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Sample records for s10fs-1 reactor

  1. 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.

  2. 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

  3. 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.

  4. 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

  5. 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.

  6. 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.

  7. 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

  8. 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

  9. 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

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. 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)

  16. 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 ...

  17. 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 ...

  18. 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

  19. 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 ...

  20. 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.

  1. 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.

  2. 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

  3. 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 ...

  4. 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 ...

  5. 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 ...

  6. 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 ...

  7. 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 ...

  8. 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 ...

  9. 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 ...

  10. 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 ...

  11. 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 ...

  12. 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 ...

  13. 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 ...

  14. 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 ...

  15. 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 ...

  16. 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 ...

  17. 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 ...

  18. 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 ...

  19. 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 ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 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 ...

  4. 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 ...

  5. 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 ...

  6. 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 ...

  7. 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 ...

  8. 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 ...

  9. 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 ...

  10. 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 ...

  11. 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 ...

  12. 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 ...

  13. 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 ...

  14. 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 ...

  15. 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 ...

  16. 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 ...

  17. 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 ...

  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: 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 ...

  2. 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 ...

  3. 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 ...

  4. 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

  5. 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 ...

  6. 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 ...

  7. 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 ...

  8. 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 ...

  9. 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 ...

  10. 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 ...

  11. 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 ...

  12. 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 ...

  13. 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 ...

  14. 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 ...

  15. 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 ...

  16. 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 ...

  17. 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 ...

  18. 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 ...

  19. 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 ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 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- ...

  4. 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- ...

  5. 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)

  6. 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 ...

  7. 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 ...

  8. 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)

  9. 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 ...

  10. 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 ...

  11. 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.)

  12. 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 ...

  13. 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 ...

  14. 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 ...

  15. 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 ...

  16. 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 ...

  17. 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 ...

  18. 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 ...

  19. 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 ...

  20. 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 ...

  1. 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 ...

  2. 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 ...

  3. 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 ...

  4. 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 ...

  5. 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 ...

  6. 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

  7. 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/

  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: 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. 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

  15. 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

  16. 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

  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. 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)

  19. 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) ...

  20. 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

  1. 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...

  2. 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

  3. 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) ...

  4. 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.

  5. 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.

  6. 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 ...

  7. 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 ...

  8. 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 ...

  9. 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 ...

  10. 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) ...

  11. 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-

  12. 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 ...

  13. 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 ...

  14. 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

  15. 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...

  16. 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 ...

  17. 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

  18. 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 ...

  19. 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 ...

  20. 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

  1. 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) ...

  2. 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 ...

  3. 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

  4. 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 ...

  5. 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

  6. 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

  7. 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

  8. 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

  9. 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

  10. 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

  11. 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

  12. 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 ...

  13. 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

  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. 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

  16. 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 ...

  17. Structure of a thermostable serralysin from Serratia sp. FS14 at 1.1 Å resolution.

    Science.gov (United States)

    Wu, Dongxia; Ran, Tinting; Wang, Weiwu; Xu, Dongqing

    2016-01-01

    Serralysin is a well studied metalloprotease, and typical serralysins are not thermostable. The serralysin isolated from Serratia sp. FS14 was found to be thermostable, and in order to reveal the mechanism responsible for its thermostability, the crystal structure of serralysin from Serratia sp. FS14 was solved to a crystallographic R factor of 0.1619 at 1.10 Å resolution. Similar to its homologues, it mainly consists of two domains: an N-terminal catalytic domain and a `parallel β-roll' C-terminal domain. Comparative studies show that the shape of the catalytic active-site cavity is more open owing to the 189-198 loop, with a short 310-helix protruding further from the molecular surface, and that the β-sheets comprising the `parallel β-roll' are longer than those in its homologues. The formation of hydrogen bonds from one of the nonconserved residues (Asn200) to Lys27 may contribute to the thermostability.

  18. 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- ...

  19. 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

  20. 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

  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: 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 ...

  3. 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

  4. 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)

  5. 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

  6. 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)

  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. Interferon-inducible protein 10 (IP-10) is associated with viremia of early HIV-1 infection in Korean patients.

    Science.gov (United States)

    Lee, SoYong; Chung, Yoon-Seok; Yoon, Cheol-Hee; Shin, YoungHyun; Kim, SeungHyun; Choi, Byeong-Sun; Kim, Sung Soon

    2015-05-01

    Cytokines/chemokines play key roles in modulating disease progression in human immunodeficiency virus (HIV) infection. Although it is known that early HIV-1 infection is associated with increased production of proinflammatory cytokines, the relationship between cytokine levels and HIV-1 pathogenesis is not clear. The concentrations of 18 cytokines/chemokines in 30 HIV-1 negative and 208 HIV-1 positive plasma samples from Korean patients were measured by the Luminex system. Early HIV-1 infection was classified according to the Fiebig stage (FS) based on the characteristics of the patients infected with HIV-1. Concentrations of interleukin-12 (IL-12), interferon-inducible protein-10 (IP-10), macrophage inflammatory protein-1α (MIP-1α) and regulated upon activation, normal T cells expressed and secreted (RANTES) were increased significantly during the early stage of HIV-1 infection (FS II-IV) compared with the HIV-1-negative group. Of these cytokines, an elevated level of IP-10 was the only factor to be correlated positively with a higher viral load during the early stages of HIV-1 infection (FS II-IV) in Koreans (R = 0.52, P IP-10 may be an indicator for HIV-1 viremia and associated closely with viral replication in patients with early HIV-1 infection. © 2015 Wiley Periodicals, Inc.

  9. The T-cell receptor beta chain CDR3 region of BV8S1/BJ1S5 transcripts in type 1 diabetes.

    Science.gov (United States)

    Naserke, H E; Durinovic-Bellò, I; Seidel, D; Ziegler, A G

    1996-01-01

    We recently described the T-cell receptor (TCR) beta chain CDR3 motif S-SDRLG-NQPQH (BV8S1-BJ1S5) in an islet-specific T-cell clone (K2.12) from a type 1 diabetic patient (AS). A similar motif (RLGNQ) was also reported in a T-cell clone of non-obese diabetic (NOD) mice by others. In order to determine the frequency of our motif in selected and unselected T-cell populations, we cloned and sequenced the CDR3 region of BV8S1-BJ1S5 transcripts. These transcripts were derived from unstimulated peripheral blood T lymphocytes from two type 1 diabetic patients (AS and FS) and their non-diabetic sibling (WS), as well as from an islet-specific T-cell line of one of the patients. In addition, we compared the structure and composition of the CDR3 region in BV8S1-BJ1S5 transcripts from peripheral blood T cells between the patients and their non-diabetic sibling (>50 sequences each). We found that 30% of the islet-specific T-cell line cDNA clones expressed the entire sequence-motif, whereas it was absent in the clones of unstimulated peripheral blood T cells from both patients and their non-diabetic sibling. The average length of the CDR3 region was shorter in the patients (mean AS 9.9, FS 9.9, versus WS 10.7, p = 0.0037) and the number of inserted nucleotides in N nucleotide addition at the DJ-junction lower (mean AS 3.5, FS 3. 2, versus WS 5.2, P = diabetic sibling. Moreover, the pattern of amino acid usage in the CDR3 region was dissimilar at positions 5 and 6, where polar amino acids predominated in both diabetic siblings. In contrast, basic amino acids are preferentially used at position 5 in the clones of the non-diabetic sibling. These data provide information on the general structure of the TCR(BV8S1-BJ1S5) CDR3 region in type 1 diabetes and may indicate differences in the amino and nucleic acid composition of the TCR beta chain CDR3 region between two type 1 diabetic patients and their non-diabetic sibling.

  10. 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.

  11. 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)

  12. 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

  13. 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.

  14. 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.

  15. 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)

  16. 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)

  17. 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.

  18. 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.

  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. 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

  1. UV-C irradiation of HSV-1 infected fibroblasts (HSV-FS) enhances human natural killer (NK) cell activity against these targets

    International Nuclear Information System (INIS)

    Pettera, L.; Fitzgerald-Bocarsly, P.

    1991-01-01

    Expression of Herpes Simplex Virus Type 1 (HSV-1) immediate early gene products has been bound to be sufficient for NK cell mediated lysis of HSV-1 infected FS. To block the targets at various stages in the infectious cycle, HSV-FS were irradiated with UV light for 1 min at 2, 6, and 20 hr post-infection. NK mediated lysis of 2 hr and 5 hr UV treated HSV-FS was 2-fold higher than non-UV treated HSV-FS despite a >99% inhibition in virus yield. In contrast, 20 hr infected targets were lysed less well than 2 and 6 hr targets despite strong glycoprotein expression and induction of high levels of interferon-alpha (IFN-α) production by effector PBMC's; this lysis was not enhanced by UV treatment. Since NK lysis of HSV-FS has been found to be dependent on an HLA-DR + accessory cell (AC), lysis of irradiated HSV-FS by PBMC's depleted of AC was measured. Such depletion eradicated NK lysis of the UV treated HSV-FS indicating that irradiation does not overcome the AC requirement for NK lysis. UV irradiation of another HLA-DR + dependent target, Vesicular Stomatitis Virus (VSV) infected FS led to a dramatic reduction in both NK lysis and IFN-α induction. HSV-1 is a DNA virus whose genes are expressed in a cascade fashion whereas VSV is an RNA virus. The authors hypothesize that the enhancement in AC dependent NK activity observed for UV irradiated HSV-FS, but not VSV-FS, targets is due to overproduction of either a cellular or viral gene product which specifically occurs early in the HSV-1 infectious cycle and is downregulated by 20 hr post-infection

  2. 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

  3. 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

  4. 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) ...

  5. 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.

  6. 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) ...

  7. Acute and subchronic toxicity studies of the original drug FS-1

    Directory of Open Access Journals (Sweden)

    Assem Kalykova

    2016-01-01

    Full Text Available Interest in iodine complexes has increased significantly in recent years because of their wide spectrum of biological activity. The FS-1 is an ion nanostructured complex formed by proteins and/or polypeptides, carbohydrates, salts of alkali and alkaline earth metals with intercalated iodine. Patented in 2014, it is intended for the treatment of infectious diseases of bacterial origin including nosocomial infections and multidrug resistant tuberculosis. The aim of the study was to determine its acute and subchronic toxicity. The study of acute and subchronic toxicity was performed on adult Wistar rats according to OECD guidelines. The data on acute toxicity showed LD50 > 2,000 mg/kg after a single intragastric administration. Twenty-eight days of FS-1 administration at a dose of 500 mg/kg resulted in toxic effects. At a dose of 250 mg/kg, the toxic effects were temporary and a return to normal followed after the recovery period. Doses of 100 mg/kg had no adverse effects on the rats.

  8. Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 1: Reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-12-01

    This annual report of the US Nuclear Regulatory Commission`s Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC`s Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC`s mission in 1996.

  9. RAZORBACK - A Research Reactor Transient Analysis Code Version 1.0 - Volume 3: Verification and Validation Report.

    Energy Technology Data Exchange (ETDEWEB)

    Talley, Darren G.

    2017-04-01

    This report describes the work and results of the verification and validation (V&V) of the version 1.0 release of the Razorback code. Razorback is a computer code designed to simulate the operation of a research reactor (such as the Annular Core Research Reactor (ACRR)) by a coupled numerical solution of the point reactor kinetics equations, the energy conservation equation for fuel element heat transfer, the equation of motion for fuel element thermal expansion, and the mass, momentum, and energy conservation equations for the water cooling of the fuel elements. This V&V effort was intended to confirm that the code shows good agreement between simulation and actual ACRR operations.

  10. Primary Productivity, SeaWiFS and Pathfinder, 0.1 degrees, Global, EXPERIMENTAL

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — Primary Productivity is calculated from SeaWiFS Chl a, Pathfinder SST, and SeaWiFS PAR data. THIS IS AN EXPERIMENTAL PRODUCT: intended strictly for scientific...

  11. 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 ...

  12. 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

  13. 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

  14. 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 ...

  15. 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 ...

  16. 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)

  17. Observation of B(s)0-->K+ K- and measurements of branching fractions of charmless two-body decays of B0 and B(s)0 mesons in pp collisions at square root of s = 1.96 TeV.

    Science.gov (United States)

    Abulencia, A; Acosta, D; Adelman, J; Affolder, T; Akimoto, T; Albrow, M G; Ambrose, D; Amerio, S; Amidei, D; Anastassov, A; Anikeev, K; Annovi, A; Antos, J; Aoki, M; Apollinari, G; Arguin, J-F; Arisawa, T; Artikov, A; Ashmanskas, W; Attal, A; Azfar, F; Azzi-Bacchetta, P; Azzurri, P; Bacchetta, N; Bachacou, H; Badgett, W; Barbaro-Galtieri, A; Barnes, V E; Barnett, B A; Baroiant, S; Bartsch, V; Bauer, G; Bedeschi, F; Behari, S; Belforte, S; Bellettini, G; Bellinger, J; Belloni, A; Ben Haim, E; Benjamin, D; Beretvas, A; Beringer, J; Berry, T; Bhatti, A; Binkley, M; Bisello, D; Blair, R E; Blocker, C; Blumenfeld, B; Bocci, A; Bodek, A; Boisvert, V; Bolla, G; Bolshov, A; Bortoletto, D; Boudreau, J; Boveia, A; Brau, B; Bromberg, C; Brubaker, E; Budagov, J; Budd, H S; Budd, S; Burkett, K; Busetto, G; Bussey, P; Byrum, K L; Cabrera, S; Campanelli, M; Campbell, M; Canelli, F; Canepa, A; Carlsmith, D; Carosi, R; Carron, S; Casarsa, M; Castro, A; Catastini, P; Cauz, D; Cavalli-Sforza, M; Cerri, A; Cerrito, L; Chang, S H; Chapman, J; Chen, Y C; Chertok, M; Chiarelli, G; Chlachidze, G; Chlebana, F; Cho, I; Cho, K; Chokheli, D; Chou, J P; Chu, P H; Chuang, S H; Chung, K; Chung, W H; Chung, Y S; Ciljak, M; Ciobanu, C I; Ciocci, M A; Clark, A; Clark, D; Coca, M; Compostella, G; Convery, M E; Conway, J; Cooper, B; Copic, K; Cordelli, M; Cortiana, G; Crescioli, F; Cruz, A; Cuenca Almenar, C; Cuevas, J; Culbertson, R; Cyr, D; Daronco, S; D'Auria, S; D'Onofrio, M; Dagenhart, D; de Barbaro, P; De Cecco, S; Deisher, A; De Lentdecker, G; Dell'Orso, M; Delli Paoli, F; Demers, S; Demortier, L; Deng, J; Deninno, M; De Pedis, D; Derwent, P F; Dionisi, C; Dittmann, J R; DiTuro, P; Dörr, C; Donati, S; Donega, M; Dong, P; Donini, J; Dorigo, T; Dube, S; Ebina, K; Efron, J; Ehlers, J; Erbacher, R; Errede, D; Errede, S; Eusebi, R; Fang, H C; Farrington, S; Fedorko, I; Fedorko, W T; Feild, R G; Feindt, M; Fernandez, J P; Field, R; Flanagan, G; Flores-Castillo, L R; Foland, A; Forrester, S; Foster, G W; Franklin, M; Freeman, J C; Furic, I; Gallinaro, M; Galyardt, J; Garcia, J E; Garcia Sciveres, M; Garfinkel, A F; Gay, C; Gerberich, H; Gerdes, D; Giagu, S; Giannetti, P; Gibson, A; Gibson, K; Ginsburg, C; Giokaris, N; Giolo, K; Giordani, M; Giromini, P; Giunta, M; Giurgiu, G; Glagolev, V; Glenzinski, D; Gold, M; Goldschmidt, N; Goldstein, J; Gomez, G; Gomez-Ceballos, G; Goncharov, M; González, O; Gorelov, I; Goshaw, A T; Gotra, Y; Goulianos, K; Gresele, A; Griffiths, M; Grinstein, S; Grosso-Pilcher, C; Grundler, U; Guimaraes da Costa, J; Gunay-Unalan, Z; Haber, C; Hahn, S R; Hahn, K; Halkiadakis, E; Hamilton, A; Han, B-Y; Han, J Y; Handler, R; Happacher, F; Hara, K; Hare, M; Harper, S; Harr, R F; Harris, R M; Hatakeyama, K; Hauser, J; Hays, C; Heijboer, A; Heinemann, B; Heinrich, J; Herndon, M; Hidas, D; Hill, C S; Hirschbuehl, D; Hocker, A; Holloway, A; Hou, S; Houlden, M; Hsu, S-C; Huffman, B T; Hughes, R E; Huston, J; Incandela, J; Introzzi, G; Iori, M; Ishizawa, Y; Ivanov, A; Iyutin, B; James, E; Jang, D; Jayatilaka, B; Jeans, D; Jensen, H; Jeon, E J; Jindariani, S; Jones, M; Joo, K K; Jun, S Y; Junk, T R; Kamon, T; Kang, J; Karchin, P E; Kato, Y; Kemp, Y; Kephart, R; Kerzel, U; Khotilovich, V; Kilminster, B; Kim, D H; Kim, H S; Kim, J E; Kim, M J; Kim, S B; Kim, S H; Kim, Y K; Kirsch, L; Klimenko, S; Klute, M; Knuteson, B; Ko, B R; Kobayashi, H; Kondo, K; Kong, D J; Konigsberg, J; Korytov, A; Kotwal, A V; Kovalev, A; Kraan, A; Kraus, J; Kravchenko, I; Kreps, M; Kroll, J; Krumnack, N; Kruse, M; Krutelyov, V; Kuhlmann, S E; Kusakabe, Y; Kwang, S; Laasanen, A T; Lai, S; Lami, S; Lammel, S; Lancaster, M; Lander, R L; Lannon, K; Lath, A; Latino, G; Lazzizzera, I; LeCompte, T; Lee, J; Lee, J; Lee, Y J; Lee, S W; Lefèvre, R; Leonardo, N; Leone, S; Levy, S; Lewis, J D; Lin, C; Lin, C S; Lindgren, M; Lipeles, E; Lister, A; Litvintsev, D O; Liu, T; Lockyer, N S; Loginov, A; Loreti, M; Loverre, P; Lu, R-S; Lucchesi, D; Lujan, P; Lukens, P; Lungu, G; Lyons, L; Lys, J; Lysak, R; Lytken, E; Mack, P; MacQueen, D; Madrak, R; Maeshima, K; Maki, T; Maksimovic, P; Malde, S; Manca, G; Margaroli, F; Marginean, R; Marino, C; Martin, A; Martin, V; Martínez, M; Maruyama, T; Mastrandrea, P; Matsunaga, H; Mattson, M E; Mazini, R; Mazzanti, P; McFarland, K S; McIntyre, P; McNulty, R; Mehta, A; Menzemer, S; Menzione, A; Merkel, P; Mesropian, C; Messina, A; von der Mey, M; Miao, T; Miladinovic, N; Miles, J; Miller, R; Miller, J S; Mills, C; Milnik, M; Miquel, R; Mitra, A; Mitselmakher, G; Miyamoto, A; Moggi, N; Mohr, B; Moore, R; Morello, M; Movilla Fernandez, P; Mülmenstädt, J; Mukherjee, A; Muller, Th; Mumford, R; Murat, P; Nachtman, J; Naganoma, J; Nahn, S; Nakano, I; Napier, A; Naumov, D; Necula, V; Neu, C; Neubauer, M S; Nielsen, J; Nigmanov, T; Nodulman, L; Norniella, O; Nurse, E; Ogawa, T; Oh, S H; Oh, Y D; Okusawa, T; Oldeman, R; Orava, R; Osterberg, K; Pagliarone, C; Palencia, E; Paoletti, R; Papadimitriou, V; Paramonov, A A; Parks, B; Pashapour, S; Patrick, J; Pauletta, G; Paulini, M; Paus, C; Pellett, D E; Penzo, A; Phillips, T J; Piacentino, G; Piedra, J; Pinera, L; Pitts, K; Plager, C; Pondrom, L; Portell, X; Poukhov, O; Pounder, N; Prakoshyn, F; Pronko, A; Proudfoot, J; Ptohos, F; Punzi, G; Pursley, J; Rademacker, J; Rahaman, A; Rakitin, A; Rappoccio, S; Ratnikov, F; Reisert, B; Rekovic, V; van Remortel, N; Renton, P; Rescigno, M; Richter, S; Rimondi, F; Ristori, L; Robertson, W J; Robson, A; Rodrigo, T; Rogers, E; Rolli, S; Roser, R; Rossi, M; Rossin, R; Rott, C; Ruiz, A; Russ, J; Rusu, V; Saarikko, H; Sabik, S; Safonov, A; Sakumoto, W K; Salamanna, G; Saltó, O; Saltzberg, D; Sanchez, C; Santi, L; Sarkar, S; Sartori, L; Sato, K; Savard, P; Savoy-Navarro, A; Scheidle, T; Schlabach, P; Schmidt, E E; Schmidt, M P; Schmitt, M; Schwarz, T; Scodellaro, L; Scott, A L; Scribano, A; Scuri, F; Sedov, A; Seidel, S; Seiya, Y; Semenov, A; Sexton-Kennedy, L; Sfiligoi, I; Shapiro, M D; Shears, T; Shepard, P F; Sherman, D; Shimojima, M; Shochet, M; Shon, Y; Shreyber, I; Sidoti, A; Sinervo, P; Sisakyan, A; Sjolin, J; Skiba, A; Slaughter, A J; Sliwa, K; Smith, J R; Snider, F D; Snihur, R; Soderberg, M; Soha, A; Somalwar, S; Sorin, V; Spalding, J; Spezziga, M; Spinella, F; Spreitzer, T; Squillacioti, P; Stanitzki, M; Staveris-Polykalas, A; St Denis, R; Stelzer, B; Stelzer-Chilton, O; Stentz, D; Strologas, J; Stuart, D; Suh, J S; Sukhanov, A; Sumorok, K; Sun, H; Suzuki, T; Taffard, A; Takashima, R; Takeuchi, Y; Takikawa, K; Tanaka, M; Tanaka, R; Tanimoto, N; Tecchio, M; Teng, P K; Terashi, K; Tether, S; Thom, J; Thompson, A S; Thomson, E; Tipton, P; Tiwari, V; Tkaczyk, S; Toback, D; Tokar, S; Tollefson, K; Tomura, T; Tonelli, D; Tönnesmann, M; Torre, S; Torretta, D; Tourneur, S; Trischuk, W; Tsuchiya, R; Tsuno, S; Turini, N; Ukegawa, F; Unverhau, T; Uozumi, S; Usynin, D; Vaiciulis, A; Vallecorsa, S; Varganov, A; Vataga, E; Velev, G; Veramendi, G; Veszpremi, V; Vidal, R; Vila, I; Vilar, R; Vine, T; Vollrath, I; Volobouev, I; Volpi, G; Würthwein, F; Wagner, P; Wagner, R G; Wagner, R L; Wagner, W; Wallny, R; Walter, T; Wan, Z; Wang, S M; Warburton, A; Waschke, S; Waters, D; Wester, W C; Whitehouse, B; Whiteson, D; Wicklund, A B; Wicklund, E; Williams, G; Williams, H H; Wilson, P; Winer, B L; Wittich, P; Wolbers, S; Wolfe, C; Wright, T; Wu, X; Wynne, S M; Yagil, A; Yamamoto, K; Yamaoka, J; Yamashita, T; Yang, C; Yang, U K; Yang, Y C; Yao, W M; Yeh, G P; Yoh, J; Yorita, K; Yoshida, T; Yu, G B; Yu, I; Yu, S S; Yun, J C; Zanello, L; Zanetti, A; Zaw, I; Zetti, F; Zhang, X; Zhou, J; Zucchelli, S

    2006-11-24

    We search for decays of the type B(s)0-->h+ h'- (where h,h' = K or pi) in 180 pb(-1) of pp collisions collected at the Tevatron by the upgraded Collider Detector at Fermilab. We report the first observation of the new mode B(s)0-->K+ K- with a yield of 236+/-32 events, corresponding to (fs/fd) x B(B(s)0-->K+ K-)/B(B0-->K+ pi-) = 0.46+/-0.08stat+/-0.07syst, where fs/fd is the ratio of production fractions of B(s)0 and B0. We find results in agreement with world averages for the B0 modes, and set the following new limits at 90% C.L.: B(B(s)0-->K- pi+) pi+ pi-) < 1.7 x 10(-6).

  18. 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)

  19. 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- ...

  20. 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.

  1. 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

  2. 76 FR 23630 - Office of New Reactors; Proposed Revision 2 to Standard Review Plan, Section 1.0 on Introduction...

    Science.gov (United States)

    2011-04-27

    ... Standard Review Plan, Section 1.0 on Introduction and Interfaces AGENCY: Nuclear Regulatory Commission (NRC... Revision 2 to Standard Review Plan (SRP), Section 1.0, ``Introduction and Interfaces'' (Agencywide Documents Access and Management System (ADAMS) Accession No. ML110110573). The Office of New Reactors (NRO...

  3. 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

  4. 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

  5. Neutron radiography in the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Pugliesi, R.; Moraes, A.P.V. de; Yamazaki, I.M.; Freitas Acosta, C. de.

    1988-08-01

    Neutronradiography of several materials have been obtained at the IEA-R1 Nuclear Research Reactor (IPEN-CNEN/SP), by means of two conversion techniques: a) (n, α) at the beam-hole n 0 3 where a collimated thermal neutron beam, exposure area 4 cm x 8cm and flux at the sample 10 5 n/s cm 2 is obtained. The film used was the CN-85 cellulose nitrate coated with lithium tetraborate (conversor). The time irradiation of the film was 15 minutes and in following was eteched during 30 minutes in a NaOH(10%) aqueous solution at a constant temperature of 60 0 C.; b) (n,γ) by using an experimental arrangement installed in the botton of the pool of the reactor. The flux of the collimated neutron beam is 10 5 n/s/cm 2 at the sample and the conversion is made by means of a dysprozium sheet. The film used was Kodak T-5. The irradiation and the transfering time was 2 hours and 20 hours respectively. (author) [pt

  6. 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

  7. 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

  8. 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 ...

  9. 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) ...

  10. 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 ...

  11. 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) ...

  12. 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) ...

  13. 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) ...

  14. 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)

  15. 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)

  16. 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) ...

  17. 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) ...

  18. 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) ...

  19. Severe accident analysis using MARCH 1.0 code

    International Nuclear Information System (INIS)

    Guimaraes, A.C.F.

    1987-09-01

    The description and utilization of the MARCH 1.0 computer code, which aim to analyse physical phenomena associated with core meltdown accidents in PWR type reactors, are presented. The primary system is modeled as a single volume which is partitioned into a gas (steam and hydrogen) region and a water region. March predicts blowdown from the primary system in single phase. Based on results of the probabilistic safety analysis for the Zion and Indian Point Nuclear Power Plants, the S 2 HFX sequence accident for Angra-1 reactor is studied. The S 2 HFX sequence means that the loss of coolant accident occurs through small break in primary system with bot total failures of the reactor safety system and containment in yours recirculation modes, leading the core melt and the containment failure due to overpressurization. The obtained results were considered reasonable if compared with the results obtained for the Zion and Indian Point nuclear power plants. (Author) [pt

  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. 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.

  2. 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 ...

  3. 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 ...

  4. 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) ...

  5. 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) ...

  6. 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) ...

  7. 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

  8. 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)

  9. 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

  10. 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) ...

  11. 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) ...

  12. 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.

  13. 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)

  14. 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

  15. 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.

  16. 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...

  17. 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

  18. 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

  19. 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

  20. 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) ...

  1. 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 ...

  2. 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) ...

  3. (2S,7S-10-Ethyl-1,8,10,12-tetraazatetracyclo[8.3.1.18,12.02,7]pentadecan-10-ium iodide

    Directory of Open Access Journals (Sweden)

    Augusto Rivera

    2012-10-01

    Full Text Available The title chiral quaternary ammonium salt, C13H25N4+·I−, was synthesized through the Menschutkin reaction between the cage aminal (2S,7S-1,8,10,12-tetraazatetracyclo[8.3.1.18,12.02,7]pentadecane and ethyl iodide. The quaternization occurred regioselectively on the nitrogen with major sp3 character. The crystal structure consists of anions and cations separated by normal distances. Ions are not linked through C—H...I hydrogen bonds.

  4. Preliminary Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

    International Nuclear Information System (INIS)

    Kim, In-Young; Choi, Heui-Joo

    2016-01-01

    In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1

  5. Preliminary Evaluation on Characteristics of Waste from Pyro-processing (FS v5.1)

    Energy Technology Data Exchange (ETDEWEB)

    Kim, In-Young; Choi, Heui-Joo [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated for revising of A-KRS concept. To reduce volume and toxicity of PWR SNFs, the P and T Technology using pyro-processing and SFR is under development in KAERI. In accordance with this R and D, the A-KRS was developed by KAERI for disposal of waste from pyro-processing. After A-KRS concept development, material balance has been revised and characteristics of waste have been changed. To solve impending saturation of storage capacity of NPP sites, national policy on SNF management seems to be determined shortly. Demand on detailed analysis on impact of P and T using pyro-processing and SFR as base data is increasing. To compare direct disposal scenario to the P and T scenario using pyro-processing and SFR, updating of A-KRS reflecting amendment of material balance is required. In this study, characteristic of waste from pyro-processing which based on material balance FS v5.1 is evaluated. Every 15 types of outputs generated from pyro-processing are evaluated. Great reduction can be achieved by complete reuse of U/TRU/RE in SFR, because most of decay heat, radioactivity and radiotoxicity are generated from U/TRU/RE ingot. Within about 300 years, the fly ash filter containing Cs, Sr containing salt waste are important waste in perspective of decay heat and radioactivity. Importance of RE containing salt waste reduced. Management of hold-ups must be clarified because hold-ups take large portion of decay heat, radioactivity in the material balance FS v5.1.

  6. 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) ...

  7. 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

  8. Neutron flux of 100kW in the irradiation terminals of the IPR-R1 Triga Reactor

    International Nuclear Information System (INIS)

    Zangirolami, Dante Marco

    2009-01-01

    In this work, it was carried out a study of the neutron flux in the IPR-R1 TRIGA reactor irradiation facilities: rotary specimen rack (RSR), pneumatic transfer tube two (PTT2) and the central thimble (CT). The objective was to obtain the neutron flux profile on the RSR, which has forty irradiation positions, and also values for the thermal and epithermal neutron fluxes of some RSR positions and also of the PTT2 and of the CT facility. It was applied the neutron activation analysis of a reference material, Al-Au (0.1%) alloy. Irradiations were performed on 16 different dates. It was concluded that for the RSR, the average value of thermal and epithermal neutron fluxes depends on the vertical position of the reactor control rods. Neutron flux variations along the RSR form a characteristic profile, whose values depend on the location of the irradiation position in the reactor core and on the control rods vertical position. In the RSR, the obtained values of thermal and epithermal neutron flux were (8.1 +- 0.3) x 10 11 n.cm -2 .s -1 , and (3.4 +- 0.2)x10 10 n.cm -2 .s -1 , respectively. For the PTT2 and the CT, the values for the epithermal neutron flux were respectively (3.3 +- 0.2) x 10 9 n.cm -2 .s -1 and (2.6 +- 0.1) x 10 11 n.cm -2 .s -1 . For these facilities, the thermal neutron flux was estimated, and the obtained values were (2.4 +- 0.2) x 10 11 n.cm -2 .s -1 and (2.8 +- 0.1)x10 12 n.cm -2 .s -1 for the PTT2 and the CT, respectively. (author)

  9. 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) ...

  10. 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)

  11. 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) ...

  12. 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) ...

  13. 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) ...

  14. 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) ...

  15. 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) ...

  16. 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) ...

  17. 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.

  18. Safety operation of training reactor VR-1

    International Nuclear Information System (INIS)

    Matejka, K.

    2001-01-01

    There are three nuclear research reactors in the Czech Republic in operation now: light water reactor LVR-15, maximum reactor power 10 MW t , owner and operator Nuclear Research Institute Rez; light water zero power reactor LR-0, maximum reactor power 5 kW t , owner and operator Nuclear Research Institute Rez and training reactor VR-1 Sparrow, maximum reactor power 5 kW t , owner and operate Faculty of Nuclear Sciences and Physical Engineering, CTU in Prague. The training reactor VR-1 Vrabec 'Sparrow', operated at the Faculty of Nuclear Sciences and Physical Engineering, Czech Technical University in Prague, was started up on December 3, 1990. Particularly it is designed for training the students of Czech universities, preparing the experts for the Czech nuclear programme, as well as for certain research work, and for information programmes in the nuclear programme, as well as for certain research work, and for information programmes in sphere of using the nuclear energy (public relations). (author)

  19. 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) ...

  20. 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) ...

  1. 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) ...

  2. 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) ...

  3. 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) ...

  4. 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) ...

  5. 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) ...

  6. 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) ...

  7. 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

  8. 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.

  9. An evaluation of TRAC-PF1/MOD1 computer code performance during posttest simulations of Semiscale MOD-2C feedwater line break transients

    International Nuclear Information System (INIS)

    Hall, D.G.; Watkins, J.C.

    1987-01-01

    This report documents an evaluation of the TRAC-PF1/MOD1 reactor safety analysis computer code during computer simulations of feedwater line break transients. The experimental data base for the evaluation included the results of three bottom feedwater line break tests performed in the Semiscale Mod-2C test facility. The tests modeled 14.3% (S-FS-7), 50% (S-FS-11), and 100% (S-FS-6B) breaks. The test facility and the TRAC-PF1/MOD1 model used in the calculations are described. Evaluations of the accuracy of the calculations are presented in the form of comparisons of measured and calculated histories of selected parameters associated with the primary and secondary systems. In addition to evaluating the accuracy of the code calculations, the computational performance of the code during the simulations was assessed. A conclusion was reached that the code is capable of making feedwater line break transient calculations efficiently, but there is room for significant improvements in the simulations that were performed. Recommendations are made for follow-on investigations to determine how to improve future feedwater line break calculations and for code improvements to make the code easier to use

  10. 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.

  11. 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

  12. 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.

  13. 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

  14. 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.

  15. 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 ...

  16. 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.

  17. 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.

  18. 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) ...

  19. 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 ...

  20. 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) ...

  1. 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) ...

  2. 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) ...

  3. 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) ...

  4. 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) ...

  5. 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) ...

  6. METEOR v1.0 - User's Guide; METEOR v1.0 - Guia de Usuarios

    Energy Technology Data Exchange (ETDEWEB)

    Palomo, E.

    1994-07-01

    This script is a User's Guide for the software package METEOR for statistical analysis of meteorological data series. The original version of METEOR have been developed by Ph.D. Elena Palomo, CIEMAT-IER, GIMASE. It is built by linking programs and routines written in FORTRAN 77 and it adds the graphical capabilities of GNUPLOT. The shape of this toolbox was designed following the criteria of modularity, flexibility and agility criteria. All the input, output and analysis options are structured in three main menus: i) the first is aimed to evaluate the quality of the data set; ii) the second is aimed for pre-processing of the data; and iii) the third is aimed towards the statistical analyses and for creating the graphical outputs. Actually the information about METEOR is constituted by three documents written in spanish: 1) METEOR v1.0: User's guide; 2) METEOR v1.0: A usage example; 3) METEOR v1.0: Design and structure of the software package. (Author)

  7. 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.

  8. 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)

  9. 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) ...

  10. 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) ...

  11. 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) ...

  12. 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) ...

  13. 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) ...

  14. 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...

  15. 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) ...

  16. 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) ...

  17. 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.

  18. 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

  19. 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.

  20. The First SeaWiFS HPLC Analysis Round-Robin Experiment (SeaHARRE-1)

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Claustre, Herve; Ras, Josephine; VanHeukelem, Laurie; Berthon, Jean-Francois; Targa, Cristina; vanderLinde, Dirk; Barlow, Ray; Sessions, Heather

    2001-01-01

    Four laboratories, which had contributed to various aspects of SeaWiFS calibration and validation activities, participated in the first SeaWiFS HPLC Analysis Round-Robin Experiment (SeaHARRE-1): Horn Point Laboratory (USA), the Joint Research Centre (Italy), the Laboratoire de Physique et Chimie Marines (France), and the Marine and Coastal Management group (South Africa). The analyses of the data are presented in Chapter 1 and the individual methods of the four groups are presented in Chapters 2-5. The average (or overall) conclusions of the round-robin are derived from 12 in situ stations occupied during a cruise in the Mediterranean Sea, although, only 11 stations are used in the analyses. The data set is composed of 12 replicates taken during each sampling opportunity with 3 replicates going to each of the 4 laboratories. The average (or overall) results from the intercomparison of 15 pigments or pigment associations are as follows (in some cases, data subsets that exclude pigments which were not analyzed by all the laboratories, or that had unusually large variances, are used to exclude a variety of problematic pigments): a) the accuracy of the four methods in determining the concentration of total chlorophyll a is 7.9%, (one method did not separate mono- and divinyl chlorophyll a, and if the samples containing significant divinyl chlorophyll a concentrations are ignored, the four methods have an accuracy of 6.7%); b) the accuracy in determining the full set of pigments is 19.1%; c) there is a reduction in accuracy of approximately - 12.2% for every decade (factor of 10) decrease in concentration (based on a data subset); d) the precision of the four methods using a subset data is 8.617( 6.2% for an edited subset); e) the repeatability of the four methods using the subset data is 9.2% (7.2%; for an edited subset, and f) the reproducibility of the four methods using the subset data is 21.31% (15.0% for an edited subset).

  1. 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.)

  2. 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.

  3. 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

  4. A M2FS Spectroscopic Study of Low-mass Young Stars in Orion OB1

    Science.gov (United States)

    Kaleida, Catherine C.; Briceno, Cesar; Calvet, Nuria; Mateo, Mario L.; Hernandez, Jesus

    2015-01-01

    Surveys of pre-main sequence stars in the ~4-10 Myr range provide a window into the decline of the accretion phase of stars and the formation of planets. Nearby star clusters and stellar associations allow for the study of these young stellar populations all the way down to the lowest mass members. One of the best examples of nearby 4-10 Myr old stellar populations is the Orion OB1 association. The CIDA Variability Survey of Orion OB1 (CVSO - Briceño et al. 2001) has used the variability properties of low-mass pre-main-sequence (PMS) stars to identify hundreds of K and M-type stellar members of the Orion OB1 association, a number of them displaying IR-excess emission and thought to be representative of more evolved disk-bearing young stars. Characterizing these young, low-mass objects using spectroscopy is integral to understanding the accretion phase in young stars. We present preliminary results of a spectroscopic survey of candidate and confirmed Orion OB1 low-mass members taken during November 2014 and February 2014 using the Michigan/Magellan Fiber Spectrograph (M2FS), a PI instrument on the Magellan Clay Telescope (PI: M. Matteo). Target fields located in the off-cloud regions of Orion were identified in the CVSO, and observed using the low and high-resolution modes of M2FS. Both low and high-resolution spectra are needed in order to confirm membership and derive masses, ages, kinematics and accretion properties. Initial analysis of these spectra reveal many new K and M-type members of the Orion OB1 association in these low extinction, off-cloud areas. These are the more evolved siblings of the youngest stars still embedded in the molecular clouds, like those in the Orion Nebula Cluster. With membership and spectroscopic indicators of accretion we are building the most comprehensive stellar census of this association, enabling us to derive a robust estimate of the fraction of young stars still accreting at a various ages, a key constraint for the end of

  5. Identification of three redundant segments responsible for herpes simplex virus 1 ICP0 to fuse with ND10 nuclear bodies.

    Science.gov (United States)

    Zheng, Yi; Gu, Haidong

    2015-04-01

    Infected cell protein 0 (ICP0) of herpes simplex virus 1 (HSV-1) is a key regulator in both lytic and latent infections. In lytic infection, an important early event is the colocalization of ICP0 to nuclear domain 10 (ND10), the discrete nuclear bodies that impose restrictions on viral expression. ICP0 contains an E3 ubiquitin ligase that degrades promyelocytic leukemia protein (PML) and Sp100, two major components of ND10, and disperses ND10 to alleviate repression. We previously reported that the association between ICP0 and ND10 is a dynamic process that includes three steps: adhesion, fusion, and retention. ICP0 residues 245 to 474, defined as ND10 entry signal (ND10-ES), is a region required for the fusion step. Without ND10-ES, ICP0 adheres at the ND10 surface but fails to enter. In the present study, we focus on characterizing ND10-ES. Here we report the following. (i) Fusion of ICP0 with ND10 relies on specific sequences located within ND10-ES. Replacement of ND10-ES by the corresponding region from ORF61 of varicella-zoster virus did not rescue ND10 fusion. (ii) Three tandem ND10 fusion segments (ND10-FS1, ND10-FS2, and ND10-FS3), encompassing 200 amino acids within ND10-ES, redundantly facilitate fusion. Each of the three segments is sufficient to independently drive the fusion process, but none of the segments by themselves are necessary for ND10 fusion. Only when all three segments are deleted is fusion blocked. (iii) The SUMO interaction motif located within ND10-FS2 is not required for ND10 fusion but is required for the complete degradation of PML, suggesting that PML degradation and ND10 fusion are regulated by different molecular mechanisms. ND10 nuclear bodies are part of the cell-intrinsic antiviral defenses that restrict viral gene expression upon virus infection. As a countermeasure, infected cell protein 0 (ICP0) of herpes simplex virus 1 (HSV-1) localizes to ND10s, degrades the ND10 organizer, and disperses ND10 components in order to

  6. Time-dependent Bloch-Maxwell modelling of 1 mJ, 200 fs seeded soft x-ray laser

    International Nuclear Information System (INIS)

    Zeitoun, Ph.; Oliva, E.; Fajardo, M.; Velarde, P.; Ros, D.; Sebban, S.

    2010-01-01

    Complete text of publication follows. Seeding of high harmonic generation in a soft x-ray plasma amplifier has been first proposed and tested by T. Ditmire and collaborators. The experiment demonstrated low amplification (*2), with a very strong background coming from the soft x-ray laser ASE. Later seeding experiments reached very high amplification factors (up to 600) in both gas (Ph. Zeitoun et al.) and solid amplifiers (Wang et at.). Surprisingly, solid amplifiers extracted less energy (90 nJ) than gas amplifier (∼ 1 μJ) with equivalent pump energy. We recently demonstrated that 50-100 μJ is achievable with adequate plasma tailoring. However, this energy is still low as compared to the 10 mJ per pulse demonstrated on the ASE soft x-ray laser running at PALS facility (Czech Republic). In order to model the seeding process of PALS soft x-ray laser, we developed a time-dependent Bloch-Maxwell model that solves coherently the pumping, amplification and saturation processes. We demonstrated that direct seeding, with femtosecond pulse, a soft x-ray plasma amplifier having gain duration of several 100s of picosecond cannot extract the stored energy keeping the output beam energy in the 100 μJ range. We proposed and fully modelled a new seeding scheme that allows to achieve 10 mJ, 200 fs soft x-ray laser.

  7. 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) ...

  8. Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Yoon, Ji Hyun; Lee, Bong Sang [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

    2017-08-15

    The precise prediction of radiation embrittlement of aged reactor pressure vessels (RPVs) is a prerequisite for the long-term operation of nuclear power plants beyond their original design life. The expiration of the operation licenses for Korean reactors the RPVs of which are made from SA533B-1 plates and welds is imminent. Korean regulatory rules have adopted the US Nuclear Regulatory Commission's transition temperature shift (TTS) models to the prediction of the embrittlement of Korean reactor pressure vessels. The applicability of the TTS model to predict the embrittlement of Korean RPVs made of SA533B-1 plates and welds was investigated in this study. It was concluded that the TTS model of 10 CFR 50.61a matched the trends of the radiation embrittlement in the SA533B-1 plates and welds better than did that of Regulatory Guide (RG) 1.99 Rev. 2. This is attributed to the fact that the prediction performance of 10 CFR 50.61a was enhanced by considering the difference in radiation embrittlement sensitivity among the different types of RPV materials.

  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. Excited-state kinetics of the carotenoid S//1 state in LHC II and two-photon excitation spectra of lutein and beta-carotene in solution Efficient Car S//1 yields Chl electronic energy transfer via hot S//1 states?

    CERN Document Server

    Walla, P J; Linden, Patricia A; Ohta, Kaoru

    2002-01-01

    The excited-state dynamics of the carotenoids (Car) in light- harvesting complex II (LHC II) of Chlamydomonas reinhardtii were studied by transient absorption measurements. The decay of the Car S //1 population ranges from similar to 200 fs to over 7 ps, depending on the excitation and detection wavelengths. In contrast, a 200 fs Car S//1 yields Chlorophyll (Chl) energy transfer component was the dominant time constant for our earlier two-photon fluorescence up- conversion measurements (Walla, P.J. ; et al. J. Phys. Chem. B 2000, 104, 4799-4806). We also present the two-photon excitation (TPE) spectra of lutein and beta-carotene in solution and compare them with the TPE spectrum of LHC II. The TPE-spectrum of LHC II has an onset much further to the blue and a width that is narrower than expected from comparison to the S//1 fluorescence of lutein and beta-carotene in solution. Different environments may affect the shape of the S//1 spectrum significantly. To explain the blue shift of the TPE spectrum and the d...

  12. 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) ...

  13. 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) ...

  14. 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) ...

  15. 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) ...

  16. 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) ...

  17. 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) ...

  18. 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) ...

  19. 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

  20. 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

  1. EST Table: FS929848 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available DICTED: similar to Low density lipoprotein receptor adapter protein 1 (Autosomal recessive hypercholesterolemia...1| PREDICTED: similar to Low density lipoprotein receptor adapter protein 1 (Autosomal recessive hypercholesterolemia protein) isoform 1 [Tribolium castaneum] FS929848 fwgP ...

  2. EST Table: FS936166 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to Low density lipoprotein receptor adapter protein 1 (Autosomal recessive hypercholesterolemia protein) ... similar to Low density lipoprotein receptor adapter protein 1 (Autosomal recessive hypercholesterolemia protein) isoform 1 [Tribolium castaneum] FS929848 fwgP ...

  3. Development and validation of library MUSE-F1.0

    International Nuclear Information System (INIS)

    Tang Haibo; Chen Yixue; Wu Jun

    2013-01-01

    The multi-group transport library MUSE-F1.0 based on ENDF/B-VII.0 with 175-group neutron and 42-group photon was developed by NJOY99. Weighting function is thermal--l/e--fast reactor-fission + fusion, and Legendre order is six. The library was validated by a series of critical and shielding benchmarks. The shielding test involves nuclear data including fission reactor, fusion reactor and accelerator. The result shows that MUSE-F1.0 is suitable for critical and shielding calculation. And it is competent for the application of fast neutron reactor design. (authors)

  4. Chlorophyll-a, Orbview-2 SeaWiFS, 0.1 degrees, Global

    Data.gov (United States)

    National Oceanic and Atmospheric Administration, Department of Commerce — NASA GSFC Ocean Color Web distributes science-quality chlorophyll-a concentration data from the Sea-viewing Wide Field-of-view Sensor (SeaWiFS) on the Orbview-2...

  5. 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) ...

  6. 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) ...

  7. 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) ...

  8. 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)

  9. EST Table: FS759318 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available 25 aa ref|XP_975608.1| PREDICTED: similar to putative lysosomal glucocerebrosidas...%/225 aa gi|91087345|ref|XP_975608.1| PREDICTED: similar to putative lysosomal glucocerebrosidase [Tribolium castaneum] FS759318 fcaL ...

  10. ''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

  11. EST Table: FS891321 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available /28 46 %/153 aa ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium c...86783|ref|XP_973163.1| PREDICTED: similar to jumping translocation breakpoint protein [Tribolium castaneum] FS891321 ftes ...

  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. 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.

  14. 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

  15. Erratum!- in paper volume 19, Supplement 1, Year 2015, pp. S109-S115, DOI:10.2298/TSCI15S1S09C

    Directory of Open Access Journals (Sweden)

    Editorial

    2015-01-01

    Full Text Available In the paper published in THERMAL SCIENCE Volume 19, Supplement 1, YEAR 2015, pp. S109-S115, DOI REFERENCE: 10.2298/TSCI15S1S09C Names and affiliations of the authors has been incorrectly written Istead of: THE DIFFUSION MODEL OF FRACTAL HEAT AND MASS TRANSFER IN FLUIDIZED BED A Local Fractional Arbitrary Euler-Lagrange Formula by Xu CHENG∗ and Xiao-Xun MA School of Chemical Engineering, Northwest University, Xi'an, Shaanxi, China Correctly has to be written: THE DIFFUSION MODEL OF FRACTAL HEAT AND MASS TRANSFER IN FLUIDIZED BED A Local Fractional Arbitrary Euler-Lagrange Formula by Xu CHENG1∗ and Lin Wang2 - 1School of Chemical Engineering, Northwest University, Xi'an, Shaanxi, China - 2Xi'an Modern Chemistry Research Institute, Xi'an, Shaanxi, China Link to the corrected article 10.2298/TSCI15S1S09C

  16. 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

  17. 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.

  18. 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

  19. EST Table: FS905368 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ...

  20. EST Table: FS931361 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fwgP ...

  1. EST Table: FS765476 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fcaL ...

  2. EST Table: FS791348 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 ffbm ...

  3. EST Table: FS909643 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available ar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] gb|EEZ97704.1| budding uninhibited by benzimidazoles...|XP_970295.1| PREDICTED: similar to BUB3 budding uninhibited by benzimidazoles 3 [Tribolium castaneum] FS920882 fufe ...

  4. Neutron Flux Variation in the Nigeria Research Reactor-1 (NIRR-1)

    International Nuclear Information System (INIS)

    Yahaya, M.; Ahmed, Y.A.

    2013-01-01

    In order to ascertain the level of flux variation in one of the inner irradiation channels of the Nigeria Research Reactor-1 (NIRR-1), the irradiation container used for routine activation analysis was employed with copper wires as flux monitors. Measurements were carried out with copper wires arranged in axial direction to determine the thermal neutron flux at selected positions using absolute foil activation method. Our results show that there exists a slight flux variation from one position to another ranging from (4.57±0.21) x 10 11 to (5.20± 0.20) x 10 11 cm -2 s -1 .Individual foil shows slight flux variation from one position to another in the same irradiation container but they all pointed toward a level of consistency in variation in spite of the recent installation of the cadmium lined irradiation channel. The values obtained in this work are in good agreement with the previously measured value of (5.14±0.24) x 10 11 cm -2 s -1 after commissioning of NIRR-1 (Jonah et al., 2005). This shows that the cadmium lined installation does not affect the flux stability. In order to improve the accuracy of NAA using NIRR-l facility, there is need for flux corrections to be made by MNSR users during NAA particularly for samples in the axial position for long irradiation.

  5. 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

  6. Femtosecond (FS) laser vision correction procedure for moderate to high myopia

    DEFF Research Database (Denmark)

    Vestergaard, Anders Højslet; Ivarsen, Anders; Asp, Sven

    2013-01-01

    Purpose:  To present our initial clinical experience with ReLEx(®) flex (ReLEx) for moderate to high myopia. We compare efficacy, safety and corneal higher-order aberrations after ReLEx with femtosecond laser in situ keratomileusis (FS-LASIK). Methods:  Prospective study of ReLEx compared...... with a retrospective study of FS-LASIK. ReLEx is a new keratorefractive procedure, where a stromal lenticule is cut by a femtosecond laser and manually extracted. Forty patients were treated with ReLEx on both eyes. A comparable group of 41 FS-LASIK patients were retrospectively identified. Visual acuity, spherical...... equivalent (SE) and corneal tomography were measured before and 3 months after surgery. Results:  Preoperative SE averaged -7.50 ± 1.16 D (ReLEx) and -7.32 ± 1.09 D (FS-LASIK). For all eyes, mean corrected distance visual acuity remained unchanged in both groups. For eyes with emmetropia as target refraction...

  7. Reproducibility of flap thickness with IntraLase FS and Moria LSK-1 and M2 microkeratomes.

    Science.gov (United States)

    Talamo, Jonathan H; Meltzer, Jeremy; Gardner, John

    2006-06-01

    To compare flap thickness reproducibility of the femtosecond laser and two mechanical microkeratomes. Flap thickness for all eyes was measured as the difference between the preoperative (day of surgery) full corneal thickness and post-flap creation central stromal bed thickness using ultrasonic pachymetry. Flap thickness values produced by three different microkeratome systems were compared for accuracy and reproducibility. For 99 flaps created using the IntraLase FS laser with an intended thickness of 110 microm, the mean achieved thickness was 119 +/- 12 microm (range: 82 to 149 microm). In 100 eyes treated with the Moria LSK-1 microkeratome with an intended flap thickness of 160 microm, the mean achieved thickness was 130 +/- 19 microm (range: 71 to 186 microm). In 135 eyes treated with the Moria M2 microkeratome with an intended flap thickness of 130 microm, mean thickness was 142 +/- 24 microm (range: 84 to 203 microm). The standard deviation and range of corneal flap thickness created with the IntraLase FS laser was significantly smaller than either mechanical microkeratome (P < .0001). When compared to two commonly used mechanical microkeratomes, mean achieved flap thickness was more reproducible with the IntraLase FS laser, reducing the comparative risk of overly thick flaps.

  8. 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.

  9. Dismantling of the reactor block of the FRJ-1 research reactor (MERLIN); Abbau des Reaktorblocks des Forschungsreaktors FRJ-1 (MERLIN)

    Energy Technology Data Exchange (ETDEWEB)

    Stahn, B.; Matela, K.; Zehbe, C. [Forschungszentrum Juelich GmbH (Germany); Poeppinghaus, J. [Gesellschaft fuer Nuklear-Service mbH, Essen (Germany); Cremer, J. [Siempelkamp Nukleartechnik GmbH, Heidelberg (Germany)

    2003-07-01

    By the end of 1998 the complete secondary cooling system and the major part of the primary cooling system were dismantled. Furthermore, the experimental devices, including a rabbit system conceived as an in-core irradiation device, were disassembled and disposed of. In total, approx. 65 t of contaminated and/or activated material as well as approx. 70 t of clearance-measured material were disposed of within the framework of these activities. The dismantling of the coolant loops and experimental devices was followed in 2000 by the removal of the reactor tank internals and the subsequent draining of the reactor tank water. The reactor tank internals were essentially the core support plate, the core box, the flow channel and the neutron flux bridges (s. Fig. 2, detailed reactor core). All components consisted of aluminium, the connecting elements such as bolts and nuts, however, of stainless steel. Due to the high activation of the core internals, disassembly had to be remotely controlled under water. All removal work was carried out from a tank intermediate floor (s. Fig. 2). These activities, which served for preparing the dismantling of the reactor block, were completed in summer 2001. The waste parts arising were transferred to the Service Department for Decontamination of the Research Centre. This included approx. 2.5 t of waste parts with a total activity of approx. 8 x 10{sup 11} Bq. (orig.)

  10. 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.

  11. Reactor Engineering Department annual report (April 1, 1996 - March 31, 1997)

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-10-01

    This report summarizes the research and development activities in the Reactor Engineering Department of JAERI during the fiscal year of 1996 (April 1, 1996 - March 31, 1997). The major Department`s programs promoted in the year are the design activities of advanced reactor system and the development of a high power proton linear accelerator to construct an intense neutron source for innovative neutron science. Other Major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analysis, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The 99 papers are indexed individually. (J.P.N.)

  12. Reactor operations at SAFARI-1

    International Nuclear Information System (INIS)

    Vlok, J.W.H.

    2003-01-01

    A vigorous commercial programme of isotope production and other radiation services has been followed by the SAFARI-1 research reactor over the past ten years - superimposed on the original purpose of the reactor to provide a basic tool for nuclear research, development and education to the country at an institutional level. A combination of the binding nature of the resulting contractual obligations and tighter regulatory control has demanded an equally vigorous programme of upgrading, replacement and renovation of many systems in order to improve the safety and reliability of the reactor. Not least among these changes is the more effective training and deployment of operations personnel that has been necessitated as the operational demands on the reactor evolved from five days per week to twenty four hours per day, seven days per week, with more than 300 days per year at full power. This paper briefly sketches the operational history of SAFARI-1 and then focuses on the training and structuring currently in place to meet the operational needs. There is a detailed step-by-step look at the operator?s career plan and pre-defined milestones. Shift work, especially the shift cycle, has a negative influence on the operator's career path development, especially due to his unavailability for training. Methods utilised to minimise this influence are presented. The increase of responsibilities regarding the operation of the reactor, ancillaries and experimental facilities as the operator progresses with his career are discussed. (author)

  13. 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...

  14. 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.

  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. Reactor core conversion studies of Ghana: Research Reactor-1 and proposal for addition of safety rod

    International Nuclear Information System (INIS)

    Odoi, H.C.

    2014-06-01

    The inclusion of an additional safety rod in conjunction with a core conversion study of Ghana Research Reactor-1 (GHARR-1) was carried out using neutronics, thermal hydraulics and burnup codes. The study is based on a recommendation by Integrated Safety Assessment for Research Reactors (INSARP) mission to incorporate a safety rod to the reactor safety system as well as the need to replace the reactor fuel with LEU. Conversion from one fuel type to another requires a complete re-evaluation of the safety analysis. Changes to the reactivity worth, shutdown margin, power density and material properties must be taken into account, and appropriate modifications made. Neutronics analysis including burnup was studied followed by thermal hydraulics analyses which comprise steady state and transients. Four computer codes were used for the analysis; MCNP, REBUS, PLTEP and PARET. The neutronics analysis revealed that the LEU core must be operated at 34 Kw in order to attain the flux of 1.0E12 n/cm 2 .s as the nominal flux of the HEU core. The auxiliary safety rod placed at a modified irradiation site gives a better worth than the cadmium capsules. For core excess reactivity of 4 mk, 348 fuel pins would be appropriate for the GHARR-1 LEU core. Results indicate that flux level of 1.0E12 n/cm 2 .s in the inner irradiation channel will not be compromised, if the power of the LEU core is increased to 34 kW. The GHARR-1 core using LEU-U0 2 -12.5% fuel can be operated for 23 shim cycles, with cycles length 2.5 years, for over 57 years at the 17 kW power level. All 23 LEU cycles meet the ∼ 4.0 mk excess reactivity required at the beginning of cycle . For comparison, the MNSR HEU reference core can also be operated for 23 shim cycles, but with a cycle length of 2.0 years for just over 46 years at 15.0kW power level. It is observed that the GHARR-1 core with LEU UO 2 fuel enriched to 12.5% and a power level of 34 kW can be operated ∼25% longer than the current HEU core operated at

  17. 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)

  18. Emission of PCDD/Fs from Domestic Combustion Using Various Woods, Biofuel and Coals

    Czech Academy of Sciences Publication Activity Database

    Ocelka, T.; Tomšej, T.; Horák, J.; Šyc, Michal; Krpec, K.; Hopan, F.; Stáňa, M.

    LVI, č. 2 (2010), s. 149-154 ISSN 1210-0471 R&D Projects: GA MŽP(CZ) SP/1A2/116/07; GA MŠk 2B08048 Institutional research plan: CEZ:AV0Z40720504 Keywords : combustion * solid fuels * emission factors Subject RIV: DI - Air Pollution ; Quality http://transactions.fs.vsb.cz/2010-2/1793.pdf

  19. 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

  20. Operation characteristics and conditions of training reactor VR-1

    International Nuclear Information System (INIS)

    Matejka, K.; Kolros, A.; Polach, S.; Sklenka, L.

    1994-01-01

    The first 3 years of operation of the VR-1 training reactor are reviewed. This period includes its physical start-up (preparation, implementation, results) and operation development as far as the current operating configuration of the reactor core. The physical start-up was commenced using a reactor core referred to as AZ A1, whose physical parameters had been verified by calculation and whose configuration was based on data tested experimentally on the SR-0 reactor at Vochov. The next operating core, labelled AZ A2, was already prepared during the test operation of the VR-1 reactor. Its configuration was such that both of the main horizontal channels, radial and tangential, could be employed. The configuration that followed, AZ A3, was an intermediate step before testing the graphite side reflector. The current reactor core, labelled AZ A3 G, was obtained by supplementing the previous core with a one-sided graphite side reflector. (Z.S.). 2 tabs., 11 figs., 2 refs

  1. 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

  2. Small Incision Lenticule Extraction (SMILE versus Femtosecond Laser-Assisted In Situ Keratomileusis (FS-LASIK for Myopia: A Systematic Review and Meta-Analysis.

    Directory of Open Access Journals (Sweden)

    Zeren Shen

    Full Text Available The goal of this study was to compare small incision lenticule extraction (SMILE with femtosecond laser-assisted in situ keratomileusis (FS-LASIK for treating myopia.The CENTRAL, EMBASE, PubMed databases and a Chinese database (SinoMed were searched in May of 2016. Twelve studies with 1,076 eyes, which included three randomized controlled trials (RCTs and nine cohorts, met our inclusion criteria. The overall quality of evidence was evaluated using the Grading of Recommendations Assessment, Development and Evaluation (GRADE working group framework. Data were extracted and analysed at three to six months postoperatively. Primary outcome measures included a loss of one or more lines of best spectacle corrected visual acuity (BSCVA, uncorrected visual acuity (UCVA of 20/20 or better, mean logMAR UCVA, postoperative mean spherical equivalent (SE and postoperative refraction within ±1.0 D of the target refraction. Secondary outcome measures included ocular surface disease index (OSDI, tear breakup time (TBUT and Schirmer's 1 test (S1T as dry eye parameters, along with corneal sensitivity.The overall quality of evidence was considered to be low to very low. Pooled results revealed no significant differences between the two groups with regard to a loss of one or more lines in the BSCVA (OR 1.71; 95% CI: 0.81, 3.63; P = 0.16, UCVA of 20/20 or better (OR 0.71; 95% CI: 0.44, 1.15; P = 0.16, logMAR UCVA (MD 0.00; 95% CI: -0.03, 0.04; P = 0.87, postoperative refractive SE (MD -0.00; 95% CI: -0.05, 0.05; P = 0.97 or postoperative refraction within ±1.0 D of the target refraction (OR 0.78; 95% CI: 0.22, 2.77; P = 0.70 within six months postoperatively. The pooled analysis also indicated that the FS-LASIK group suffered more severely from dry eye symptoms (OSDI; MD -6.68; 95% CI: -11.76, -2.00; P = 0.006 and lower corneal sensitivity (MD 12.40; 95% CI: 10.23, 14.56; P < 0.00001 at six months postoperatively.In conclusion, both FS-LASIK and SMILE are safe

  3. 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)

  4. Reactor engineering department annual report. April 1, 1994 - March 31, 1995

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1994 (April 1, 1994 - March 31, 1995). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal-hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author).

  5. Reactor Engineering Department annual report. April 1, 1997 - March 31, 1998

    Energy Technology Data Exchange (ETDEWEB)

    Ochiai, Masaaki; Ohnuki, Akira; Ono, Toshihiko [eds.] [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment] [and others

    1998-11-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1997 (April 1, 1997 - March 31, 1998). The major Department`s programs promoted in the year are the achievement of the world-strongest lasing of Free Electron Laser and the verification of the core thermal integrity during design basis events in PWRs. Other Major tasks of the Department are various basic researches on the advanced reactor system design studies, the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the reactor instrumentation, the reactor control/diagnosis, the thermal hydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermal hydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor, the fusion reactor and PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

  6. Reactor engineering department annual report. April 1, 1995 - March 31, 1996

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1996-09-01

    This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1995 (April 1, 1995 - March 31, 1996). The major Department`s programs promoted in the year are the design activities of advanced reactor system and development of a high intensity proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basics researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, the fusion neutronics, the radiation shielding, the reactor instrumentation, the reactor control/diagnosis, the thermalhydraulics and the technology developments related to the reactor engineering facilities, the accelerator facilities and the thermalhydraulic facilities. The cooperative works to JAERI`s major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC`s fast reactor project were also progressed. The activities of the research committees to which the Department takes a role of secretariat are also summarized in this report. (author)

  7. Demolition of the FRJ-1 research reactor (MERLIN); Abbau des Reaktorblocks des Forschungsreaktors FRJ-1 (MERLIN)

    Energy Technology Data Exchange (ETDEWEB)

    Stahn, B.; Matela, K.; Zehbe, C. [Forschungszentrum Juelich GmbH (Germany); Poeppinghaus, J. [Gesellschaft fuer Nuklearservice, Essen (Germany); Cremer, J. [SNT Siempelkamp Nukleartechnik, Heidelberg (Germany)

    2003-06-01

    FRJ-2 (MERLIN), the swimming pool reactor cooled and moderated by light water, was built at the then Juelich Nuclear Research Establishment (KFA) between 1958 and 1962. In the period between 1964 and 1985, it was used for. The reactor was decommissioned in 1985. Since 1996, most of the demolition work has been carried out under the leadership of a project team. The complete secondary cooling system was removed by late 1998. After the cooling loops and experimental installations had been taken out, the reactor vessel internals were removed in 2000 after the water had been drained from the reactor vessel. After the competent authority had granted a license, demolition of the reactor block, the central part of the research reactor, was begun in October 2001. In a first step, the reactor operating floor and the reactor attachment structures were removed by the GNS/SNT consortium charged with overall planning and execution of the job. This phase gave rise to approx. The reactor block proper is dismantled in a number of steps. A variety of proven cutting techniques are used for this purpose. Demolition of the reactor block is to be completed in the first half of 2003. (orig.) [German] Der mit Leichtwasser gekuehlte und moderierte Schwimmbad-Forschungsreaktor FRJ-2 (MERLIN) wurde von 1958 bis 1962 fuer die damalige Kernforschungsanlage Juelich (KFA) errichtet. Von 1964 bis 1985 wurde er fuer Experimente mit zunaechst 5 MW und spaeter 10 MW thermischer Leistung bei einem maximalen thermischen Neutronenfluss von 1,1.10{sup 14} n/cm{sup 2}s genutzt. Im Jahr 1985 stellte der Reaktor seinen Betrieb ein. Die Brennelemente wurden aus der Anlage entfernt und in die USA und nach Grossbritannien verbracht. Seit 1996 erfolgen die wesentlichen Abbautaetigkeiten unter Leitung eines verantwortlichen Projektteams. Bis Ende 1998 wurde das komplette Sekundaerkuehlsystem entfernt. Dem Abbau der Kuehlkreislaeufe und Experimentiereinrichtungen folgte im Jahr 2000 der Ausbau der

  8. (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.

  9. 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)

  10. 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$^{-1}$.

  11. 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

  12. 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.

  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. Computer Program of SIE ASME-NH (Revision 1.0) Code

    Energy Technology Data Exchange (ETDEWEB)

    Koo, Gyeong Hoi; Lee, J. H

    2008-01-15

    In this report, the SIE ASME (Structural Integrity Evaluations by ASME-NH) (Revision 1.0), which has a computerized implementation of ASME Pressure Vessels and Piping Code Section III Subsection NH rules, is developed to apply to the next generation reactor design subjecting to the elevated temperature operations over 500 .deg. C and over 30 years design lifetime, and the user's manual for this program is described in detail.

  15. 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.

  16. 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

  17. 40-fs hydrogen Raman laser

    Energy Technology Data Exchange (ETDEWEB)

    Didenko, N V; Konyashchenko, A V; Kostryukov, P V; Losev, L L; Pazyuk, V S [P N Lebedev Physics Institute, Russian Academy of Sciences, Moscow (Russian Federation); Tenyakov, S Yu [Avesta Ltd., Troitsk, Moscow (Russian Federation); Molchanov, V Ya; Chizhikov, S I; Yushkov, K B [National University of Science and Technology ' MISIS' , Acoustooptical Research Center, Moscow (Russian Federation)

    2015-12-31

    40-fs first Stokes pulses at a wavelength of 1.2 μm were generated in a hydrogen SRS-converter pumped by orthogonally polarised double chirped pulses of a Ti : sapphire laser. To obtain a Stokes pulse close to a transform-limited one, a programmed acousto-optic dispersive delay line was placed between the master oscillator and regenerative amplifier. The energy efficiency of Stokes radiation conversion reached 22%. (lasers)

  18. 40-fs hydrogen Raman laser

    International Nuclear Information System (INIS)

    Didenko, N V; Konyashchenko, A V; Kostryukov, P V; Losev, L L; Pazyuk, V S; Tenyakov, S Yu; Molchanov, V Ya; Chizhikov, S I; Yushkov, K B

    2015-01-01

    40-fs first Stokes pulses at a wavelength of 1.2 μm were generated in a hydrogen SRS-converter pumped by orthogonally polarised double chirped pulses of a Ti : sapphire laser. To obtain a Stokes pulse close to a transform-limited one, a programmed acousto-optic dispersive delay line was placed between the master oscillator and regenerative amplifier. The energy efficiency of Stokes radiation conversion reached 22%. (lasers)

  19. Reversal of OFI and CHF in Research Reactors Operating at 1 to 50 Bar. Version 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Kalimullah, M. [Argonne National Lab. (ANL), Argonne, IL (United States); Olson, A. P. [Argonne National Lab. (ANL), Argonne, IL (United States); Dionne, B. [Argonne National Lab. (ANL), Argonne, IL (United States); Feldman, E. E. [Argonne National Lab. (ANL), Argonne, IL (United States); Matos, J. E. [Argonne National Lab. (ANL), Argonne, IL (United States)

    2014-02-28

    The conditions at which the critical heat flux (CHF) and the heat flux at the onset of Ledinegg flow instability (OFI) are equal, are determined for a coolant channel with uniform heat flux as a function of five independent parameters: the channel exit pressure (P), heated length (Lh) , heated diameter (Dh), inlet temperature (Tin), and mass flux (G). A diagram is made by plotting the mass flux and heat flux at the OFI-CHF intersection (reversal from CHF > OFI to CHF < OFI as G increases) as a function of P (1 to 50 bar), for 36 combinations of the remaining three parameters (Lh , Dh , Tin): Lh = 0.28, 0.61, 1.18 m; Dh = 3, 4, 6, 8 mm; Tin = 30, 50, 70 °C. The use of the diagram to scope whether a research reactor is OFI-limited (below the curve) or CHF-limited based on the five parameters of its coolant channel is described. Justification for application of the diagram to research reactors with axially non-uniform heat flux is provided. Due to its limitations (uncertainties not included), the diagram cannot replace the detailed thermal-hydraulic analysis required for a reactor safety analysis. In order to make the OFI-CHF intersection diagram, two world-class CHF prediction methods (the Hall-Mudawar correlation and the extended Groeneveld 2006 table) are compared for 216 combinations of the five independent parameters. The two widely used OFI correlations (the Saha- Zuber and the Whittle-Forgan with η = 32.5) are also compared for the same combinations of the five parameters. The extended Groeneveld table and the Whittle-Forgan OFI correlation are selected for use in making the diagram. Using the above five design parameters, a research reactor can be represented by a point on the reversal diagram, and the diagram can be used to scope, without a thermal-hydraulic calculation, whether the OFI will occur before the CHF, or the CHF will occur before the OFI when the reactor power is increased keeping the five parameters fixed.

  20. 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.

  1. 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.

  2. 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.

  3. Small Incision Lenticule Extraction (SMILE) versus Femtosecond Laser-Assisted In Situ Keratomileusis (FS-LASIK) for Myopia: A Systematic Review and Meta-Analysis

    Science.gov (United States)

    Shen, Zeren; Shi, Keda; Yu, Yinhui; Yu, Xiaoning; Lin, Yuchen; Yao, Ke

    2016-01-01

    Purpose The goal of this study was to compare small incision lenticule extraction (SMILE) with femtosecond laser-assisted in situ keratomileusis (FS-LASIK) for treating myopia. Methods The CENTRAL, EMBASE, PubMed databases and a Chinese database (SinoMed) were searched in May of 2016. Twelve studies with 1,076 eyes, which included three randomized controlled trials (RCTs) and nine cohorts, met our inclusion criteria. The overall quality of evidence was evaluated using the Grading of Recommendations Assessment, Development and Evaluation (GRADE) working group framework. Data were extracted and analysed at three to six months postoperatively. Primary outcome measures included a loss of one or more lines of best spectacle corrected visual acuity (BSCVA), uncorrected visual acuity (UCVA) of 20/20 or better, mean logMAR UCVA, postoperative mean spherical equivalent (SE) and postoperative refraction within ±1.0 D of the target refraction. Secondary outcome measures included ocular surface disease index (OSDI), tear breakup time (TBUT) and Schirmer’s 1 test (S1T) as dry eye parameters, along with corneal sensitivity. Results The overall quality of evidence was considered to be low to very low. Pooled results revealed no significant differences between the two groups with regard to a loss of one or more lines in the BSCVA (OR 1.71; 95% CI: 0.81, 3.63; P = 0.16), UCVA of 20/20 or better (OR 0.71; 95% CI: 0.44, 1.15; P = 0.16), logMAR UCVA (MD 0.00; 95% CI: -0.03, 0.04; P = 0.87), postoperative refractive SE (MD -0.00; 95% CI: -0.05, 0.05; P = 0.97) or postoperative refraction within ±1.0 D of the target refraction (OR 0.78; 95% CI: 0.22, 2.77; P = 0.70) within six months postoperatively. The pooled analysis also indicated that the FS-LASIK group suffered more severely from dry eye symptoms (OSDI; MD -6.68; 95% CI: -11.76, -2.00; P = 0.006) and lower corneal sensitivity (MD 12.40; 95% CI: 10.23, 14.56; P LASIK and SMILE are safe, effective and predictable surgical

  4. 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.

  5. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... systems. (8) Emergency ac electrical power systems, including: Emergency diesel generators (EDGs...

  6. Dry Eye Disease following Refractive Surgery: A 12-Month Follow-Up of SMILE versus FS-LASIK in High Myopia

    Directory of Open Access Journals (Sweden)

    Bingjie Wang

    2015-01-01

    Full Text Available Purpose. To compare dry eye disease following SMILE versus FS-LASIK. Design. Prospective, nonrandomised, observational study. Patients. 90 patients undergoing refractive surgery for myopia were included. 47 eyes underwent SMILE and 43 eyes underwent FS-LASIK. Methods. Evaluation of dry eye disease was conducted preoperatively and at 1, 3, 6, and 12 months postoperatively, using the Salisbury Eye Evaluation Questionnaire (SEEQ and TBUT. Results. TBUT reduced following SMILE at 1 and 3 months (p<0.001 and at 1, 3, and 6 months following FS-LASIK (p<0.001. TBUT was greater following SMILE than FS-LASIK at 3, 6, and 12 months (p<0.001, p<0.001, and p=0.009, resp.. SEEQ scores increased (greater symptoms following SMILE at 1 month (p<0.001 and 3 months (p=0.003 and at 1, 3, and 6 months following FS-LASIK (p<0.001. SMILE produced lower SEEQ scores (fewer symptoms than FS-LASIK at 1, 3, and 6 months (p<0.001. Conclusion. SMILE produces less dry eye disease than FS-LASIK at 6 months postoperatively but demonstrates similar degrees of dry eye disease at 12 months.

  7. 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-10’s 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.

  8. EST Table: FS768084 [KAIKOcDNA[Archive

    Lifescience Database Archive (English)

    Full Text Available pro dipeptidase pepd/pepq(e.coli) [Aedes aegypti] gb|EAT39285.1| xaa-pro dipeptidase pepd/pepq(e.coli) [Aede... 57 %/201 aa gi|189233738|ref|XP_971576.2| PREDICTED: similar to xaa-pro dipeptidase pepd/pepq(e.coli) [Tribolium castaneum] FS768084 fcaL ...

  9. Extensive utilization of training reactor VR-1

    International Nuclear Information System (INIS)

    Matejka, Karel; Sklenka, Lubomir

    2003-01-01

    to provide special training for selected specialists from Czech and Slovak Nuclear Power Plants. Scientific research respects reactor parameters and requirements of the so-called clean reactor core (free from a major effect of the fission products). Research on VR-1 is mainly aimed at the preparation and testing of new educational methodologies, investigation of reactor lattice parameters, reactor dynamics study, research in the control equipment field, neutron detector calibration, etc. Information services and promotional activities in the nuclear power field are important parts of the reactor operation. Many visitors, mainly high school students, come to the reactor. The reactor staff prepares an attractive program including reactor operation. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. The plan for the training reactor VR-1 for the next 10 years covers essential activities (less important activities describes the annual plan for each year) in five fields: education activities, research activities, public relation activities, international cooperation, and human resources, innovation and new equipment.Education activities: Keeping the current state in the field number of user schools, number of students and number of offered experimental exercises; Improving existing experimental exercises and establishing new according requests users from Universities and Nuclear Engineering companies, for example: study of neutron noise and it's application, study of thermal effects, study of digital control systems, study of transmutation technologies ADTT, study of neutron detectors. Research activities: Seeking research activities which can use advantages of 'clean' core without temperature, pressure, burn-up feedback etc.; Continuing in study of the digitally controlled nuclear research reactors; Continuing development of control equipment the VR-1 reactor; Continuing wide co-operation with Czech and Slovak

  10. The advanced MAPLE reactor concept

    International Nuclear Information System (INIS)

    Lidstone, R.F.; Lee, A.G.; Gillespie, G.E.; Smith, H.J.

    1989-01-01

    High-flux neutron sources are continuing to be of interest both in Canada and internationally to support materials testing for advanced power reactors, new developments in extracted-neutron-beam applications, and commercial production of selected radioisotopes. The advanced MAPLE reactor concept has been developed to meet these needs. The advanced MAPLE reactor is a new tank-type D 2 O reactor that uses rodded low-enrichment uranium fuel in a compact annular core to generate peak thermal-neutron fluxes of 1 x 10 19 n·s -1 in a central irradiation rig with a thermal power output of 50 MW. Capital and incremental development costs are minimized by using MAPLE reactor technology to the greatest extent practicable

  11. 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)

  12. 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.

  13. A Compilation of Boiling Water Reactor Operational Experience for the United Kingdom's Office for Nuclear Regulation's Advanced Boiling Water Reactor Generic Design Assessment

    Energy Technology Data Exchange (ETDEWEB)

    Wheeler, Timothy A. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Liao, Huafei [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

    2014-12-01

    United States nuclear power plant Licensee Event Reports (LERs), submitted to the United States Nuclear Regulatory Commission (NRC) under law as required by 10 CFR 50.72 and 50.73 were evaluated for reliance to the United Kingdom’s Health and Safety Executive – Office for Nuclear Regulation’s (ONR) general design assessment of the Advanced Boiling Water Reactor (ABWR) design. An NRC compendium of LERs, compiled by Idaho National Laboratory over the time period January 1, 2000 through March 31, 2014, were sorted by BWR safety system and sorted into two categories: those events leading to a SCRAM, and those events which constituted a safety system failure. The LERs were then evaluated as to the relevance of the operational experience to the ABWR design.

  14. 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

  15. Design of a 2 kA, 30 fs Rf-Photoinjector for Waterbag Compression

    Science.gov (United States)

    van der Geer, S. B.; Luiten, O. J.; de Loos, M. J.

    Because uniformly filled ellipsoidal ‘waterbag’ bunches have linear self-fields in all dimensions, they do not suffer from space-charge induced brightness degradation. This in turn allows very efficient longitudinal compression of high-brightness bunches at sub or mildly relativistic energies, a parameter regime inaccessible up to now due to detrimental effects of non-linear space-charge forces. To demonstrate the feasibility of this approach, we investigate ballistic bunching of 1 MeV, 100 pC waterbag electron bunches, created in a half-cell rf-photogun, by means of a two-cell booster-compressor. Detailed GPT simulations of this table-top set-up are presented, including realistic fields, 3D space-charge effects, path-length differences and image charges at the cathode. It is shown that with a single 10MW S-band klystron and fields of 100 MV/m, 2kA peak current is attainable with a pulse duration of only 30 fs at a transverse normalized emittance of 1.5 μm.

  16. 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)

  17. 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.

  18. The SPHINX reactor for engineering tests

    International Nuclear Information System (INIS)

    Adamov, E.O.; Artamkin, K.N.; Bovin, A.P.; Bulkin, Y.M.; Kartashev, E.F.; Korneev, A.A.; Stenbok, I.A.; Terekhov, A.S.; Khmel'Shehikov, V.V.; Cherkashov, Y.M.

    1990-01-01

    A research reactor known as SPHINX is under development in the USSR. The reactor will be used mainly to carry out tests on mock-up power reactor fuel assemblies under close-to-normal parameters in experimental loop channels installed in the core and reflector of the reactor, as well as to test samples of structural materials in ampoule and loop channels. The SPHINX reactor is a channel-type reactor with light-water coolant and moderator. Maximum achievable neutron flux density in the experimental channels (cell composition 50% Fe, 50% H 2 O) is 1.1 X 10 15 neutrons/cm 2 · s for fast neutrons (E > 0.1 MeV) and 1.7 X 10 15 for thermal neutrons at a reactor power of 200 MW. The design concepts used represent a further development of the technical features which have met with approval in the MR and MIR channel-type engineering test reactors currently in use in the USSR. The 'in-pond channel' construction makes the facility flexible and eases the carrying out of experimental work while keeping discharges of radioactivity into the environment to a low level. The reactor and all associated buildings and constructions conform to modern radiation safety and environmental protection requirements

  19. 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...

  20. Electrical system regulations of the IEA-R1 reactor

    International Nuclear Information System (INIS)

    Mello, Jose Roberto de; Madi Filho, Tufic

    2013-01-01

    The IEA-R1 reactor of the Nuclear and Energy Research Institute (IPEN-CNEN/SP), is a research reactor open pool type, designed and built by the U.S. firm Babcock and Wilcox, having, as coolant and moderator, deionized light water and beryllium and graphite, as reflectors. Until about 1988, the reactor safety systems received power from only one source of energy. As an example, it may be cited the control desk that was powered only by the vital electrical system 220V, which, in case the electricity fails, is powered by the generator group: no-break 220V. In the years 1989 and 1990, a reform of the electrical system upgrading to increase the reactor power and, also, to meet the technical standards of the ABNT (Associacao Brasileira de Normas Tecnicas) was carried out. This work has the objective of showing the relationship between the electric power system and the IEA-R1 reactor security. Also, it demonstrates that, should some electrical power interruption occur, during the reactor operation, this occurrence would not start an accident event. (author)

  1. 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.)

  2. 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)

  3. TRAC-P validation test matrix. Revision 1.0

    Energy Technology Data Exchange (ETDEWEB)

    Hughes, E.D.; Boyack, B.E.

    1997-09-05

    This document briefly describes the elements of the Nuclear Regulatory Commission`s (NRC`s) software quality assurance program leading to software (code) qualification and identifies a test matrix for qualifying Transient Reactor Analysis Code (TRAC)-Pressurized Water Reactor Version (-P), or TRAC-P, to the NRC`s software quality assurance requirements. Code qualification is the outcome of several software life-cycle activities, specifically, (1) Requirements Definition, (2) Design, (3) Implementation, and (4) Qualification Testing. The major objective of this document is to define the TRAC-P Qualification Testing effort.

  4. 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

  5. Measurement of β/Λ ratio in IEA-R1 reactor using noise technique

    International Nuclear Information System (INIS)

    Moreira, J.M.L.; Kassar, E.

    1986-01-01

    The ratio β/Λ for the IEA-R1 reactor is obtained experimentally through the noise analysis technique. This technique is based on the determination of the power spectral density of the reactor neutron population, with the reactor in a subcritical state driven by a 'white' neutron source. A ratio β/Λ of 43,5 s -1 is estimated from the break frequency of the measured transfer function of the IEA-R1 reactor. (Author) [pt

  6. Safe decommissioning of the Romanian VVR-S research reactor

    International Nuclear Information System (INIS)

    Garlea, C.; Garlea, I.; Kelerman, C.; Rodna, A.

    2002-01-01

    The VVR-S Romania research reactor was operated between 1957-1997, at 2 MW nominal power, for research and radioisotopical production. The detailed decommissioning plan was developed between 1995-1998, in the frame of the International Atomic Energy Agency Technical assistance project ROM/9/017. The proposed strategy agreed by the counterpart as well as international experts was stage 1. In 1997, an independent analysis performed by European Commission experts, in the frame of PHARE project PH04.1/1994 was dedicated to the 'Study of Soviet Design Research Reactors', had consolidated the development of the project emphasizing technical options of safe management for radioactive wastes and VVR-S spent fuel. The paper presents the main technical aspects as well as those of social impact, which lead to the establishment of strategy for safe management of decommissioning. Technical analysis of the VVR-S reactor and associated radwaste facilities (Radioactive Waste Treatment Plant - Magurele and National Repository Baita-Bihor) proved the possibility of the classical method utilization for dismantling of the facility and treatment-conditioning-disposal of the arrised wastes in safe conditions. The decommissioning plan at stage 2 has been developed based on radiological safety assessment, evaluation of radwaste inventory (removed as well as preserved on site), cost analysis and environmental impact. Technical data were provided by the R and D programme including neutron calculations and experiments, radiological characterizing (for facility and its influence area), seismic analysis and environmental balance during the operation and after shut down of the reactor. A special chapter is dedicated to regulatory issues concerning the development of decommissioning under nuclear safety. Based on the Fundamental Norms of Radiological Safety, the Regulatory Body defined the clearance levels and safety criteria for the process. The development of National Norms for the

  7. Catalytic decomposition of gaseous 1,2-dichlorobenzene over CuOx/TiO₂ and CuOx/TiO₂-CNTs catalysts: Mechanism and PCDD/Fs formation.

    Science.gov (United States)

    Wang, Qiu-lin; Huang, Qun-xing; Wu, Hui-fan; Lu, Sheng-yong; Wu, Hai-long; Li, Xiao-dong; Yan, Jian-hua

    2016-02-01

    Gaseous 1,2-dichlorobenzene (1,2-DCBz) was catalytically decomposed in a fixed-bed catalytic reactor using composite copper-based titanium oxide (CuOx/TiO2) catalysts with different copper ratios. Carbon nanotubes (CNTs) were introduced to produce novel CuOx/TiO2-CNTs catalysts by the sol-gel method. The catalytic performances of CuOx/TiO2 and CuOx/TiO2-CNTs on 1,2-DCBz oxidative destruction under different temperatures (150-350 °C) were experimentally examined and the correlation between catalyst structure and catalytic activity was characterized and the role of oxygen in catalytic reaction was discussed. Polychlorinated dibenzo-p-dioxins and dibenzofurans (PCDD/Fs) generation during 1,2-DCBz catalytic oxidation by CuOx/TiO2-CNTs composite catalyst was also examined. Results indicate that the 1,2-DCBz destruction/removal efficiencies of CuOx (4 wt%)/TiO2 catalyst at 150 °C and 350 °C with a GHSV of 3400 h(-1) are 59% and 94% respectively and low-temperature (150 °C) catalytic activity of CuOx/TiO2 on 1,2-DCBz oxidation can be improved from 59 to 77% when CNTs are introduced. Furthermore, oxygen either in catalyst or from reaction atmosphere is indispensible in reaction. The former is offered to activate and oxidize the 1,2-DCBz adsorbed on catalyst, thus can be generally consumed during reaction and the oxygen content in catalyst is observed lost from 39.9 to 35.0 wt% after reacting under inert atmosphere; the latter may replenish the vacancy in catalyst created by the consumed oxygen thus extends the catalyst life and raises the destruction/removal efficiency. The introduction of CNTs also increases the Cu(2+)/Cu(+) ratio, chemisorbed oxygen concentration and surface lattice oxygen binding energy which are closely related with catalytic activity. PCDD/Fs is confirmed to be formed when 1,2-DCBz catalytically oxidized by CuOx/TiO2-CNTs composite catalyst with sufficient oxygen (21%), proper temperature (350 °C) and high concentration of 1,2-DCBz feed (120 ppm

  8. Monte Carlo Modeling Electronuclear Processes in Cascade Subcritical Reactor

    CERN Document Server

    Bznuni, S A; Zhamkochyan, V M; Polyanskii, A A; Sosnin, A N; Khudaverdian, A G

    2000-01-01

    Accelerator driven subcritical cascade reactor composed of the main thermal neutron reactor constructed analogous to the core of the VVER-1000 reactor and a booster-reactor, which is constructed similar to the core of the BN-350 fast breeder reactor, is taken as a model example. It is shown by means of Monte Carlo calculations that such system is a safe energy source (k_{eff}=0.94-0.98) and it is capable of transmuting produced radioactive wastes (neutron flux density in the thermal zone is PHI^{max} (r,z)=10^{14} n/(cm^{-2} s^{-1}), neutron flux in the fast zone is respectively equal PHI^{max} (r,z)=2.25 cdot 10^{15} n/(cm^{-2} s^{-1}) if the beam current of the proton accelerator is k_{eff}=0.98 and I=5.3 mA). Suggested configuration of the "cascade" reactor system essentially reduces the requirements on the proton accelerator current.

  9. 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

  10. [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.

  11. 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..."

  12. Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP.

    Science.gov (United States)

    Abrefah, R G; Sogbadji, R B M; Ampomah-Amoako, E; Birikorang, S A; Odoi, H C; Nyarko, B J B

    2011-01-01

    The MCNP model for the Ghana Research Reactor-1 was redesigned to incorporate a boron carbide-shielded irradiation channel in one of the outer irradiation channels. Extensive investigations were made before arriving at the final design of only one boron carbide covered outer irradiation channel; as all the other designs that were considered did not give desirable results of neutronic performance. The concept of redesigning a new MCNP model, which has a boron carbide-shielded channel is to equip the Ghana Research Reactor-1 with the means of performing efficient epithermal neutron activation analysis. After the simulation, a comparison of the results from the original MCNP model for the Ghana Research Reactor-1 and the new redesigned model of the boron carbide shielded channel was made. The final effective criticality of the original MCNP model for the GHARR-1 was recorded as 1.00402 while that of the new boron carbide designed model was recorded as 1.00282. Also, a final prompt neutron lifetime of 1.5245 × 10(-4)s was recorded for the new boron carbide designed model while a value of 1.5571 × 10(-7)s was recorded for the original MCNP design of the GHARR-1. Copyright © 2010 Elsevier Ltd. All rights reserved.

  13. A PC-based high temperature gas reactor simulator for Indonesian conceptual HTR reactor basic training

    Science.gov (United States)

    Syarip; Po, L. C. C.

    2018-05-01

    In planning for nuclear power plant construction in Indonesia, helium cooled high temperature reactor (HTR) is favorable for not relying upon water supply that might be interrupted by earthquake. In order to train its personnel, BATAN has cooperated with Micro-Simulation Technology of USA to develop a 200 MWt PC-based simulation model PCTRAN/HTR. It operates in Win10 environment with graphic user interface (GUI). Normal operation of startup, power maneuvering, shutdown and accidents including pipe breaks and complete loss of AC power have been conducted. A sample case of safety analysis simulation to demonstrate the inherent safety features of HTR was done for helium pipe break malfunction scenario. The analysis was done for the variation of primary coolant pipe break i.e. from 0,1% - 0,5 % and 1% - 10 % helium gas leakages, while the reactor was operated at the maximum constant power of 10 MWt. The result shows that the highest temperature of HTR fuel centerline and coolant were 1150 °C and 1296 °C respectively. With 10 kg/s of helium flow in the reactor core, the thermal power will back to the startup position after 1287 s of helium pipe break malfunction.

  14. 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)

  15. Neutronic studies in the enrichment reduction of research reactor IEAR-1

    International Nuclear Information System (INIS)

    Maiorino, J.R.; Fanaro, L.C.B.; Mai, L.A.; Ferreira, P.S.B.; Garone, J.G.M.

    1987-01-01

    In the present work the codes used by the Reactor Physics Division of IPEN-CNEN-SP in calculations for plate-type reactors are described analyzing research reactor IEAR-1. The IAEA model problem for a plate-type reactor 10 MW with high, medium and low enrichment is solved through different methodologies now in use at the RTF/IPEN-CNEN-SP (HAMMER and HAMMER-TECH-CITATION and LEO4-2DBP-UM) looking into the calculation capability for high to low enrichment conversion within the contract held with the IAEA (BRA-4661). Finally, present reactor configuration calculations are compared with experimental measurements with the aim to validate the calculation method. (Author)

  16. 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

  17. 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)

  18. Shielding assessment of the ETRR-1 Reactor Under power upgrading

    Energy Technology Data Exchange (ETDEWEB)

    Ahmad, E E [Reactor Department, Nuclear Research Center, Atomic Energy Authority, Cairo (Egypt)

    1997-12-31

    The assessment of existing shielding of the ETRR-1 reactor in case of power upgrading is presented and discussed. It was carried out using both the present EK-10 type fuel elements and some other types of fuel elements with different enrichments. The shielding requirements for the ETRR-1 when power is upgraded are also discussed. The optimization curves between the upgraded reactor power and the shield thickness are presented. The calculation have been made using the ANISN code with the DLC-75 data library. The results showed that the present shield necessitates an additional layer of steel with thickness of 10.20 and 25 cm. When its power is upgraded to 3, 6 and 10 MWt in order to cutoff all neutron energy groups to be adequately safe under normal operating conditions. 4 figs.

  19. [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.

  20. Thermal hydraulic and safety analyses for Pakistan Research Reactor-1

    International Nuclear Information System (INIS)

    Bokhari, I.H.; Israr, M.; Pervez, S.

    1999-01-01

    Thermal hydraulic and safety analysis of Pakistan Research Reactor-1 (PARR-1) utilizing low enriched uranium (LEU) fuel have been performed using computer code PARET. The present core comprises of 29 standard and 5 control fuel elements. Results of the thermal hydraulic analysis show that the core can be operated at a steady-state power level of 10 MW for a flow rate of 950 m 3 /h, with sufficient safety margins against ONB (onset of nucleate boiling) and DNB (departure from nucleate boiling). Safety analysis has been carried out for various modes of reactivity insertions. The events studied include: start-up accident; accidental drop of a fuel element in the core; flooding of a beam tube with water; removal of an in-pile experiment during reactor operation etc. For each of these transients, time histories of reactor power, energy released and clad surface temperature etc. were calculated. The results indicate that the peak clad temperatures remain well below the clad melting temperature during these accidents. It is therefore concluded that the reactor can be safely operated at 10 MW without compromising safety. (author)

  1. Instrumentation renewal at the FIR 1 research reactor in Finland

    International Nuclear Information System (INIS)

    Bars, Bruno; Kall, Leif

    1982-01-01

    The Finnish TRIGA Mark II reactor (FIR 1 100 kW, later 250 kW steady state power and pulsing capability up to 250 MW) has been in operation for 20 years. The reactor is the only research reactor in Finland and is an important research training and service facility, which obviously will be operated for 10...20 years ahead. The mechanical parts of the reactor are in good shape. Some minor modifications have previously been made in the instrumentation. However, the original instrumentation could hardly have been used for 10...20 years ahead without extensive modifications and modernization. After a careful evaluation and planning process the whole reactor instrumentation was renewed in 1981 at a cost of about 400 000 dollar. The renewal was carried out in cooperation with the Central Research Institute for Physics (KFKI) at the Hungarian Academy of Sciences, which delivered the nuclear part of the instrumentation and with the Finnish company Valmet Oy Instrument Works, which delivered the conventional instrumentation, including the automatic power control system and the control console. The instrumentation, which is located in-a new isolated control room is based on modern industrial standard modular units with standardized signal ranges, electronic testing possibilities, galvanically isolated outputs etc. The instrument renewal project was brought successfully to completion in November 1981 after only about 10 working days of shut down time. The reactor is now in routine operation and the experiences gained from the new instrumentation are excellent. (author)

  2. Very high flux steady state reactor and accelerator based sources

    International Nuclear Information System (INIS)

    Ludewig, H.; Todosow, M.; Simos, N.; Shapiro, S.; Hastings, J.

    2004-01-01

    With the number of steady state neutron sources in the US declining (including the demise of the Bnl HFBR) the remaining intense sources are now in Europe (i.e. reactors - ILL and FMR, accelerator - PSI). The intensity of the undisturbed thermal flux for sources currently in operation ranges from 10 14 n/cm 2 *s to 10 15 n/cm 2 *s. The proposed Advanced Neutron Source (ANS) was to be a high power reactor (about 350 MW) with a projected undisturbed thermal flux of 7*10 15 n/cm 2 *s but never materialized. The objective of the current study is to explore the requirements and implications of two source concepts with an undisturbed flux of 10 16 n/cm 2 *s. The first is a reactor based concept operating at high power density (10 MW/l - 15 MW/l) and a total power of 100 MW - 250 MW, depending on fissile enrichment. The second is an accelerator based concept relying on a 1 GeV - 1.5 GeV proton Linac with a total beam power of 40 MW and a liquid lead-bismuth eutectic target. In the reactor source study, the effects of fissile material enrichment, coolant temperature and pressure drop, and estimates of pressure vessel stress levels will be investigated. The fuel form for the reactor will be different from all other operating source reactors in that it is proposed to use an infiltrated graphitic structure, which has been developed for nuclear thermal propulsion reactor applications. In the accelerator based source the generation of spallation products and their activation levels, and the material damage sustained by the beam window will be investigated. (authors)

  3. A report on the transport of MTR-type spent fuel assemblies of the Philippine Research Reactor (PRR-1)

    International Nuclear Information System (INIS)

    Yoshisaki, Magno B.; Leopando, Leonardo S.

    1999-03-01

    Fifty one (51) fuel assemblies of mixed enrichment from the Philippine Research Reactor (PRR-1), consisting of 50 spent and 1 fresh, were shipped to the United States last 14 March 1999 under the U.S. Return of Foreign Research Reactor (FRR) fuel policy. The shipment was in line with the U.S. initiative to implement its Record of Decision (ROD) which took effect on 13 May 1996 to accept and manage all FRR uranium fuel of U.S. origin and enriched in the United States. The shipment program would last10 years, ending midnight of 13 May 2006. The ROD provided a 3 year extension period within which to accept FRR spent nuclear fuel (SNF) withdrawn from reactors after 2006. The U.S. policy gave priority to the NPT significance of high enriched U, as the prime target of the return of FRR policy. Classified as a developing country, the Philippines, through the PNRI, signed a contract with the U.S. Department of Energy for the cost-free shipment of PRR-1 spent fuel to the United States. Spent fuel loading and transport operations to the port area lasted seven (7) days, from 8 to 14 March 1999. (Author)

  4. SATURN-FS 1: A computer code for thermo-mechanical fuel rod analysis

    International Nuclear Information System (INIS)

    Ritzhaupt-Kleissl, H.J.; Heck, M.

    1993-09-01

    The SATURN-FS code was written as a general revision of the SATURN-2 code. SATURN-FS is capable to perform a complete thermomechanical analysis of a fuel pin, with all thermal, mechanical and irradiation-based effects. Analysis is possible for LWR and for LMFBR fuel pins. The thermal analysis consists of calculations of the temperature profile in fuel, gap and in the cladding. Pore migration, stoichiometry change of oxide fuel, gas release and diffusion effects are taken into account. The mechanical modeling allows the non steady-state analysis of elastic and nonelastic fuel pin behaviour, such as creep, strain hardening, recovery and stress relaxation. Fuel cracking and healing is taken into account as well as contact and friction between fuel and cladding. The modeling of the irradiation effects comprises swelling and fission gas production, Pu-migration and irradiation induced creep. The code structure, the models and the requirements for running the code are described in the report. Recommendations for the application are given. Program runs for verification and typical examples of application are given in the last part of this report. (orig.) [de

  5. Thermal neutron flux measurements in the rotary specimen rack of the IPR-R1 TRIGA reactor

    Energy Technology Data Exchange (ETDEWEB)

    Souza, Rose Mary G. do Prado; Rodrigues, Rogério R.; Souza, Luiz Claudio A., E-mail: souzarm@cdtn.br, E-mail: rrr@cdtn.br, E-mail: lcas@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The thermal neutron flux in the rotary specimen rack of the IPR-R1 TRIGA reactor at the Nuclear Technology Development Center (CDTN), Belo Horizonte, Brazil, has been measured by the neutron activation method, using bare and cadmium covered gold foils. Those foils were irradiated in the rotary specimen rack with the reactor at 100 kW. The reactor core configuration has 63 fuel elements, composed of 59 original aluminum-clad elements and 4 stainless steel-clad fuel elements. The gamma activities of the foils were measured using Ge spectrometer. The perturbations of the thermal neutron flux caused by the introduction of an absorbing foil into the medium were considered in order to obtain accurate determination of the flux. The thermal neutron flux obtained was 7.4 x 10{sup 11} n.cm{sup -2}.s{sup -1}. (author)

  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. Air quality assessment by tree bark biomonitoring in urban, industrial and rural environments of the Rhine Valley: PCDD/Fs, PCBs and trace metal evidence.

    Science.gov (United States)

    Guéguen, Florence; Stille, Peter; Millet, Maurice

    2011-09-01

    Tree barks were used as biomonitors to evaluate past atmospheric pollution within and around the industrial zones of Strasbourg (France) and Kehl (Germany) in the Rhine Valley. The here estimated residence time for trace metals, PCBs and PCDD/Fs in tree bark is >10 years. Thus, all pollution observed by tree bark biomonitoring can be older than 10 years. The PCB baseline concentration (sum of seven PCB indicators (Σ(7)PCB(ind))) determined on tree barks from a remote area in the Vosges mountains is 4 ng g(-1) and corresponds to 0.36 × 10(-3)ng toxic equivalent (TEQ) g(-1) for the dioxin-like PCBs (DL-PCBs). The northern Rhine harbor suffered especially from steel plant, waste incinerator and thermal power plant emissions. The polychlorinated dibenzo-p-dioxin and dibenzofuran (PCDD/Fs) concentrations analyzed in tree barks from this industrial area range between 392 and 1420 ng kg(-1) dry-weight (dw) corresponding to 3.9 ng TEQ(PCDD/Fs) kg(-1) to 17.8 ng TEQ(PCDD/Fs) kg(-1), respectively. Highest PCDD/F values of 7.2 ng TEQ kg(-1) to 17.8 ng TEQ kg(-1) have been observed close to and at a distance of fires might have been the reasons of these PCB enrichments. Other urban environments of the cities of Kehl and Strasbourg show significantly lower Σ(7)PCB(ind) concentrations. They suffer especially from road and river traffic and have typically Σ(7)PCB(ind) concentrations ranging from 11 ng g(-1) to 29 ng g(-1). The PCB concentration of 29 ng g(-1) has been found in tree bark close to the railway station of Strasbourg. Nevertheless, the corresponding TEQ(DL-PCB) are low and range between 0.2 × 10(-3) ng TEQ g(-1) and 7 × 10(-3) ng TEQ g(-1). Samples collected near road traffic are enriched in Fe, Sb, Sn and Pb. Cd enrichments were found close to almost all types of industries. Rural environments not far from industrial sites suffered from organic and inorganic pollution. In this case, TEQ(DL-PCB) values may reach up to 58 × 10(-3) ng TEQ g(-1) and the

  8. The analysis for inventory of experimental reactor high temperature gas reactor type

    International Nuclear Information System (INIS)

    Sri Kuntjoro; Pande Made Udiyani

    2016-01-01

    Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

  9. A pulsed neutron monochromatic beam at the ET-RR-1 reactor

    International Nuclear Information System (INIS)

    Adib, M.; Abdel-Kawy, A.; Eid, Y.; Maayouf, R.M.A.

    1985-01-01

    A pulsed neutron monochromatic beam, at the ET-RR-1 reactor, is produced by two 32 cm diameter rotors suspended in magnetic fields, whose centres are 126 cm apart rotating at speeds up to 16,000 rev/min. Each of the rotors has two slots, which are of constant cross-section in area - 7x10mm 2 , and are curved so that they have a maximum transmission for neutrons whose speed is 8.2 times that of the rotor tip. The jitter of the phase between the rotors at different rotation rates is found not to exceed +-1 μs. It has been found that both the observed time distribution and the TOF distribution of the neutrons at different rotation rates are in good agreement with the calculated ones. The observed intensity of the monochromatic neutrons of wavelength 2.74+-0.09 A, obtained by the rotors rotating at a speed of 10,500 rev/min with 864+-1 μs difference in phase between them, is 66.8 n/s. This value is found to be less than the predicted one by a factor of 5.5. (author)

  10. Physics and safety of advanced research reactors

    International Nuclear Information System (INIS)

    Boening, K.; Hardt, P. von der

    1987-01-01

    Advanced research reactor concepts are presently being developed in order to meet the neutron-based research needs of the nineties. Among these research reactors, which are characterized by an average power density of 1-10 MW per liter, highest priority is now generally given to the 'beam tube reactors'. These provide very high values of the thermal neutron flux (10 14 -10 16 cm -2 s -1 ) in a large volume outside of the reactor core, which can be used for sample irradiations and, in particular, for neutron scattering experiments. The paper first discusses the 'inverse flux trap concept' and the main physical aspects of the design and optimization of beam tube reactors. After that two examples of advanced research reactor projects are described which may be considered as two opposite extremes with respect to the physical optimization principle just mentioned. The present situation concerning cross section libraries and neutronic computer codes is more or less satisfactory. The safety analyses of advanced research reactors can largely be updated from those of current new designs, partially taking advantage of the immense volume of work done for power reactors. The paper indicates a few areas where generic problems for advanced research reactor safety are to be solved. (orig.)

  11. 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)

  12. Quality assurance in the manufacture of metallic uranium fuel for research reactors

    International Nuclear Information System (INIS)

    Shah, B.K.; Kumar, Arbind; Nanekar, P.P.; Vaidya, P.R.

    2009-01-01

    Two Research Reactors viz. CIRUS and DHRUVA are operating at Trombay since 1960 and 1985 respectively. Cirus is a 40 MWth reactor using heavy water as moderator and light water as coolant. Dhruva is a 100 MWth reactor using heavy water as moderator and coolant. The maximum neutron flux of these reactors are 6.7 x 10 13 n/cm 2 /s (Cirus) and 1.8 x 10 14 n/cm 2 /s (Dhruva). Both these reactors are used for basic research, R and D in reactor technology, isotope production and operator training. Fuel material for these reactors is natural uranium metallic rods claded in finned aluminium (99.5%) tubes. This presentation will discuss various issues related to fabrication quality assurance and reactor behavior of metallic uranium fuel used in research reactors

  13. 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.

  14. 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.

  15. Reactivity feedback coefficients Pakistan research reactor-1 using PRIDE code

    Energy Technology Data Exchange (ETDEWEB)

    Mansoor, Ali; Ahmed, Siraj-ul-Islam; Khan, Rustam [Pakistan Institute of Engineering and Applied Sciences, Islamabad (Pakistan). Dept. of Nuclear Engineering; Inam-ul-Haq [Comsats Institute of Information Technology, Islamabad (Pakistan). Dept. of Physics

    2017-05-15

    Results of the analyses performed for fuel, moderator and void's temperature feedback reactivity coefficients for the first high power core configuration of Pakistan Research Reactor - 1 (PARR-1) are summarized. For this purpose, a validated three dimensional model of PARR-1 core was developed and confirmed against the reference results for reactivity calculations. The ''Program for Reactor In-Core Analysis using Diffusion Equation'' (PRIDE) code was used for development of global (3-dimensional) model in conjunction with WIMSD4 for lattice cell modeling. Values for isothermal fuel, moderator and void's temperature feedback reactivity coefficients have been calculated. Additionally, flux profiles for the five energy groups were also generated.

  16. 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) ...

  17. Welding of the A1 reactor pressure vessel

    International Nuclear Information System (INIS)

    Becka, J.

    1975-01-01

    As concerns welding, the A-1 reactor pressure vessel represents a geometrically complex unit containing 1492 welded joints. The length of welded sections varies between 10 and 620 mm. At an operating temperature of 120 degC and a pressure of 650 N/cm 2 the welded joints in the reactor core are exposed to an integral dose of 3x10 18 n/cm 2 . The chemical composition is shown for pressure vessel steel as specified by CSN 413090.9 modified by Ni, Ti and Al additions, and for the welding electrodes used. The requirements are also shown for the mechanical properties of the base and the weld metals. The technique and conditions of welding are described. No defects were found in ultrasonic testing of welded joints. (J.B.)

  18. 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.

  19. Emission profiles of polychlorinated dibenzodioxins, polychlorinated dibenzofurans (PCDD/Fs), dioxin-like PCBs and hexachlorobenzene (HCB) from secondary metallurgy industries in Portugal.

    Science.gov (United States)

    Antunes, Pedro; Viana, Paula; Vinhas, Tereza; Rivera, J; Gaspar, Elvira M S M

    2012-09-01

    This paper reports, for the first time, a study of dioxin emissions from 10 siderurgies and metallurgies, secondary copper, aluminum and lead metallurgies, in Portugal. The study reports the emission factors and total emission amounts of PCDD/Fs, dioxin-like PCBs and hexachlorobenzene (HCB). The congener patterns were characterized and are discussed. The results showed that the total amount of PCDFs is higher than PCDDs in flue gas of each industrial unit. The toxic equivalent emission factors of pollutants emitted are 3098-3338 ngI-TEQt(-1) for PCDD/Fs and 597-659 ng I-TEQt(-1) for dioxin-like PCBs in siderurgies production (total estimated emission amounts released to atmosphere of 3.9-4.5 g I-TEQyr(-1)), 50-152 ng I-TEQt(-1) for PCDD/Fs and 24-121 ng I-TEQt(-1) for dioxin-like PCBs in ferrous foundries production (total estimated emission amounts released to atmosphere of 0.0010-0.0016 g I-TEQyr(-1)) and 5.8-5715 ng I-TEQt(-1) for PCDD/Fs and 0.49-259 ng I-TEQt(-1) for dioxin-like PCBs in non-ferrous foundries production (total estimated emission amounts released to atmosphere of 0.00014-0.12 g I-TEQyr(-1)). The HCB emission from siderurgies production is 0.94-3.2 mg t(-1) (total estimated emission amounts released 0.94-3.8 g yr(-1)), being much smaller, residual, in the emissions of the other types of plants (0.0012-0.026 mg t(-1) production and total estimated emission amounts released to atmosphere of 0.013-1.7 mg yr(-1)). Copyright © 2012 Elsevier Ltd. All rights reserved.

  20. Power Trip Set-points of Reactor Protection System for New Research Reactor

    International Nuclear Information System (INIS)

    Lee, Byeonghee; Yang, Soohyung

    2013-01-01

    This paper deals with the trip set-point related to the reactor power considering the reactivity induced accident (RIA) of new research reactor. The possible scenarios of reactivity induced accidents were simulated and the effects of trip set-point on the critical heat flux ratio (CHFR) were calculated. The proper trip set-points which meet the acceptance criterion and guarantee sufficient margins from normal operation were then determined. The three different trip set-points related to the reactor power are determined based on the RIA of new research reactor during FP condition, over 0.1%FP and under 0.1%FP. Under various reactivity insertion rates, the CHFR are calculated and checked whether they meet the acceptance criterion. For RIA at FP condition, the acceptance criterion can be satisfied even if high power set-point is only used for reactor trip. Since the design of the reactor is still progressing and need a safety margin for possible design changes, 18 MW is recommended as a high power set-point. For RIA at 0.1%FP, high power setpoint of 18 MW and high log rate of 10%pp/s works well and acceptance criterion is satisfied. For under 0.1% FP operations, the application of high log rate is necessary for satisfying the acceptance criterion. Considering possible decrease of CHFR margin due to design changes, the high log rate is suggested to be 8%pp/s. Suggested trip set-points have been identified based on preliminary design data for new research reactor; therefore, these trip set-points will be re-established by considering design progress of the reactor. The reactor protection system (RPS) of new research reactor is designed for safe shutdown of the reactor and preventing the release of radioactive material to environment. The trip set point of RPS is essential for reactor safety, therefore should be determined to mitigate the consequences from accidents. At the same time, the trip set-point should secure margins from normal operational condition to avoid

  1. Fs-transient absorption and fluorescence upconversion after two- photon excitation of carotenoids in solution and in LHC II

    CERN Document Server

    Wall, P J; Fleming, G R

    2000-01-01

    With time resolved two-photon techniques we determined the lifetime and two-photon spectrum of the forbidden S/sub 1/ state of beta - carotene (9+or-0.2 ps), lutein (15+or-0.5 ps) and the energy transferring carotenoids in LHC II (250+or-50 fs). (7 refs).

  2. 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

  3. 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) ...

  4. 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) ...

  5. 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) ...

  6. Stationary low power reactor No. 1 (SL-1) accident site decontamination ampersand dismantlement project

    International Nuclear Information System (INIS)

    Perry, E.F.

    1995-01-01

    The Army Reactor Area (ARA) II was constructed in the late 1950s as a test site for the Stationary Low Power Reactor No. 1 (SL-1). The SL-1 was a prototype power and heat source developed for use at remote military bases using a direct cycle, boiling water, natural circulation reactor designed to operate at a thermal power of 3,000 kW. The ARA II compound encompassed 3 acres and was comprised of (a) the SL-1 Reactor Building, (b) eight support facilities, (c) 50,000-gallon raw water storage tank, (d) electrical substation, (e) aboveground 1,400-gallon heating oil tank, (f) underground 1,000-gallon hazardous waste storage tank, and (g) belowground power, sewer, and water systems. The reactor building was a cylindrical, aboveground facility, 39 ft in diameter and 48 ft high. The lower portion of the building contained the reactor pressure vessel surrounded by gravel shielding. Above the pressure vessel, in the center portion of the building, was a turbine generator and plant support equipment. The upper section of the building contained an air cooled condenser and its circulation fan. The major support facilities included a 2,500 ft 2 two story, cinder block administrative building; two 4,000 ft 2 single story, steel frame office buildings; a 850 ft 2 steel framed, metal sided PL condenser building, and a 550 ft 2 steel framed decontamination and laydown building

  7. 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) ...

  8. 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 ...

  9. 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) ...

  10. 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) ...

  11. Heat transfer for ultrahigh flux reactor

    International Nuclear Information System (INIS)

    Wadkins, R.P.; Lake, J.A.; Oh, C.H.

    1987-01-01

    The use of a uniquely designed nuclear reactor to supply neutrons for materials research is the focus of recent reactor design efforts. The biological, materials, and fundamental physics aspects of research require neutron fluxes much higher than present research and testing facilities can produce. The most advanced research using neutrons as probing detectors is being done in the High Flux Reactor at the Institut Laue Langeuin, France. The design of a reactor that can produce neutron fluxes of 1.0 x 10 16 n/cm 2 .s requires a relatively high power (300 MW range) and a small core volume (approximately 30 liters). This combination of power and volume leads to a high power density which places increased demands on thermal hydraulic margins

  12. Reactor dynamics experiment of N.S. Mutsu using pseudo random signal. 1

    International Nuclear Information System (INIS)

    Hayashi, Koji; Nabeshima, Kunihiko; Shinohara, Yoshikuni; Shimazaki, Junya; Inoue, Kimihiko; Ochiai, Masaaki.

    1993-10-01

    In order to investigate dynamics of the reactor plant of the nuclear ship Mutsu, reactor noise experiments using pseudo random binary sequences (PRBS) have been planned, and a preliminary experiment was performed on March 4, 1991 in the first experimental navigation with the aim of checking the experimental procedures and conditions. The experiments using both reactivity and load disturbances were performed at 70 % of reactor power and under a quiet sea condition. Each PRBS was applied by manual operation of the control rod or the main steam valve. Various signals of the plant responses and of the acceleration of ship motion were measured. From the results obtained, we confirmed that (1) the procedures and experimental conditions determined prior to the experiment were suitable for performing the PRBS experiments, (2) when the PRBS disturbances were applied, the plant state remained quite stable, and (3) the quality of the measured data is adequate for the purpose of dynamics analysis. This paper summarizes the planning and preparation of the experiment, the instruction for the experiment and logs, the data recording conditions, recorded signal wave forms and the results of power spectral analysis. (author)

  13. Integral Inherently Safe Light Water Reactor (I2S-LWR)

    International Nuclear Information System (INIS)

    Petrovic, Bojan; Memmott, Matthew; Boy, Guy; Charit, Indrajit; Manera, Annalisa; Downar, Thomas; Lee, John; Muldrow, Lycurgus; Upadhyaya, Belle; Hines, Wesley; Haghighat, Alierza

    2017-01-01

    This final report summarizes results of the multi-year effort performed during the period 2/2013- 12/2016 under the DOE NEUP IRP Project ''Integral Inherently Safe Light Water Reactors (I 2 S-LWR)''. The goal of the project was to develop a concept of a 1 GWe PWR with integral configuration and inherent safety features, at the same time accounting for lessons learned from the Fukushima accident, and keeping in mind the economic viability of the new concept. Essentially (see Figure 1-1) the project aimed to implement attractive safety features, typically found only in SMRs, to a larger power (1 GWe) reactor, to address the preference of some utilities in the US power market for unit power level on the order of 1 GWe.

  14. Selecting a MAPLE research reactor core for 1-10 mW operation

    International Nuclear Information System (INIS)

    Smith, H.J.; Roy, M.-F.; Carlson, P.A.

    1986-06-01

    The MAPLE class of research reactors is designed so that a single reactor concept can satisfy a wide range of practical applications. This paper reports the results of physics studies performed on a number of potential core configurations fuelled with either 5 w/o or 8 w/o enriched UO 2 or 20 w/o U 3 Si-Al and assesses the relative merits of each. Recommended core designs are given to maximize the neutron fluxes available for scientific application and isotope production

  15. 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

  16. 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)

  17. 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)

  18. 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

  19. 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)

  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. 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.

  3. Stylized whole-core benchmark of the Integral Inherently Safe Light Water Reactor (I2S-LWR) concept

    International Nuclear Information System (INIS)

    Hon, Ryan; Kooreman, Gabriel; Rahnema, Farzad; Petrovic, Bojan

    2017-01-01

    Highlights: • A stylized benchmark specification of the I2S-LWR core. • A library of cross sections were generated in both 8 and 47 groups. • Monte Carlo solutions generated for the 8 group library using MCNP5. • Cross sections and pin fission densities provided in journal’s repository. - Abstract: The Integral, Inherently Safe Light Water Reactor (I 2 S-LWR) is a pressurized water reactor (PWR) concept under development by a multi-institutional team led by Georgia Tech. The core is similar in size to small 2-loop PWRs while having the power level of current large reactors (∼1000 MWe) but using uranium silicide fuel and advanced stainless steel cladding. A stylized benchmark specification of the I 2 S-LWR core has been developed in order to test whole-core neutronics codes and methods. For simplification the core was split into 57 distinct material regions for cross section generation. Cross sections were generated using the lattice physics code HELIOS version 1.10 in both 8 and 47 groups. Monte Carlo solutions, including eigenvalue and pin fission densities, were generated for the 8 group library using MCNP5. Due to space limitations in this paper, the full cross section library and normalized pin fission density results are provided in the journal’s electronic repository.

  4. Transformation of 1,1,1-trichloroethane in an anaerobic packed-bed reactor at various concentrations of 1,1,1-trichloroethane, acetate and sulfate

    NARCIS (Netherlands)

    deBest, JH; Jongema, H; Weijling, A; Doddema, HJ; Janssen, DB; Harder, W

    Biotransformation of 1,1,1-trichloroethane (CH3CCl3) was observed in an anaerobic packed-bed reactor under conditions of both sulfate reduction and methanogenesis. Acetate (1 mM) served as an electron donor. CH3CCl3 was completely converted up to the highest investigated concentration of 10 mu M.

  5. Training courses at VR-1 reactor

    International Nuclear Information System (INIS)

    Sklenka, L.; Kropik, M.

    2006-01-01

    This paper describes one of the main purposes of the VR-1 training reactor utilization - i.e. extensive educational program. The educational program is intended for the training of university students and selected nuclear power plant personnel. The training courses provide them experience in reactor and neutron physics, dosimetry, nuclear safety and operation of nuclear facilities. At present, the training course participants can go through more than 20 standard experimental exercises; particular exercises for special training can be prepared. Approximately 200 university students become familiar with the reactor (lectures, experiments, experimental and diploma works, etc.) every year. About 12 different faculties from Czech universities use the reactor. International co-operation with European universities in Germany, Hungary, Austria, Slovakia, Holland and UK is frequent. The VR-1 reactor takes also part in Eugene Wigner Course on Reactor Physics Experiments in the framework of European Nuclear Educational Network (ENEN) association. Recently, training courses for Bulgarian research reactor specialists supported by IAEA were carried out. An attractive program including demonstration of reactor operation is prepared also for high school students. Every year, more than 1500 high school students come to visit the reactor, as do many foreigner visitors. (author)

  6. Identification of an Nav1.1 sodium channel (SCN1A) loss-of-function mutation associated with familial simple febrile seizures

    Science.gov (United States)

    Mantegazza, Massimo; Gambardella, Antonio; Rusconi, Raffaella; Schiavon, Emanuele; Annesi, Ferdinanda; Cassulini, Rita Restano; Labate, Angelo; Carrideo, Sara; Chifari, Rosanna; Canevini, Maria Paola; Canger, Raffaele; Franceschetti, Silvana; Annesi, Grazia; Wanke, Enzo; Quattrone, Aldo

    2005-01-01

    Febrile seizures (FS) affect 5–12% of infants and children up to 6 years of age. There is now epidemiological evidence that FS are associated with subsequent afebrile and unprovoked seizures in ≈7% of patients, which is 10 times more than in the general population. Extensive genetic studies have demonstrated that various loci are responsible for familial FS, and the FEB3 autosomal-dominant locus has been identified on chromosome 2q23–24, where the SCN1A gene is mapped. However, gene mutations causing simple FS have not been found yet. Here we show that the M145T mutation of a well conserved amino acid in the first transmembrane segment of domain I of the human Nav1.1 channel α-subunit cosegregates in all 12 individuals of a large Italian family affected by simple FS. Functional studies in mammalian cells demonstrate that the mutation causes a 60% reduction of current density and a 10-mV positive shift of the activation curve. Thus, M145T is a loss-of-function mutant. These results show that monogenic FS should also be considered a channelopathy. PMID:16326807

  7. Office for Analysis and Evaluation of Operational Data 1996 annual report. Volume 10, Number 1: Reactors

    International Nuclear Information System (INIS)

    1997-12-01

    This annual report of the US Nuclear Regulatory Commission's Office for Analysis and Evaluation of Operational Data (AEOD) describes activities conducted during 1996. The report is published in three parts. NUREG-1272, Vol. 10, No. 1, covers power reactors and presents an overview of the operating experience of the nuclear power industry from the NRC perspective, including comments about trends of some key performance measures. The report also includes the principal findings and issues identified in AEOD studies over the past year and summarizes information from such sources as licensee event reports and reports to the NRC's Operations Center. NUREG-1272, Vol. 10, No. 2, covers nuclear materials and presents a review of the events and concerns during 1996 associated with the use of licensed material in nonreactor applications, such as personnel overexposures and medical misadministrations. Both reports also contain a discussion of the Incident Investigation Team program and summarize both the Incident Investigation Team and Augmented Inspection Team reports. Each volume contains a list of the AEOD reports issued from CY 1980 through 1996. NUREG-1272, Vol. 10, No. 3, covers technical training and presents the activities of the Technical Training Center in support of the NRC's mission in 1996

  8. Current status of the Thai Research Reactor (TRR-1/M1)

    International Nuclear Information System (INIS)

    Chueinta, Siripone; Julanan, Mongkol; Charncanchee, Decharchai

    2006-01-01

    The first Thai Research Reactor, TRR-1 went critical on 27 October 1962 at the maximum power of 1 MW. It was located at Office of Atoms for Peace (OAP) in Bangkok. Since then, TRR-1 was continuously operated and eventually shut down in 1975. Plate type, high-enriched uranium (HEU) and U 3 O 8 A1 cladding were used as the reactor fuel. Light water was used as moderator and coolant as well. In 1975, because of the problem from fuel supplier and also to supporting the Treaty of Non Proliferation of Nuclear Weapon or NPT, TRR-1 was shut down for modification. The reactor core and control system were disassembled and replaced by TRIGA Mark III. A new core was a hexagonal core shape designed by General Atomics (GA). Afterwards, TRR-1 was officially renamed to the Thai Research Reactor-1/Modification 1 (TRR-1/M1). TRR-1/M1 is a multipurpose swimming pool type reactor with nominal power of 2 MW. The TRR-1/M1 uses uranium enriched at 20% in U-235 (LEU) and ZrH alloy as fuel. Light water is also used as coolant and moderator. At present, the reactor is operating with core No.14. The reactor has been serving for various kinds of utilization namely, radioisotope production, neutron activation analysis, beam experiments and reactor physics experiments. (author)

  9. 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

  10. The Jules Horowitz reactor project, a driver for revival of the research reactor community

    Energy Technology Data Exchange (ETDEWEB)

    Pere, P.; Cavailler, C.; Pascal, C. [AREVA TA, CEA Cadarache - Etablissement d' AREVA TA - Chantier RJH - MOE - BV2 - BP no. 9 - 13115 Saint Paul lez Durance (France); CS 50497 - 1100, rue JR Gauthier de la Lauziere, 13593 Aix en Provence cedex 3 (France)

    2010-07-01

    The first concrete of the nuclear island for the Jules Horowitz Reactor (JHR) was poured at the end of July 2009 and construction is ongoing. The JHR is the largest new platform for irradiation experiments supporting Generation II and III reactors, Generation IV technologies, and radioisotope production. This facility, composed of a unique grouping of workshops, hot cells and hot laboratories together with a first -rate MTR research reactor, will ensure that the process, from preparations for irradiation experiments through post-irradiation non-destructive examination, is completed expediently, efficiently and, of course, safely. In addition to the performance requirements to be met in terms of neutron fluxes on the samples (5x10{sup 14} n.cm{sup -2}/sec{sup -1} E> 1 MeV in core and 3,6x10{sup 14} n.cm{sup -2}/sec{sup -1} E<0.625 eV in the reflector) and the JHR's considerable irradiation capabilities (more than 20 experiments and one-tenth of irradiation area for simultaneous radioisotope production), the JHR is the first MTR to be built since the end of the 1960's, making this an especially challenging project. The presentation will provide an overview of the reactor, hot cells and laboratories and an outline of the key milestones in the project schedule, including initial criticality in early 2014 and radioisotope production in 2015. This will be followed by a description of the project organization set up by the CEA as owner and future operator and AREVA TA as prime contractor and supplier of critical systems, and a discussion of project challenges, especially those dealing with the following items: - accommodation of a broad experimental domain, - involvement by international partners making in-kind contributions to the project, - development of components critical to safety and performance, - the revival of engineering of research reactors and experimental devices involving France's historical players in the field of research reactors, and

  11. Annual report on JEN-1 reactor; Informe periodico del Reactor JEN-1 correspondiente al ano 1971

    Energy Technology Data Exchange (ETDEWEB)

    Montes, J

    1972-07-01

    In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

  12. 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) ...

  13. 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) ...

  14. The U.S. reduced enrichment research and test reactor (RERTR) program

    International Nuclear Information System (INIS)

    Travelli, A.

    1993-01-01

    Research and test reactors are widely deployed to study the irradiation behavior of materials of interest in nuclear engineering, to produce radioisotopes for medicine, industry, and agriculture, and as a basic research and teaching tool. In order to maximize neutron flux per unit power and/or to minimize capital costs and fuel cycle costs, most of these reactors were de- signed to utilize uranium with very high enrichment (in the 70% to 95% range). Research reactor fuels with such high uranium enrichment cause a potential risk of nuclear weapons proliferation. Over 140 research and test reactors of significant power (between 10 kW and 250 MW) are in operation with very highly enriched uranium in more than 35 countries, with total power in excess of 1,700 MW. The overall annual fuel requirement of these reactors corresponds to approximately 1,200 kg of 235 U. This highly strategic material is normally exported from the United States, converted to metal form, shipped to a fuel fabricator, and then shipped to the reactor site in finished fuel element form. At the reactor site the fuel is first stored, then irradiated, stored again, and eventually shipped back to the United States for reprocessing. The whole cycle takes approximately four years to complete, bringing the total required fuel inventory to approximately 5,000 kg of 235 U. The resulting international trade in highly-enriched uranium may involve several countries in the process of refueling a single reactor and creates a considerable concern that the highly-enriched uranium may be diverted for non-peaceful purposes while in fabrication, transport, or storage, particularly when it is in the unirradiated form. The proliferation resistance of nuclear fuels used in research and test reactors can be considerably improved by reducing their uranium enrichment to a value less than 20%, but significantly greater than natural to avoid excessive plutonium production

  15. High-power parametric amplification of 11.8-fs laser pulses with carrier-envelope phase control

    NARCIS (Netherlands)

    Zinkstok, R.T.; Witte, S.; Hogervorst, W.; Eikema, K.S.E.

    2005-01-01

    Phase-stable parametric chirped-pulse amplification of ultrashort pulses from a carrier-envelope phase-stabilized mode-locked Ti:sapphire oscillator (11.0 fs) to 0.25 mJ/pulse at 1 kHz is demonstrated. Compression with a grating compressor and a LCD shaper yields near-Fourier-limited 11.8-fs pulses

  16. Reactor of the XXI century

    International Nuclear Information System (INIS)

    Zhotabaev, Zh.R.; Solov'ev, Yu.A.

    2001-01-01

    The advantages of both molten salt reactors (MSR) and homogenous molten salt reactors (HMSR) are illuminated. It is noted that the MSR possess accident probability A=10 -6 1/reactor.years and the HMSR with integral configuration has A=10 -7 1/reactor.years. The methods for these reactors technological problems solution - tritium removal, salt melt circulation and capacity pick up - are discussed

  17. 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) ...

  18. 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) ...

  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. 10 CFR 50.46a - Acceptance criteria for reactor coolant system venting systems.

    Science.gov (United States)

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Acceptance criteria for reactor coolant system venting systems. 50.46a Section 50.46a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND... function of these systems. High point vents are not required for the tubes in U-tube steam generators...

  1. Climatic potential productivity and an IRS-1CWiFS image in Natural Park Los Alcornocales. Relationship with the standing forest biomass; Productividad Potencial Climatica y una imagen IRS-1CWiFS en el Parque Natural Los Alcornocales. Relacion con la biomasa forestal real

    Energy Technology Data Exchange (ETDEWEB)

    Cuevas, J. M.; Gonzalez-Alonso, F.; Roldan, A.; Huesca, M.

    2009-07-01

    It is studied the use of the Map of Forest Potential Productivity of Spain as information in base to which classify an Indian IRS-1C WiFS satellite image in Los Alcornocales Natural Park (Andalucia, Spain), a large forest area covered by natural forests of Mediterranean broad-leaved species, mainly cork oak (Quercus suber L.). Grouping the classes of climatic potential productivity of this map were obtained three macro classes that resulted significantly different among them at the 99% confidence level for the visible and the Normalized Difference Vegetation Index (NDVI) of the WiFS image. It was built a classifier using these macro classes of climatic potential productivity as ground truth areas. By maximum likelihood supervised classification of the NDVI were obtained classes who resulted significantly different among them at the 90% confidence level for the basal area from the Second Spanish National Forest Inventory ground plots located in the park. (Author) 60 refs.

  2. Embrittlement of the nuclear icebreaker Lenin reactor pressure vessel materials reconstruction

    International Nuclear Information System (INIS)

    Krasikov, E.A.; Nikolaenko, V.A.

    2008-01-01

    Paper deals with the results of the efforts to examine the radiation damage of the Lenin nuclear-powered ice-breaker decommissioned reactor pressure vessel on the basis of which one has determined the peculiar features of the metal radiation embrittlement. Under 10 10 -10 11 s -1 cm -2 low density neutron flux irradiation one notes the most intensive embrittlement of the metal. Then, as the noxious element content in the metal matrix grows smaller the embrittlement reduces up to the change of sign as to the normal curve plotted at the neutron flux density exceeding 10 13 s -1 cm -2 . One assumes that as a result of the low density neutron flux irradiation the reactor pressure vessel edge spaces at some operation stages may be damaged more severely in contrast to these near the reactor core. The neutron irradiation density is the factor affecting the reactor vessel material embrittlement, that is why, it is important to study the damage mechanism of the materials of the power reactor vessels under design characterized by the low radiation load. The mentioned is important, as well, to evaluate the efficiency of the efforts undertaken to mitigate the effect of the neutron radiation on the reactor vessel [ru

  3. 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)

  4. 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)).

  5. 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

  6. 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)

  7. 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...

  8. [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.

  9. 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) ...

  10. Precision measurement of the $B^0_s - \\bar{B}^0_s$ oscillation frequency with the decay $B^0_s \\to D^-_s \\pi^+$

    CERN Document Server

    Aaij, R; Adeva, B; Adinolfi, M; Adrover, C; Affolder, A; Ajaltouni, Z; Albrecht, J; Alessio, F; Alexander, M; Ali, S; Alkhazov, G; Alvarez Cartelle, P; Alves Jr, A A; Amato, S; Amerio, S; Amhis, Y; Anderlini, L; Anderson, J; Andreassen, R; Appleby, R B; Aquines Gutierrez, O; Archilli, F; Artamonov, A; Artuso, M; Aslanides, E; Auriemma, G; Bachmann, S; Back, J J; Baesso, C; Balagura, V; Baldini, W; Barlow, R J; Barschel, C; Barsuk, S; Barter, W; Bauer, Th; Bay, A; Beddow, J; Bedeschi, F; Bediaga, I; Belogurov, S; Belous, K; Belyaev, I; Ben-Haim, E; Benayoun, M; Bencivenni, G; Benson, S; Benton, J; Berezhnoy, A; Bernet, R; Bettler, M -O; van Beuzekom, M; Bien, A; Bifani, S; Bird, T; Bizzeti, A; Bjørnstad, P M; Blake, T; Blanc, F; Blouw, J; Blusk, S; Bocci, V; Bondar, A; Bondar, N; Bonivento, W; Borghi, S; Borgia, A; Bowcock, T J V; Bowen, E; Bozzi, C; Brambach, T; van den Brand, J; Bressieux, J; Brett, D; Britsch, M; Britton, T; Brook, N H; Brown, H; Burducea, I; Bursche, A; Busetto, G; Buytaert, J; Cadeddu, S; Callot, O; Calvi, M; Calvo Gomez, M; Camboni, A; Campana, P; Campora Perez, D; Carbone, A; Carboni, G; Cardinale, R; Cardini, A; Carranza-Mejia, H; Carson, L; Carvalho Akiba, K; Casse, G; Cattaneo, M; Cauet, Ch; Charles, M; Charpentier, Ph; Chen, P; Chiapolini, N; Chrzaszcz, M; Ciba, K; Cid Vidal, X; Ciezarek, G; Clarke, P E L; Clemencic, M; Cliff, H V; Closier, J; Coca, C; Coco, V; Cogan, J; Cogneras, E; Collins, P; Comerma-Montells, A; Contu, A; Cook, A; Coombes, M; Coquereau, S; Corti, G; Couturier, B; Cowan, G A; Craik, D C; Cunliffe, S; Currie, R; D'Ambrosio, C; David, P; David, P N Y; De Bonis, I; De Bruyn, K; De Capua, S; De Cian, M; De Miranda, J M; De Paula, L; De Silva, W; De Simone, P; Decamp, D; Deckenhoff, M; Del Buono, L; Derkach, D; Deschamps, O; Dettori, F; Di Canto, A; Dijkstra, H; Dogaru, M; Donleavy, S; Dordei, F; Dosil Suárez, A; Dossett, D; Dovbnya, A; Dupertuis, F; Dzhelyadin, R; Dziurda, A; Dzyuba, A; Easo, S; Egede, U; Egorychev, V; Eidelman, S; van Eijk, D; Eisenhardt, S; Eitschberger, U; Ekelhof, R; Eklund, L; El Rifai, I; Elsasser, Ch; Elsby, D; Falabella, A; Färber, C; Fardell, G; Farinelli, C; Farry, S; Fave, V; Ferguson, D; Fernandez Albor, V; Ferreira Rodrigues, F; Ferro-Luzzi, M; Filippov, S; Fiore, M; Fitzpatrick, C; Fontana, M; Fontanelli, F; Forty, R; Francisco, O; Frank, M; Frei, C; Frosini, M; Furcas, S; Furfaro, E; Gallas Torreira, A; Galli, D; Gandelman, M; Gandini, P; Gao, Y; Garofoli, J; Garosi, P; Garra Tico, J; Garrido, L; Gaspar, C; Gauld, R; Gersabeck, E; Gersabeck, M; Gershon, T; Ghez, Ph; Gibson, V; Gligorov, V V; Göbel, C; Golubkov, D; Golutvin, A; Gomes, A; Gordon, H; Grabalosa Gándara, M; Graciani Diaz, R; Granado Cardoso, L A; Graugés, E; Graziani, G; Grecu, A; Greening, E; Gregson, S; Grünberg, O; Gui, B; Gushchin, E; Guz, Yu; Gys, T; Hadjivasiliou, C; Haefeli, G; Haen, C; Haines, S C; Hall, S; Hampson, T; Hansmann-Menzemer, S; Harnew, N; Harnew, S T; Harrison, J; Hartmann, T; He, J; Heijne, V; Hennessy, K; Henrard, P; Hernando Morata, J A; van Herwijnen, E; Hicks, E; Hill, D; Hoballah, M; Hombach, C; Hopchev, P; Hulsbergen, W; Hunt, P; Huse, T; Hussain, N; Hutchcroft, D; Hynds, D; Iakovenko, V; Idzik, M; Ilten, P; Jacobsson, R; Jaeger, A; Jans, E; Jaton, P; Jing, F; John, M; Johnson, D; Jones, C R; Jost, B; Kaballo, M; Kandybei, S; Karacson, M; Karbach, T M; Kenyon, I R; Kerzel, U; Ketel, T; Keune, A; Khanji, B; Kochebina, O; Komarov, I; Koopman, R F; Koppenburg, P; Korolev, M; Kozlinskiy, A; Kravchuk, L; Kreplin, K; Kreps, M; Krocker, G; Krokovny, P; Kruse, F; Kucharczyk, M; Kudryavtsev, V; 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; Lazzeroni, C; Le Gac, R; van Leerdam, J; Lees, J -P; Lefèvre, R; Leflat, A; Lefrançois, J; Leo, S; Leroy, O; Lesiak, T; Leverington, B; Li, Y; Li Gioi, L; Liles, M; Lindner, R; Linn, C; Liu, B; Liu, G; Lohn, S; Longstaff, I; Lopes, J H; Lopez Asamar, E; Lopez-March, N; Lu, H; Lucchesi, D; Luisier, J; Luo, H; Machefert, F; Machikhiliyan, I V; Maciuc, F; Maev, O; Malde, S; Manca, G; Mancinelli, G; Marconi, U; Märki, R; Marks, J; Martellotti, G; Martens, A; Martin, L; Martín Sánchez, A; Martinelli, M; Martinez Santos, D; Martins Tostes, D; Massafferri, A; Matev, R; Mathe, Z; Matteuzzi, C; Maurice, E; Mazurov, A; McCarthy, J; McNab, A; McNulty, R; Meadows, B; Meier, F; Meissner, M; Merk, M; Milanes, D A; Minard, M -N; Molina Rodriguez, J; Monteil, S; Moran, D; Morawski, P; Morello, M J; Mountain, R; Mous, I; Muheim, F; Müller, K; Muresan, R; Muryn, B; Muster, B; Naik, P; Nakada, T; Nandakumar, R; Nasteva, I; Needham, M; Neufeld, N; Nguyen, A D; Nguyen, T D; Nguyen-Mau, C; Nicol, M; Niess, V; Niet, R; Nikitin, N; Nikodem, T; Nomerotski, A; Novoselov, A; Oblakowska-Mucha, A; Obraztsov, V; Oggero, S; Ogilvy, S; Okhrimenko, O; Oldeman, R; Orlandea, M; Otalora Goicochea, J M; Owen, P; Oyanguren, A; Pal, B K; Palano, A; Palutan, M; Panman, J; Papanestis, A; Pappagallo, M; Parkes, C; Parkinson, C J; Passaleva, G; Patel, G D; Patel, M; 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; Pérez-Calero Yzquierdo, A; Perret, P; Perrin-Terrin, M; Pessina, G; Petridis, K; Petrolini, A; Phan, A; Picatoste Olloqui, E; Pietrzyk, B; Pilař, T; Pinci, D; Playfer, S; Plo Casasus, M; Polci, F; Polok, G; Poluektov, A; Polycarpo, E; Popov, D; Popovici, B; Potterat, C; Powell, A; Prisciandaro, J; Pugatch, V; Puig Navarro, A; Punzi, G; Qian, W; Rademacker, J H; Rakotomiaramanana, B; Rangel, M S; Raniuk, I; Rauschmayr, N; Raven, G; Redford, S; Reid, M M; dos Reis, A C; Ricciardi, S; Richards, A; Rinnert, K; Rives Molina, V; Roa Romero, D A; Robbe, P; Rodrigues, E; Rodriguez Perez, P; Roiser, S; Romanovsky, V; Romero Vidal, A; Rouvinet, J; Ruf, T; Ruffini, F; Ruiz, H; Ruiz Valls, P; Sabatino, G; Saborido Silva, J J; Sagidova, N; Sail, P; Saitta, B; Salzmann, C; Sanmartin Sedes, B; Sannino, M; Santacesaria, R; Santamarina Rios, C; Santovetti, E; Sapunov, M; Sarti, A; Satriano, C; Satta, A; Savrie, M; Savrina, D; Schaack, P; Schiller, M; Schindler, H; Schlupp, M; Schmelling, M; Schmidt, B; Schneider, O; Schopper, A; Schune, M -H; Schwemmer, R; Sciascia, B; Sciubba, A; Seco, M; Semennikov, A; Senderowska, K; Sepp, I; Serra, N; Serrano, J; Seyfert, P; Shapkin, M; Shapoval, I; Shatalov, P; Shcheglov, Y; Shears, T; Shekhtman, L; Shevchenko, O; Shevchenko, V; Shires, A; Silva Coutinho, R; Skwarnicki, T; Smith, N A; Smith, E; Smith, M; Sokoloff, M D; Soler, F J P; Soomro, F; Souza, D; 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; Subbiah, V K; Swientek, S; Syropoulos, V; Szczekowski, M; Szczypka, P; Szumlak, T; T'Jampens, S; Teklishyn, M; Teodorescu, E; Teubert, F; Thomas, C; Thomas, E; van Tilburg, J; Tisserand, V; Tobin, M; Tolk, S; Tonelli, D; Topp-Joergensen, S; Torr, N; Tournefier, E; Tourneur, S; Tran, M T; Tresch, M; Tsaregorodtsev, A; Tsopelas, P; Tuning, N; Ubeda Garcia, M; Ukleja, A; Urner, D; Uwer, U; Vagnoni, V; Valenti, G; Vazquez Gomez, R; Vazquez Regueiro, P; Vecchi, S; Velthuis, J J; Veltri, M; Veneziano, G; Vesterinen, M; Viaud, B; Vieira, D; Vilasis-Cardona, X; Vollhardt, A; Volyanskyy, D; Voong, D; Vorobyev, A; Vorobyev, V; Voß, C; Voss, H; Waldi, R; Wallace, R; Wandernoth, S; Wang, J; Ward, D R; Watson, N K; Webber, A D; Websdale, D; Whitehead, M; Wicht, J; Wiechczynski, J; Wiedner, D; Wiggers, L; Wilkinson, G; Williams, M P; Williams, M; Wilson, F F; Wishahi, J; Witek, M; Wotton, S A; Wright, S; Wu, S; Wyllie, K; Xie, Y; Xing, F; Xing, Z; Yang, Z; Young, R; Yuan, X; Yushchenko, O; Zangoli, M; Zavertyaev, M; Zhang, F; Zhang, L; Zhang, W C; Zhang, Y; Zhelezov, A; Zhokhov, A; Zhong, L; Zvyagin, A

    2013-01-01

    A key ingredient to searches for physics beyond the Standard Model in $B^{0}_{s}$ mixing phenomena is the measurement of the $B^{0}_{s}$-$\\bar{B}^{0}_{s}$ oscillation frequency, which is equivalent to the mass difference $\\Delta m_{s}$ of the $B^{0}_{s}$ mass eigenstates. Using the world's largest $B^{0}_{s}$ meson sample accumulated in a dataset, corresponding to an integrated luminosity of 1.0 fb$^{-1}$, collected by the LHCb experiment at the CERN LHC in 2011, a measurement of $\\Delta m_{s}$ is presented. A total of about 34,000 $B^{0}_{s}\\rightarrow D^{-}_{s}\\pi^{+}$ signal decays are reconstructed, with an average decay time resolution of 44 fs. The oscillation frequency is measured to be $\\Delta m_{s}$ = 17.768 $\\pm$ 0.023 (stat) $\\pm$ 0.006 (syst) ps$^{-1}$}, which is the most precise measurement to date.

  11. Annual report on JEN-1 reactor

    International Nuclear Information System (INIS)

    Montes, J.

    1972-01-01

    In the annual report on the JEN-1 reactor the main features of the reactor operations and maintenance are described. The reactor has been critical for 1831 hours, what means 65,8% of the total working time. Maintenance and pool water contamination have occupied the rest of the time. The maintenance schedule is shown in detail according to three subjects. The main failures and reactor scrams are also described. The daily maximum values of the water activity are given so as the activity of the air in the reactor hall. (Author)

  12. SeaWiFS technical report series. Volume 32: Level-3 SeaWiFS data products. Spatial and temporal binning algorithms

    Science.gov (United States)

    Hooker, Stanford B. (Editor); Firestone, Elaine R. (Editor); Acker, James G. (Editor); Campbell, Janet W.; Blaisdell, John M.; Darzi, Michael

    1995-01-01

    The level-3 data products from the Sea-viewing Wide Field-of-view Sensor (SeaWiFS) are statistical data sets derived from level-2 data. Each data set will be based on a fixed global grid of equal-area bins that are approximately 9 x 9 sq km. Statistics available for each bin include the sum and sum of squares of the natural logarithm of derived level-2 geophysical variables where sums are accumulated over a binning period. Operationally, products with binning periods of 1 day, 8 days, 1 month, and 1 year will be produced and archived. From these accumulated values and for each bin, estimates of the mean, standard deviation, median, and mode may be derived for each geophysical variable. This report contains two major parts: the first (Section 2) is intended as a users' guide for level-3 SeaWiFS data products. It contains an overview of level-0 to level-3 data processing, a discussion of important statistical considerations when using level-3 data, and details of how to use the level-3 data. The second part (Section 3) presents a comparative statistical study of several binning algorithms based on CZCS and moored fluorometer data. The operational binning algorithms were selected based on the results of this study.

  13. G1/S-regulated E2F-containing protein complexes bind to the mouse thymidine kinase gene promoter

    DEFF Research Database (Denmark)

    Dou, Q P; Zhao, S; Levin, A H

    1994-01-01

    report that MT2 includes an E2F-like binding site (GTTCGCGGGCAAA), as shown by the following evidence. (i) MT2 bound specifically to an affinity-purified fusion human E2F protein. (ii) Both MT2 and an authentic E2F site (TTTCGCGCGCTTT) bound specifically to similar or identical nuclear protein complexes...... complexes were also investigated. Studies using specific antibodies revealed that p107, a retinoblastoma-like protein, was present in both E2F-G0/G1 and E2F.S, whereas cyclin E.cyclin A.cdk2 were only present in E2F.S complex(es). These data suggest that removal of the p107-containing E2F.G0/G1 complex...

  14. Comparison of DLK incidence after laser in situ keratomileusis associated with two femtosecond lasers: Femto LDV and IntraLase FS60

    Directory of Open Access Journals (Sweden)

    Tomita M

    2013-07-01

    Full Text Available Minoru Tomita,1–3 Yuko Sotoyama,1 Satoshi Yukawa,1 Tadayuki Nakamura1 1Shinagawa LASIK Center, Chiyoda-ku, Tokyo, Japan; 2Department of Ophthalmology, Wenzhou Medical College, Wenzhou, People’s Republic of China; 3Eye Can Cataract Surgery Center, Manila, Philippines Purpose: To compare the incidence of diffuse lamellar keratitis (DLK after laser in situ keratomileusis (LASIK with flap creation using the Femto LDV and IntraLase™ FS60 femtosecond lasers. Methods: A total of 818 consecutive myopic eyes had LASIK performed using either Femto LDV or IntraLase FS60 for flap creation. The same excimer laser, the Allegretto Wave® Eye-Q Laser, was used for correcting refractive errors for all patients. In the preoperative examination, uncorrected distance visual acuity, corrected distance visual acuity, and manifest refraction spherical equivalent were measured. At the postop examination, the same examinations were performed along with a slit-lamp biomicroscopic examination, and patients with DLK were classified into stages. For the statistical analysis of the DLK occurrence rate and the visual and refractive outcomes, the Mann-Whitney’s U-test was used. Results: In the Femto LDV group with 514 eyes, 42 (8.17% had DLK. In the IntraLase FS60 group with 304 eyes, 114 (37.5% had DLK. There was a statistically significant difference in the DLK incidence rate between these groups (P < 0.0001. Both groups had excellent visual and refractive outcomes. Although low levels of DLK were observed for both groups, they did not affect visual acuity. Conclusion: While there were significantly fewer incidences of low level DLK when using Femto LDV, neither femtosecond laser induced high levels of DLK, and any postoperative DLK cleared up within 1 week. Therefore, both lasers provide excellent results, with no clinical differences, and both excel at flap creation for LASIK. Keywords: LASIK, Ziemer, Femto LDV, DLK, IntraLase FS60, femtosecond laser

  15. Reactor protection system. Revision 1

    International Nuclear Information System (INIS)

    Fairbrother, D.B.; Vincent, D.R.; Lesniak, L.M.

    1975-04-01

    The reactor protection system-II (RPS-II) designed for use on Babcock and Wilcox 145- and 205-fuel assembly pressurized water reactors is described. In this system, relays in the trip logic have been replaced by solid state devices. A calculating module for the low DNBR, pump status, and offset trip functions has replaced the overpower trip (based on flow and imbalance), the power/RC pump trip, and the variable low pressure trip. Included is a description of the changes from the present Oconee-type reactor protection system (RPS-I), a functional and hardware description of the calculating module, and a discussion of the qualification program conducted to ensure that the degree of protection provided by RPS-II is not less than that provided by previously licensed systems supplied by B and W. (U.S.)

  16. 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) ...

  17. 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) ...

  18. 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) ...

  19. 77 FR 74697 - Meeting of the ACRS, Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting

    Science.gov (United States)

    2012-12-17

    ..., Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on January 17, 2013, Room T-2B1, 11545 Rockville Pike... be made. Thirty-five hard copies of each presentation or handout should be provided to the DFO thirty...

  20. 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)

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