realizando con las barras de control de reactores de tipo piscina de cuerpo abierto cuando funcionan en el intervalo de potencias comprendido entre 10 y 30 MW. (author) [Russian] 1. V svete raschetov i jeksperimentov, provedennyh pri postrojke reaktora STLOE , rassmatrivajutsja problemy, voznikajushhie v svjazi s regulirujushhimi sterzhnjami dlja issledovatel'skih reaktorov otkrytogo bassejnovogo tipa s bol'shoj udel'noj moshhnost'ju i s vysokoj plotnost'ju nejtronnogo potoka. Privodjatsja takzhe rezul'taty ispytanija jetogo reaktora pri .moshhnosti 13 mgvt v svjazi s razlichnymi regulirujushhimi sterzhnjami. 2. Posledov atel'no rassmatrivajutsja sledujushhie problemy: a) balans reaktivnosti i reaktivnaja sposobnost' podvergnutyh ispytanijam regulirujushhih sterzhnej razlichnyh tipov (kadmij, B{sub 4}C , redkie zemli

  19. LTS and FS inhibitory interneurons, short-term synaptic plasticity, and cortical circuit dynamics.

    Directory of Open Access Journals (Sweden)

    Itai Hayut

    2011-10-01

    Full Text Available Somatostatin-expressing, low threshold-spiking (LTS cells and fast-spiking (FS cells are two common subtypes of inhibitory neocortical interneuron. Excitatory synapses from regular-spiking (RS pyramidal neurons to LTS cells strongly facilitate when activated repetitively, whereas RS-to-FS synapses depress. This suggests that LTS neurons may be especially relevant at high rate regimes and protect cortical circuits against over-excitation and seizures. However, the inhibitory synapses from LTS cells usually depress, which may reduce their effectiveness at high rates. We ask: by which mechanisms and at what firing rates do LTS neurons control the activity of cortical circuits responding to thalamic input, and how is control by LTS neurons different from that of FS neurons? We study rate models of circuits that include RS cells and LTS and FS inhibitory cells with short-term synaptic plasticity. LTS neurons shift the RS firing-rate vs. current curve to the right at high rates and reduce its slope at low rates; the LTS effect is delayed and prolonged. FS neurons always shift the curve to the right and affect RS firing transiently. In an RS-LTS-FS network, FS neurons reach a quiescent state if they receive weak input, LTS neurons are quiescent if RS neurons receive weak input, and both FS and RS populations are active if they both receive large inputs. In general, FS neurons tend to follow the spiking of RS neurons much more closely than LTS neurons. A novel type of facilitation-induced slow oscillations is observed above the LTS firing threshold with a frequency determined by the time scale of recovery from facilitation. To conclude, contrary to earlier proposals, LTS neurons affect the transient and steady state responses of cortical circuits over a range of firing rates, not only during the high rate regime; LTS neurons protect against over-activation about as well as FS neurons.

  20. Theory of superconducting spintronic SIsFS devices

    International Nuclear Information System (INIS)

    Bakurskiy, S.V.; Klenov, N.V.; Soloviev, I.I.; Kupriyanov, M.Yu.; Bol'ginov, V.V.; Ryazanov, V.V.; Vernik, I.V.; Mukhanov, O.A.; Golubov, A.A.

    2013-01-01

    Full text: Motivated by recent progress in developments of cryogenic memory compatible with single flux quantum (SFQ) circuits we have performed a theoretical study of magnetic SIsFS Josephson junctions, where 'S' is a bulk superconductor, 's' is a thin superconducting film, 'F' is a metallic ferromagnet and 'I' is an insulator. We calculate the Josephson current as a function of s and F layers thickness, temperature and exchange energy of F film. We outline several modes of operation of these junctions and demonstrate their unique ability to have high I C R N product in the π-state, comparable to that in SIS tunnel junctions commonly used in SFQ circuits. We develop a model describing switching of the Josephson critical current in these devices by external magnetic field. The results are in good agreement with the experimental data for Nb-Al/AlOx-Nb-Pd0:99Fe0:01-Nb junctions. This work is supported by RFBR No. 12-02-90010-Bel a .

  1. 5,10,15,20-Tetrakis(4-carboxyl phenyl)porphyrin–CdS nanocomposites with intrinsic peroxidase-like activity for glucose colorimetric detection

    Energy Technology Data Exchange (ETDEWEB)

    Liu, Qingyun, E-mail: qyliu@sdust.edu.cn [School of Chemistry and Environmental Engineering, Shandong University of Science and Technology, Qingdao 266510 (China); Jia, Qingyan; Zhu, Renren; Shao, Qian; Wang, Dongmei; Cui, Peng [School of Chemistry and Environmental Engineering, Shandong University of Science and Technology, Qingdao 266510 (China); Ge, Jiechao, E-mail: jchge2010@mail.ipc.ac.cn [Technical Institute of Physics and Chemistry, Chinese Academy of Sciences, Beijing 100190 (China)

    2014-09-01

    Here, we describe the design of a novel mimic peroxidase, nanocomposites composed by 5,10,15,20-tetrakis(4-carboxyl phenyl)-porphyrin (H{sub 2}TCPP) and cadmium sulfide (CdS). The H{sub 2}TCPP–CdS nanocomposites can catalyze oxidation of substrate 3,3,5,5-tetramethylbenzidine (TMB) in the presence of H{sub 2}O{sub 2} and form a blue product which can be seen by the naked eye in 5 min. The mechanism of the catalytic reaction originated from the generation of hydroxyl radical (·OH), which is a powerful oxidizing agent to oxidize TMB to produce a blue product. Then, we developed a colorimetric method that is highly sensitive and selective to detect glucose, combined with glucose oxidase (GOx). The proposed method allowed the detection of H{sub 2}O{sub 2} concentration in the range of 4 × 10{sup −6}–1.4 × 10{sup −5} M and glucose in the range of 1.875 × 10{sup −5}–1 × 10{sup −4} M with detectable H{sub 2}O{sub 2} concentration as low as 4.6 × 10{sup −7} M and glucose as low as 7.02 × 10{sup −6} M, respectively. The results provided the theoretical basis of practical application in glucose detecting and peroxidase mimetic enzymes. - Graphical abstract: 5,10,15,20-tetrakis(4-carboxyl phenyl)-porphyrin (H{sub 2}TCPP)–CdS nanohybrids were demonstrated to possess intrinsic peroxidase-like activity and used for a glucose colorimetric sensor. - Highlights: • H{sub 2}TCPP–CdS nanocomposites were synthesized by a facile one step under mild condition. • H{sub 2}TCPP–CdS nanocomposites possess excellent intrinsic peroxidase-like activity. • A sensitive and selective colorimetric sensor for glucose is provided based on H{sub 2}TCPP–CdS nanocomposites. • The generation of hydroxyl radical (·OH) decomposed from H{sub 2}O{sub 2} is contributed to efficient catalytic.

  2. Jordan Research and Training Reactor (JRTR) Utilization Facilities

    International Nuclear Information System (INIS)

    Xoubi, N.

    2013-01-01

    Jordan Research and Training Reactor (JRTR) is a 5 MW light water open pool multipurpose reactor that serves as the focal point for Jordan National Nuclear Centre, and is designed to be utilized in three main areas: Education and training, nuclear research, and radioisotopes production and other commercial and industrial services. The reactor core is composed of 18 fuel assemblies, MTR plate type 19.75% enriched uranium silicide (U 3 Si 2 ) in aluminium matrix, and is reflected on all sides by beryllium and graphite. The reactor power is upgradable to 10 MW with a maximum thermal flux of 1.45×10 14 cm -2 s -1 , and is controlled by a Hafnium control absorber rod and B 4 C shutdown rod. The reactor is designed to include laboratories and classrooms that will support the establishment of a nuclear reactor school for educating and training students in disciplines like nuclear engineering, reactor physics, radiochemistry, nuclear technology, radiation protection, and other related scientific fields where classroom instruction and laboratory experiments will be related in a very practical and realistic manner to the actual operation of the reactor. JRTR is designed to support advanced nuclear research as well as commercial and industrial services, which can be preformed utilizing any of its 35 experimental facilities. (author)

  3. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2007

    International Nuclear Information System (INIS)

    2012-03-01

    In the fiscal year 2007, the research reactor JRR-3 was operated for 7 cycles (cycle operation : 26days/cycle) and the JRR-4 was operated for 92 days. JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment and practice in the nuclear reactor training, Irradiation for activation analyses, RI productions, fission tracks, etc. The volume contains 262 activity reports, which are categorized into the fields of neutron scattering (10 subcategories), neutron radiography, neutron activation analyses, prompt gamma-ray analyses, and others submitted by the users in JAEA and other Organizations. (author)

  4. Concentrations of trace elements and PCDD/Fs around a municipal solid waste incinerator in Girona (Catalonia, Spain). Human health risks for the population living in the neighborhood.

    Science.gov (United States)

    Rovira, Joaquim; Nadal, Martí; Schuhmacher, Marta; Domingo, José L

    2018-07-15

    Previously to the modernization of the municipal solid waste incinerator (MSWI) of Campdorà (Girona, Catalonia, Spain) two sampling campaigns (2015 and 2016) were conducted. In each campaign, 8 soil and 4 air samples (PM 10 and total particle phase and gas phase) were collected. The levels of As, Cd, Co, Cr, Cu, Hg, Mn, Ni, Pb, Sb, Sn, Tl and V, and PCDD/Fs were analysed at different distances and wind directions around the MSWI. Environmental levels of trace elements and PCDD/Fs were used to assess exposure and health risks (carcinogenic and non-carcinogenic) for the population living around the facility. In soils, no significant differences were observed for trace elements and PCDD/Fs between both campaigns. In air, significant higher levels of As, Cd, Co, Mn, Ni, Pb, Tl and V were detected in 2016. Regarding soil levels, only Cd (distances) and As, Cu, Mn, and Ni (wind directions) showed significant differences. No differences were noted in the concentrations of trace elements and PCDD/Fs in air levels with respect to distances and directions to the MSWI. No differences were registered in air levels (elements and PCDD/Fs) between points influenced by MSWI emissions and background point. However some differences in congener profile were noted regarding from where back-trajectories come from (HYSPLIT model results), pointing some influence of Barcelona metropolitan area. The concentrations of trace elements and PCDD/Fs were similar -or even lower- than those reported around other MSWIs in Catalonia and various countries. Non-carcinogenic risks were below the safety limit (HQ<1). In turn, carcinogenic risks due to exposure to trace elements and PCDD/Fs were in acceptable ranges, according to national and international standard regulations. Copyright © 2018 Elsevier B.V. All rights reserved.

  5. Effect of Co3O4 and CeO2 Infiltration on the Activity of a LSM15/GDC10 Highly Porous Electrochemical Reactor

    DEFF Research Database (Denmark)

    Ippolito, Davide; Kammer Hansen, Kent

    2014-01-01

    The reduction of air pollution has become an international concern over the last ten years because of increases in emissions from mobile and stationary sources. Among these sources, volatile organic compounds (VOC) represent a serious environmental problem, together with NOx, SOx and particulate...... VOC component of Diesel engine exhausts, over a wide range of temperatures. The entire reactor was thought as a highly porous catalytic filter for a possible application in a Diesel exhausts purification system. The porous reactor was used as a backbone for the infiltration of Co3O4 and Co3O4/CeO2...

  6. Optical Waveform Sampling and Error-Free Demultiplexing of 1.28 Tb/s Serial Data in a Nanoengineered Silicon Waveguide

    DEFF Research Database (Denmark)

    Ji, Hua; Pu, Minhao; Hu, Hao

    2011-01-01

    This paper presents the experimental demonstrations of using a pure nanoengineered silicon waveguide for 1.28 Tb/s serial data optical waveform sampling and 1.28 Tb/s–10 Gb/s error free demultiplexing. The 330-fs pulses are resolved in each 780-fs time slot in waveform sampling. Error...

  7. Study on in-vessel thermohydraulics phenomena of sodium-cooled fast reactors. 4. Numerical analysis of 1/10 scaled water experiment with the AQUA code

    International Nuclear Information System (INIS)

    Muramatu, Toshiharu; Yamaguchi, Akira

    2004-01-01

    A large-scale sodium-cooled fast breeder reactor in the feasibility studies on commercialized fast reactors has a feature of consideration of thorough simplified and compacted systems and components design to realize drastic economical improvements. Therefore, special attentions should be paid to thermohydraulic designs for gas entrainment behavior from free surface, flow-induced vibration of in-vessel components, thermal stratification in the plenum, thermal shock for various structures due to high-speed coolant flows, nonsymmetrical coolant flows, etc. in the reactor vessel. A numerical analysis was carried out with a multi-dimensional code AQUA to confirm an applicability to the evaluations for the in-vessel thermohydraulic phenomena using a 1/10 scaled water experiment simulating the large-scale fast breeder reactor in the feasibility studies. From the analysis, the following results were obtained. (1) In-vessel thermohydraulics characterized by a radiated flow pattern to the reactor vessel wall and a strong upward flow through a slit of the upper core structures were evaluated. These characteristics agreed approximately with the water experiment. (2) The upward velocity values at the slit agreed well with the experimental data under a condition of γ z = 0.3 and ξ z = 0.5, though overall evaluations of the in-vessel thermohydraulics were failed to predict quantitatively. (3) The AQUA code is applicable to the in-vessel thermohydraulics evaluations in the feasibility studies, though it is necessary to make further modifications of the calculational models for accurate evaluations. On the one hand, it was confirmed that calculated results for the 1/10 water experimental model and the 1/1 actual-scaled model agreed quantitatively for the in-vessel thermohydraulics characteristics indicated above. (author)

  8. Manila on CephFS at CERN

    CERN Document Server

    Wiebalck, Arne

    2017-01-01

    In response to the user demand for a light-weight provisioning of distributed file system shares, the OpenStack and Ceph teams at CERN have recently added Manila/CephFS to their service catalogues. While leveraging the operational experience with a 190'000 core OpenStack deployment and a 12 PB Ceph cluster for such a self-service kiosque suggested itself, the service design and setup phases were followed by a number of functionality and stress tests to ensure the individual components are ready for production use. The final service design and the results obtained during the pre-production phase, for instance when scaling to a large number of Manila and CephFS clients or the integration with Magnum/Kubernetes, will be presented alongside the initial use cases and our first experiences running these new services in production.

  9. An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Rosenthal, Murray Wilford [ORNL

    2009-08-01

    The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

  10. U.S. Status of Fast Reactor Research and Technology

    International Nuclear Information System (INIS)

    Hill, Robert

    2012-01-01

    Summary: • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction) and safety: 1. System Integration and Concept Development; 2. Safety Technology; 3. Advanced Materials; 4. Ultrasonic Viewing; 5. Advanced Energy Conversion (Supercritical CO 2 Brayton cycle); 6. Reactor Simulation; 7. Nuclear Data; 8. Advanced Fuels. • Fast reactors have flexible capability for actinide management: – A wide variety of fuel cycle options are being considered; • International R&D collaboration pursued in Generation-IV and multilateral arrangements

  11. FS laser processing of bio-polymer thin films for studying cell-to-substrate specific response

    Energy Technology Data Exchange (ETDEWEB)

    Daskalova, A., E-mail: a_daskalova@code.bg [Institute of Electronics, Bulgarian Academy of Sciences, 72, Tsarigradsko Chaussee Blvd., 1784 Sofia (Bulgaria); Nathala, Chandra S.R. [Institute of General Physics, Vienna University of Technology, Wiedner Hauptstr. 8-10/134, A-1040 Wien (Austria); Spectra-Physics Vienna, Fernkorngasse 10, 1100 Wien (Austria); Kavatzikidou, P.; Ranella, A. [Institute for Electronic Structure and Lasers-FORTH, P.O. Box 1385, Vassilika Vouton, 711 10 Heraklion, Crete (Greece); Szoszkiewicz, R. [Faculty of Materials Science and Engineering, Warsaw University of Technology, 141 Woloska Str., 02-507 Warsaw, Poland (Poland); Husinsky, W. [Institute of General Physics, Vienna University of Technology, Wiedner Hauptstr. 8-10/134, A-1040 Wien (Austria); Fotakis, C. [Institute for Electronic Structure and Lasers-FORTH, P.O. Box 1385, Vassilika Vouton, 711 10 Heraklion, Crete (Greece)

    2016-09-30

    Highlights: • Systematic research in the field of fs laser interaction with biopolymers for application in tissue engineering. • Utilizing a new biopolymer blend of collagen/elastin material for studying the interaction process in the fs domain. • Obtaining of improved, circularly shaped, interconnected nanopores, with high reproducibility from collagen/elastin layer. • Observation of randomly arranged pattern outside modification zone due to formation of an impact wave over biofilm surface. • NIH/3T3 cell-interface interaction reveal a preferable cell migration on fs laser-modified surface array. - Abstract: The use of ultra-short pulses for nanoengineering of biomaterials opens up possibilities for biological, medical and tissue engineering applications. Structuring the surface of a biomaterial into arrays with micro- and nanoscale features and architectures, defines new roadmaps to innovative engineering of materials. Thin films of novel collagen/elastin composite and gelatin were irradiated by Ti:sapphire fs laser in air at central wavelength 800 nm, with pulse durations in the range of 30 fs. The size and shape as well as morphological forms occurring in the resulted areas of interaction were analyzed as a function of irradiation fluence and number of pulses by atomic force microscopy (AFM). The fs interaction regime allows generation of well defined micro porous surface arrays. In this study we examined a novel composite consisting of collagen and elastin in order to create a biodegradable matrix to serve as a biomimetic surface for cell attachment. Confocal microscopy images of modified zones reveal formation of surface fringe patterns with orientation direction alongside the area of interaction. Outside the crater rim a wave-like topography pattern is observed. Structured, on a nanometer scale, surface array is employed for cell-culture experiments for testing cell’s responses to substrate morphology. Mice fibroblasts migration was monitored

  12. FS laser processing of bio-polymer thin films for studying cell-to-substrate specific response

    International Nuclear Information System (INIS)

    Daskalova, A.; Nathala, Chandra S.R.; Kavatzikidou, P.; Ranella, A.; Szoszkiewicz, R.; Husinsky, W.; Fotakis, C.

    2016-01-01

    Highlights: • Systematic research in the field of fs laser interaction with biopolymers for application in tissue engineering. • Utilizing a new biopolymer blend of collagen/elastin material for studying the interaction process in the fs domain. • Obtaining of improved, circularly shaped, interconnected nanopores, with high reproducibility from collagen/elastin layer. • Observation of randomly arranged pattern outside modification zone due to formation of an impact wave over biofilm surface. • NIH/3T3 cell-interface interaction reveal a preferable cell migration on fs laser-modified surface array. - Abstract: The use of ultra-short pulses for nanoengineering of biomaterials opens up possibilities for biological, medical and tissue engineering applications. Structuring the surface of a biomaterial into arrays with micro- and nanoscale features and architectures, defines new roadmaps to innovative engineering of materials. Thin films of novel collagen/elastin composite and gelatin were irradiated by Ti:sapphire fs laser in air at central wavelength 800 nm, with pulse durations in the range of 30 fs. The size and shape as well as morphological forms occurring in the resulted areas of interaction were analyzed as a function of irradiation fluence and number of pulses by atomic force microscopy (AFM). The fs interaction regime allows generation of well defined micro porous surface arrays. In this study we examined a novel composite consisting of collagen and elastin in order to create a biodegradable matrix to serve as a biomimetic surface for cell attachment. Confocal microscopy images of modified zones reveal formation of surface fringe patterns with orientation direction alongside the area of interaction. Outside the crater rim a wave-like topography pattern is observed. Structured, on a nanometer scale, surface array is employed for cell-culture experiments for testing cell’s responses to substrate morphology. Mice fibroblasts migration was monitored

  13. A basic design of SR4 instrumentation and control system for research reactor

    International Nuclear Information System (INIS)

    Syahrudin Yusuf; M Subhan; Ikhsan Shobari; Sutomo Budihardjo

    2010-01-01

    An SR4 instrumentation and control systems of research reactor is the equipment of nuclear research reactors as power protection devices and control systems. The equipment is to monitor safety parameters and process parameters in the state of reactor shut down, start-up, and in operation at fixed power. In the engineering of Instrumentation and control systems SR4 research reactor, its basic design consists of technical specifications of the reactor protection system devices, technical specifications of the reactor power control system devices, technical specifications information system devices, and systems process termination cabling as a support system. This basic design is used as the basis for the preparation of detailed design and subsequent engineering development of instrumentation systems and control system integrated. (author)

  14. Cross-sensor comparisons between Landsat 5 TM and IRS-P6 AWiFS and disturbance detection using integrated Landsat and AWiFS time-series images

    Science.gov (United States)

    Chen, Xuexia; Vogelmann, James E.; Chander, Gyanesh; Ji, Lei; Tolk, Brian; Huang, Chengquan; Rollins, Matthew

    2013-01-01

    Routine acquisition of Landsat 5 Thematic Mapper (TM) data was discontinued recently and Landsat 7 Enhanced Thematic Mapper Plus (ETM+) has an ongoing problem with the scan line corrector (SLC), thereby creating spatial gaps when covering images obtained during the process. Since temporal and spatial discontinuities of Landsat data are now imminent, it is therefore important to investigate other potential satellite data that can be used to replace Landsat data. We thus cross-compared two near-simultaneous images obtained from Landsat 5 TM and the Indian Remote Sensing (IRS)-P6 Advanced Wide Field Sensor (AWiFS), both captured on 29 May 2007 over Los Angeles, CA. TM and AWiFS reflectances were compared for the green, red, near-infrared (NIR), and shortwave infrared (SWIR) bands, as well as the normalized difference vegetation index (NDVI) based on manually selected polygons in homogeneous areas. All R2 values of linear regressions were found to be higher than 0.99. The temporally invariant cluster (TIC) method was used to calculate the NDVI correlation between the TM and AWiFS images. The NDVI regression line derived from selected polygons passed through several invariant cluster centres of the TIC density maps and demonstrated that both the scene-dependent polygon regression method and TIC method can generate accurate radiometric normalization. A scene-independent normalization method was also used to normalize the AWiFS data. Image agreement assessment demonstrated that the scene-dependent normalization using homogeneous polygons provided slightly higher accuracy values than those obtained by the scene-independent method. Finally, the non-normalized and relatively normalized ‘Landsat-like’ AWiFS 2007 images were integrated into 1984 to 2010 Landsat time-series stacks (LTSS) for disturbance detection using the Vegetation Change Tracker (VCT) model. Both scene-dependent and scene-independent normalized AWiFS data sets could generate disturbance maps similar to

  15. Reactor power cutback system test experience at YGN 4

    International Nuclear Information System (INIS)

    Chi, Sung Goo; Kim, Se Chang; Seo, Jong Tae; Eom, Young Meen; Wook, Jeong Dae; Choi, Young Boo

    1995-01-01

    YGN 3 and 4 are the nuclear power plants having System 80 characteristics with a rated thermal output of 2815 MWth and a nominal net electrical output of 1040 MWe. YGN 3 achieved commercial operation on March 31, 1995 and YGN 4 completed Power Ascension Test (PAT) at 20%, 50%, 80% and 100% power by September 23, 1995. YGN 3 and 4 design incorporates the Reactor POwer Cutback System (RPCS) which reduces plant trips caused by Loss of Load (LOL)/ Turbine Trip and Loss of One Main Feedwater Pump (LOMFWP). The key design objective of the RPCS is to improve overall plant availability and performance, while minimizing challenges to the plant safety systems. The RPCS is designed to rapidly reduce reactor power by dropping preselected Control Element Assemblies (CEAs) while other NSSS control systems maintain process parameters within acceptable ranges. Extensive RPCS related tests performed during the initial startup of YGN 4 demonstrated that the RPCS can maintain the reactor on-line without opening primary or secondary safety valves and without actuating the Engineered Safety Features Actuation System (ESFAS). It is expected that use of the RPCS at YGN will increase the overall availability of the units and reduce the number of challenges to plant safety systems

  16. Conceptual design of a mirror reactor for a fusion engineering research facility (FERF)

    International Nuclear Information System (INIS)

    Batzer, T.H.; Burleigh, R.C.; Carlson, G.A.; Dexter, W.L.; Hamilton, G.W.; Harvey, A.R.; Hickman, R.G.; Hoffman, M.A.; Hooper, E.B. Jr.; Moir, R.W.; Nelson, R.L.; Pittenger, L.C.; Smith, B.H.; Taylor, C.E.; Werner, R.W.; Wilcox, T.P.

    1975-01-01

    A conceptual design is presented for a small mirror fusion reactor for a Fusion Engineering Research Facility (FERF). The reactor produces 3.4 MW of fusion power and a useful neutron flux of about 10 14 n.cm -2 .s -1 . Superconducting ''yin-yang'' coils are used, and the plasma is sustained by injection of energetic neutral D 0 and T 0 . Conceptual layouts are given for the reactor, its major components, and supporting facilities. (author)

  17. Development of conceptual nuclear design of 10MWt research reactor core

    International Nuclear Information System (INIS)

    Kim, M. H.; Lim, J. Y.; Win, Naing; Park, J. M.

    2008-03-01

    KAERI has been devoted to develop export-oriented research reactors for a growing world-wide demand of new research reactor construction. Their ambition is that design of Korean research reactor must be competitive in commercial and technological based on the experience of the HANARO core design concept with thermal power of 30MW. They are developing a new research reactor named Advanced HANARO research Reactor (AHR) with thermal power of 20 MW. KAERI has export records of nuclear technology. In 1954-1967 two series of pool type research reactors based on the Russian design, VVR type and IRT type, have been constructed and commissioned in some countries as well as Russia. Nowadays Russian design is introducing again for export to developing countries such as Union of Myanmar. Therefore the objective of this research is that to build and innovative 10 MW research reactor core design based on the concept of HANARO core design to be competitive with Russian research reactor core design. system tool of HELIOS was used at the first stage in both cases which are research reactor using tubular type fuel assemblies and that reactor using pin type fuel assemblies. The reference core design of first kind of research reactor includes one in-core irradiation site at the core center. The neutron flux evaluations for core as well as reflector region were done through logical consistency of neutron flux distributions for individual assemblies. In order to find the optimum design, the parametric studies were carried out for assembly pitch, active fuel length, number of fuel ring in each assembly and so on. Design result shows the feasibility to have high neutron flux at in-core irradiation site. The second kind of research reactor is used the same kind of assemblies as HANARO and hence there is no optimization about basic design parameters. That core has only difference composition of assemblies and smaller specific power than HANARO. Since it is a reference core at first stage

  18. Quarterly technical progress report on water reactor safety programs sponsored by the Nuclear Regulatory Commission's Division of Reactor Safety Research, October--December 1975

    Energy Technology Data Exchange (ETDEWEB)

    1976-05-01

    Light water reactor safety activities performed during October--December 1975 are reported. The blowdown heat transfer tests series of the Semiscale Mod-1 test program was completed. In the LOFT Program, preparations were made for nonnuclear testing. The Thermal Fuels Behavior Program completed a power-cooling-mismatch test and an irradiation effects test on PWR-type fuel rods. Model development and verification efforts of the Reactor Behavior Program included developing new analysis models for the RELAP4 computer code, subroutines for the FRAP-S and FRAP-T codes, and new models for predicting reactor fuel restructuring and zircaloy cladding behavior; an analysis of post-CHF fuel behavior was made using FRAP-T.

  19. PERFORMA NEUTRONIK BAHAN BAKAR LiF-BeF2-ThF4-UF4 PADA SMALL MOBILE-MOLTEN SALT REACTOR

    Directory of Open Access Journals (Sweden)

    S. N. Rokhman

    2015-04-01

    Full Text Available Telah dilakukan analisis terhadap performa neutronik bahan bakar garam lebur LiF-BeF2-ThF4-UF4 pada Small Mobile-Molten Salt Reactor (SM-MSR. Penyesuaian konfigurasi teras dan temperatur operasi harus dilakukan untuk penggunaan bahan bakar baru tersebut agar mencapai keff > 1 dan CR (conversion ratio > 1 pada fraksi 0,5% 233U, 20% 232Th, 28% Li, 51,5% Be. Setelah didapat nilai keff ≈ 1 dan CR ≈ 1, dilakukan analisis pengaruh perubahan Th terhadap Be dan Be terhadap Li yang terlihat dalam perubahan parameter keff dan CR. Setelah itu fraksi 233U divariasi antara 0,5–0,46% untuk memperoleh keff > 1 dan CR > 1. Dalam perhitungan koefisien reaktifitas temperatur (αT, temperatur teras dinaikkan sebesar +25K dan +50K., dan untuk koefisien reaktifitas void (αV, densitas bahan bakar dikurangi hingga 90%. Hasil perhitungan menunjukkan bahwa pengurangan Th terhadap Be menyebabkan penurunan nilai CR dan naiknya keff akibat berkurangnya material fertil. Sebaliknya penambahan Be terhadap Li mengakibatkan terjadi kenaikan nilai keff dan menurunkan CR, akibat laju serapan Li lebih besar dari Be. Pada 5 (lima fraksi 233U dalam rentang 0,5–0,49%, hasil perhitungan keff dan CR masing-masing bervariasi dalam rentang 1,00001 - 1,00327 dan 1,00016 - 1,00731. Untuk faktor puncak daya (PPF, hasil perhitungan memberikan nilai dalam rentang 2,4311 -2,4714. Sedangkan untuk parameter keselamatan, koefisien reaktivitas temperatur (αT dan reaktivitas void (αV masingmasing bernilai negatif dalam rentang 4,972×10-5 - 5,909×10-5 dan 2,596×10-2- 2,8287×10-2 ∆k/k/K. Dapat disimpulkan bahwa teras SM-MSR memberikan nilai negatif di kedua koefisien reaktivitas tersebut untuk setiap fraksi,, sehingga memenuhi kriteria keselamatan dan keselamatan melekat. Kata kunci: SM-MSR (small mobile-molten salt reactor, bahan bakar LiF-BeF2-ThF4-UF4, keselamatan melekat, koefisien reaktivitas temperatur, koefisien reaktivitas void   The analysis of neutronic performance has

  20. Destruction kinetic of PCDDs/Fs in MSWI fly ash using microwave peroxide oxidation.

    Science.gov (United States)

    Chang, Yu-Min; Fang, Wen-Bin; Tsai, Kuo-Sheng; Kao, Jimmy C M; Lin, Kae-Long; Chen, Ching-Ho

    2015-01-01

    Microwave peroxide oxidation is a less greenhouse gas emission and energy-efficient technology to destroy toxic organic compounds in hazardous waste. The research novelty is to adopt the innovative microwave peroxide oxidation in H2SO4/HNO3 solution to efficiently destroy the polychlorinated dibenzo-p-dioxins (PCDDs)/Fs in municipal solid waste incineration fly ash. The major objective of this paper is to study dynamic destruction of PCDDs/Fs using the microwave peroxide oxidation. Almost all PCDDs/Fs in the raw fly ash can be destructed in 120 min at a temperature of 423 K using the microwave peroxide oxidation treatment. It was found that the microwave peroxide oxidation provides the potential to destruct the PCDDs/Fs content in municipal solid waste incinerator (MSWI) fly ash to a low level as a function of treatment time. A useful kinetic correlation between destruction efficiency and treatment conditions is proposed on the basis of the experimental data obtained in this study. The significance of this work in terms of practical engineering applications is that the necessary minimum treatment time can be solved using a proposed graphic illustration method, by which the minimum treatment time is obtained if the desired destruction efficiency and treatment temperature are known. Because of inorganic salt dissolution, the temperature would be a critical factor facilitating the parts of fly ash dissolution. Material loss problem caused by the microwave peroxide oxidation and the effects of treatment time and temperature are also discussed in this paper.