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Sample records for dr-3 reactor

  1. Pilot plant production at Riso of LEU silicide fuel for the Danish reactor DR3

    International Nuclear Information System (INIS)

    Toft, P.; Borring, J.; Adolph, E.

    1988-01-01

    A pilot plant for fabricating LEU silicide fuel elements has been established at Riso National Laboratory. Three test elements for the Danish reactor DR3 have been fabricated, based on 19.88% enriched U 3 Si 2 powder that has been purchased elsewhere. The pilot plant has been set up and 3 test elements fabricated without any major difficulties

  2. The DR 3 reactor at Risoe, Denmark and its associated hot cell facilities. Information sheets

    International Nuclear Information System (INIS)

    Hardt, P. von der; Roettger, H.

    1981-01-01

    Technical information is given on the DR 2 reactor and associated hot cell facilities, with the main emphasis on experimental irradiation facilities, specialized irradiation devices (loops and capsules) and possibilities for post-irradiation examinations of samples. The information is presented in the form of seven information sheets under the headings: main characteristics of the reactor; utilization and specialization of the reactor; experimental facilities; main characteristics of specialized irradiation devices; main characteristics of hot cell facilities; equipment and techniques available for post-irradiation examinations; utilization and specialization of the hot cell facilities

  3. Development of a 3-dimensional calculation model of the Danish research reactor DR3 to analyse a proposal to a new core design called ring-core

    Energy Technology Data Exchange (ETDEWEB)

    Nonboel, E

    1985-07-01

    A 3-dimensional calculation model of the Danish research reactor DR3 has been developed. Demands of a more effective utilization of the reactor and its facilities has required a more detailed calculation tool than applied so far. A great deal of attention has been devoted to the treatment of the coarse control arms. The model has been tested against measurements with satisfying results. Furthermore the model has been used to analyse a proposal to a new core design called ring-core where 4 central fuel elements are replaced by 4 dummy elements to increase the thermal flux in the center of the reactor. (author)

  4. Data quality objectives summary report for the 100-BC-1, 100-BC-2, and 100-DR-1, and 100-DR-2 group 3 waste sites

    International Nuclear Information System (INIS)

    1997-03-01

    The 100-BC-1, 100-BC-2, 100-DR-1, and 100-DR-2 Group 3 waste sites contain 22 past-practice liquid waste disposal sites and process effluent piping associated with four plutonium-production nuclear reactors that operated from 1944 to 1967. The 100-BC-1, 100-BC-2, 100-DR-1, and 100-DR-2 Group 3 waste sites are the third set of Hanford 100 Area sites to undergo remediation to the extent practicable. Like the sites listed in Groups 1 and 2, the Group 3 sites are considered high-priority because of the contaminants present and their proximity to the Columbia River. Remediation of the 100-BC-1, 100-HR-1 and 100-DR-1 radioactive liquid waste sites is planned to occur in two phases: The first phase, which has been completed, was a demonstration project in the 100-B/C Area to test field techniques and acquire contamination data. The second phase is full-scale remediation of all the reactor areas, starting in the 10-B/C Area, using the field experience gained in the first phase and each subsequent reactor area remediation. This document provides the DQO in support of remediation sampling and analysis at selected sites in the 100-B/C and 100-D Areas

  5. The code DYN3DR for steady-state and transient analyses of light water reactor cores with Cartesian geometry

    International Nuclear Information System (INIS)

    Grundmann, U.

    1995-11-01

    The code DYN3D/M2 was developed for 3-dimensional steady-state and transient analyses of reactor cores with hexagonal fuel assemblies. The neutron kinetics of the new version DYN3DR is based on a nodal method for the solution of the 3-dimensional 2-group neutron diffusion equation for Cartesian geometry. The thermal-hydraulic model FLOCAL simulating the two phase flow of coolant and the fuel rod behaviour is used in the two versions. The fundamentals for the solution of the neutron diffusion equations in DYN3DR are described. The 3-dimensional NEACRP benchmarks for rod ejections in LWR with quadratic fuel assemblies were calculated and the results were compared with the published solutions. The developed algorithm for neutron kinetics are suitable for using parallel processing. The behaviour of speed-up versus the number of processors is demonstrated for calculations of a static neutron flux distribution using a workstation with 4 processors. (orig.) [de

  6. Engineering evaluation/cost analysis for the 105-DR and 105-F Reactor facilities and ancillary facilities

    International Nuclear Information System (INIS)

    Coenenberg, E.T.

    1998-01-01

    This document presents the results of an engineering evaluation/cost analysis (EE/CA) that was conducted to evaluate alternatives to address final disposition of the 105-DR and 105-F Reactor Buildings (subsequently referred to as facilities), including the fuel storage basins (FSB) and below-grade portions of the reactors, excluding the reactor blocks. The reactor blocks will remain in a safe storage mode for up to 75 years as identified in the Record the Decision (ROD) (58 FR 48509) for the Environmental Impact Statement (EIS), Decommissioning of Eight Surplus Production Reactors at the Hanford Site, Richland, Washington (DOE 1992a). This EE/CA also addresses final disposition of four ancillary facilities: 116-D and 116-DR Exhaust Air Stacks, 117-DR Exhaust Filter Building, and 119-DR Exhaust Air Sample Building. The 105-DR and 105-F facilities are located in the 100-D and 100-F Areas of the Hanford Site. In November 1989, the 100 Area of the Hanford Site was placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List (NPL) under the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA). The 100 Area NPL includes the 100-D Area (which includes the 100-DR site) and the 100-F Area, which are in various stages of the remediation process. It has been determined by DOE that hazardous substances in the 105-DR, 105-F, and the four ancillary facilities may present a potential threat to human health or the environment, and that a non-time critical removal action at these facilities is warranted. To help determine the most appropriate action, DOE, in cooperation with the Washington State Department of Ecology (Ecology) and the EPA, has prepared this EE/CA. The scope of the evaluation includes the 105-DR and 105-F facilities and the four ancillary facilities. The 116-DR and 117-DR facilities are located within the boundaries of the 105-DR Large Sodium Fire Facility Treatment, Storage, and Disposal (TSD) unit, which is

  7. Well Completion Report for the Fiscal Year 1999 Drilling Within the Chromium Plume West of the 100-D/DR Reactors

    International Nuclear Information System (INIS)

    Ford, B. H.

    1999-01-01

    This report describes the fiscal year (FY) 1999 field activities associated with installing 12 groundwater monitoring wells in the vicinity of the 100-D Area chromium plume west of the 100-D/DR Reactors (100-HR-3 Operable Unit [OU]). The wells were installed to further investigate the extent of the hexavalent chromium hot spot west of the 100-D/DR Reactors and to support future remedial action decisions associated with the 100-HR-3 OU. These wells were designed for multi-purpose use (i.e., monitoring, extraction, and injection). In addition, one of the wells was installed to support the initial deployment of the In Situ Redox Manipulation (ISRM) technology to remediate the chromium plume

  8. Study on Al-alloy or silicide LEU for DR3 in Denmark

    Energy Technology Data Exchange (ETDEWEB)

    Haack, Karsten [Riso National Laboratory, DK 4000 Roskilde (Germany)

    1985-07-01

    The 10 MW D{sub 2}0-moderated and -cooled research reactor DR3 has at present HEU fuel available for continued operation till early 19. This report presents the status of a feasibility study prepared for selection of the best suited candidate LEU fuel type for DR3 at a potential conversion in 1988. At the moment two alternatives are evaluated: UAl-alloy with modified geometry and U{sub 3}Si{sub 2} with unchanged geometry. A decision on the type selected for further investigation is expected late 1984. The investigation should comprise development, in- and out-of-pile--testing and licensing activities on the potential LEU option. (author)

  9. Verification of the code DYN3D/R with the help of international benchmarks

    International Nuclear Information System (INIS)

    Grundmann, U.; Rohde, U.

    1997-10-01

    Different benchmarks for reactors with quadratic fuel assemblies were calculated with the code DYN3D/R. In this report comparisons with the results of the reference solutions are carried out. The results of DYN3D/R and the reference calculation for the eigenvalue k eff and the power distribution are shown for the steady-state 3-dimensional IAEA-Benchmark. The results of NEACRP-Benchmarks on control rod ejections in a standard PWR were compared with the reference solutions published by the NEA Data Bank. For assessing the accuracy of DYN3D/R results in comparison to other codes the deviations to the reference solutions are considered. Detailed comparisons with the published reference solutions of the NEA-NSC Benchmarks on uncontrolled withdrawal of control rods are made. The influence of the axial nodalization is also investigated. All in all, a good agreement of the DYN3D/R results with the reference solutions can be seen for the considered benchmark problems. (orig.) [de

  10. The DR-2 project

    DEFF Research Database (Denmark)

    Ølgaard, Povl Lebeck

    2003-01-01

    state of the reactor and to determine, which radionuclides remain where in the reactor in what amounts. The first part of the reactor to be investigated was the reactor tank. The lids at the reactor top wereremoved, air samples taken and smear test made in the tank. Then the control rods, the magnet....... At the start of the project the activity in DR-2 was about 45-50 GBq. Now it is about 5-10 GBq. Based on the results of the DR-2 project it is believed that the reactor can readily bedismantled and decommissioned....

  11. Irradiation of MEU and LEU test fuel elements in DR 3

    International Nuclear Information System (INIS)

    Haack, K.

    1984-01-01

    Irradiation of three MEU and three LEU fuel elements in the Danish reactor DR 3. Thermal and fast neutron flux density scans of the core have been made and the results, related to the U235-content of each fuel element, are compared with the values from HEU fuel elements. The test elements were taken to burn-up percentages of 50-60%. Reactivity values of the test elements at charge and at discharge have been measured and the values are compared with those of HEU fuel elements. (author)

  12. Description of work for the drilling within the chromium plume west of 100-D/DR Reactors

    International Nuclear Information System (INIS)

    Peterson, R.E.; Walker, L.D.

    1997-07-01

    This document describes the work scope associated with installing four new monitoring wells in the 100-D/DR Area (100-HR-3 Operable Unit). The strategy relies on estimates for flow paths that might have existed during operation of the 100-D Reactor and on experience gained during the recent installation of well 199-D4-1. A Data Quality Objectives (DQO) workshop was held to evaluate data collection needs during well installation. The workshop included input from key project team members and the lead regulatory agency. Decisions concerning data resulting from the DQO process have been incorporated into this document

  13. 105-DR large sodium fire facility closure Plan. Revision 2

    International Nuclear Information System (INIS)

    Ruck, F.A. III.

    1995-03-01

    The 105-DR Large Sodium Fire Facility (LSFF), which was operated 1972-1986, was a research laboratory that occupied the former ventilation supply room on the SW side of the 105-DR Reactor Facility. (The 105-DR defense reactor was shut down in 1964.) LSFF was used to investigate fire and safety aspects of large sodium or other metal alkali fires in the LMFBR facilities; it was also used to store and treat alkali metal waste. This closure plan presents a description of the unit, the history of the waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of LSFF is expected. It is located within the 100-DR-2 (source) and 100-HR-3 (groundwater) operable units, which will be addressed through the RCRA facility investigation/corrective measures study process

  14. Data Quality Objective Summary Report for Phase II of the 105-F and DR Reactor Buildings

    International Nuclear Information System (INIS)

    Bauer, R.G.

    1998-01-01

    This data quality objective (DQO) process is to support planning and decision-making activities of Phase II decontamination and decommissioning (D and D) activities for the 105-F and 105-DR Reactor Buildings.The objective of this DQO is to determine the survey and characterization requirements for these rooms to provide the necessary information for worker safety, waste designation, recycle, reuse, and clean landfill disposal decisions during D and D

  15. Human immune responsiveness to Lolium perenne pollen allergen Lol p III (rye III) is associated with HLA-DR3 and DR5.

    Science.gov (United States)

    Ansari, A A; Freidhoff, L R; Meyers, D A; Bias, W B; Marsh, D G

    1989-05-01

    A well-characterized allergen of Lolium perenne (perennial rye grass) pollen, Lol p III, has been used as a model antigen to study the genetic control of the human immune response. Associations between HLA type and IgE or IgG antibody (Ab) responsiveness to Lol p III were studied in two groups of skin-test-positive Caucasoid adults (N = 135 and 67). We found by nonparametric and parametric analyses that immune responsiveness to Lol p III was significantly associated with HLA-DR3 and DR5. No association was found between any DQ type and immune responsiveness to Lol p III. Geometric mean IgE or IgG Ab levels to Lol p III were not different between B8+, DR3+ subjects and B8-, DR3+ subjects, showing that HLA-B8 had no influence on the association. Lol p III IgG Ab data obtained on subjects after grass antigen immunotherapy showed that 100% of DR3 subjects and 100% of DR5 subjects were Ab+. A comparison of all the available protein sequences of DRB gene products showed that the first hypervariable region of DR3 and DR5 (and DRw6), and no other region, contains the sequence Glu9-Tyr-Ser-Thr-Ser13. Our observations are consistent with the possibility that immune responsiveness to the allergen Lol p III is associated with this amino acid sequence in the first hypervariable region of the DR beta 1 polypeptide chain.

  16. 105-DR Large Sodium Fire Facility closure plan

    International Nuclear Information System (INIS)

    1993-05-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected

  17. 105-DR Large Sodium Fire Facility decontamination, sampling, and analysis plan

    International Nuclear Information System (INIS)

    Knaus, Z.C.

    1995-01-01

    This is the decontamination, sampling, and analysis plan for the closure activities at the 105-DR Large Sodium Fire Facility at Hanford Reservation. This document supports the 105-DR Large Sodium Fire Facility Closure Plan, DOE-RL-90-25. The 105-DR LSFF, which operated from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility in the 100-D Area of the Hanford Site. The LSFF was established to investigate fire fighting and safety associated with alkali metal fires in the liquid metal fast breeder reactor facilities. The decontamination, sampling, and analysis plan identifies the decontamination procedures, sampling locations, any special handling requirements, quality control samples, required chemical analysis, and data validation needed to meet the requirements of the 105-DR Large Sodium Fire Facility Closure Plan in compliance with the Resource Conservation and Recovery Act

  18. Evaluasi Fungsi Insinerator Dalam Memusnahkan Limbah B3 Di Rumah Sakit NI Dr.Ramelan Surabaya

    Directory of Open Access Journals (Sweden)

    Jahn Leonard Saragih

    2013-09-01

    Full Text Available Pengelolaan limbah padat B3 di Rumah Sakit TNI Angkatan Laut Dr. Ramelan sangat penting diperhatikan karena dapat berdampak buruk apabila tidak dikelola dengan baik. Oleh sebab itu diperlukan adanya penelitian untuk mengidentifikasi jumlah timbulan dan penanganan limbah padat B3, mengevaluasi manajemen, penyimpanan sementara serta mengevaluasi proses insinerasi. Evaluasi fungsi incinerator di Rumah Sakit TNI Angkatan Laut Dr. Ramelan dilakukan dengan meneliti jumlah timbulan limbah B3, kapasitas pembakaran insinerator, suhu pembakaran insinerator, densitas limbah dan abu pembakaran, dan tes TCLP residu pembakaran incinerator Rumah Sakit TNI Angkatan Laut Dr. Ramelan. Dalam penelitian ini, Rumkital Dr. Ramelan memusnahkan limbah dengan incinerator. Limbah B3 yang dihasilkan Rumkital Dr. Ramelan dimusnakan dengan satu incinerator dengan type KAMINE TYPE BDR-INC 10. Limbah yang dimusnahkan di Rumkital Dr. Ramelan berasal dari Rumkital Dr. Ramelan dan Lantamal Perak. Setelah dilakukan penelitian langsung selama 14 hari berturut-turut, didapatkan bahwa rata-rata timbulan limbah B3 di Rumkital Dr. Ramelan adalah 89.98 Kg/hari dan dengan densitas rata-rata limbah ialah 166,67 kg/m3. Tinggat removal dari pembakaran limbah dengan incinerator di Rumah Sakit TNI Angkatan Laut Dr. Ramelan ialah 82,63%. Pengelolaan abu sisa incinerator Rumkital Dr. Ramelan belum sesuai dengan peraturan yang berlaku dan dari penelitian yang dilakukan yaitu pengujian kandungan abu incinerator, solidifikasi abu incinerator dengan perbandingan semen:abu adalah 1:3 dan uji TCLP, didapatkan bahwa limbah abu sisa insinerator Rumah Sakit TNI Angkatan Laut Dr. Ramelan Surabaya, dapat ditimbun pada landfill kategori I sesuai dengan Keputusan Kepala Bapedal No.4 Tahun 1995.

  19. 105-DR Large Sodium Fire Facility closure plan. Revision 1

    Energy Technology Data Exchange (ETDEWEB)

    1993-05-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, and activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide a means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950`s and is located in the 100-D Area of the Hanford Site. The building housed the 105-DR defense reactor, which was shut down in 1964. The LSFF was initially used only for engineering-scale alkali metal reaction studies. In addition, the Fusion Safety Support Studies program sponsored intermediate-size safety reaction tests in the LSFF with lithium and lithium lead compounds. The facility has also been used to store and treat alkali metal waste, therefore the LSFF is subject to the regulatory requirements for the storage and treatment of dangerous waste. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610. This closure plan presents a description of the facility, the history of waste managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  20. Calculation of heat rating and burn-up for test fuel pins irradiated in DR 3

    International Nuclear Information System (INIS)

    Bagger, C.; Carlsen, H.; Hansen, K.

    1980-01-01

    A summary of the DR 3 reactor and HP1 rig design is given followed by a detailed description of the calculation procedure for obtaining linear heat rating and burn-up values of fuel pins irradiated in HP1 rigs. The calculations are carried out rather detailed, especially regarding features like end pellet contribution to power as a function of burn-up, gamma heat contributions, and evaluation of local values of heat rating and burn-up. Included in the report is also a description of the fast flux- and cladding temperature calculation techniques currently used. A good agreement between measured and calculated local burn-up values is found. This gives confidence to the detailed treatment of the data. (author)

  1. Decommissioning of DR 1, Final report

    Energy Technology Data Exchange (ETDEWEB)

    Lauridsen, Kurt

    2006-01-15

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  2. Decommissioning of DR 1, Final report

    International Nuclear Information System (INIS)

    Lauridsen, Kurt

    2006-01-01

    The report describes the decommissioning activities carried out at the 2kW homogeneous reactor DR 1 at Risoe National Laboratory. The decommissioning work took place from summer 2004 until late autumn 2005. The components with the highest activity, the core vessel the recombiner and the piping and valves connected to these, were dismantled first by Danish Decommissioning's own technicians. Demolition of the control rod house and the biological shield as well as the removal of the floor in the reactor hall was carried out by an external demolition contractor. The building was emptied and left for other use. Clearance measurements of the building showed that radionuclide concentrations were everywhere below the clearance limit set by the Danish nuclear regulatory authorities. Furthermore, measurements on the surrounding area showed that there was no contamination that could be attributed to the operation and decommissioning of DR 1. (au)

  3. Recent results on the neutron irradiation of ITER candidate copper alloys irradiated in DR-3 at 250{degrees}C to 0.3 dpa

    Energy Technology Data Exchange (ETDEWEB)

    Edwards, D.J. [Pacific Northwest National Lab., Richland, WA (United States); Singh, B.N.; Toft, P.; Eldrup, M.

    1997-04-01

    Tensile specimens of CuCrZr and CuNiBe alloys were given various heat treatments corresponding to solution anneal, prime-ageing and bonding thermal treatment with additional specimens re-aged and given a reactor bakeout treatment at 350{degrees}C for 100 h. CuAl-25 was also heat treated to simulate the effects of a bonding thermal cycle on the material. A number of heat treated specimens were neutron irradiated at 250{degrees}C to a dose level of {approximately}0.3 dpa in the DR-3 reactor as Riso. The main effect of the bonding thermal cycle heat treatment was a slight decrease in strength of CuCrZr and CuNiBe alloys. The strength of CuAl-25, on the other hand, remained almost unaltered. The post irradiation tests at 250{degrees}C showed a severe loss of ductility in the case of the CuNiBe alloy. The irradiated CuAl-25 and CuCrZr specimens exhibited a reasonable amount of uniform elongation, with CuCrZr possessing a lower strength.

  4. Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Qualls, A. L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Betzler, Benjamin R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Carbajo, Juan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Greenwood, Michael Scott [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hale, Richard Edward [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Robb, Kevin R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrell, Jerry W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-12-01

    Development of the Fluoride Salt-Cooled High-Temperature Reactor (FHR) Demonstration Reactor (DR) is a necessary intermediate step to enable commercial FHR deployment through disruptive and rapid technology development and demonstration. The FHR DR will utilize known, mature technology to close remaining gaps to commercial viability. Lower risk technologies are included in the initial FHR DR design to ensure that the reactor can be built, licensed, and operated within an acceptable budget and schedule. These technologies include tristructural-isotropic (TRISO) particle fuel, replaceable core structural material, the use of that same material for the primary and intermediate loops, and tube-and-shell heat exchangers. This report provides an update on the development of the FHR DR. At this writing, the core neutronics and thermal hydraulics have been developed and analyzed. The mechanical design details are still under development and are described to their current level of fidelity. It is anticipated that the FHR DR can be operational within 10 years because of the use of low-risk, near-term technology options.

  5. Preliminary Demonstration Reactor Point Design for the Fluoride Salt-Cooled High-Temperature Reactor

    International Nuclear Information System (INIS)

    Qualls, A. L.; Betzler, Benjamin R.; Brown, Nicholas R.; Carbajo, Juan; Greenwood, Michael Scott; Hale, Richard Edward; Harrison, Thomas J.; Powers, Jeffrey J.; Robb, Kevin R.; Terrell, Jerry W.

    2015-01-01

    Development of the Fluoride Salt-Cooled High-Temperature Reactor (FHR) Demonstration Reactor (DR) is a necessary intermediate step to enable commercial FHR deployment through disruptive and rapid technology development and demonstration. The FHR DR will utilize known, mature technology to close remaining gaps to commercial viability. Lower risk technologies are included in the initial FHR DR design to ensure that the reactor can be built, licensed, and operated within an acceptable budget and schedule. These technologies include tristructural-isotropic (TRISO) particle fuel, replaceable core structural material, the use of that same material for the primary and intermediate loops, and tube-and-shell heat exchangers. This report provides an update on the development of the FHR DR. At this writing, the core neutronics and thermal hydraulics have been developed and analyzed. The mechanical design details are still under development and are described to their current level of fidelity. It is anticipated that the FHR DR can be operational within 10 years because of the use of low-risk, near-term technology options.

  6. Limited field investigation report for the 100-DR-1 Operable Unit

    International Nuclear Information System (INIS)

    1994-06-01

    This limited field investigation (LFI) report summarizes the data collection and analysis activities conducted during the 100-DR-1 Source Operable Unite LFI and the associated qualitative risk assessment (QRA), and makes recommendations on the continued candidacy of high-priority sites for interim remedial measures (IRM). The results and recommendations presented in this report are generally independent of future land use scenarios. The 100-DR-1 Operable Unit is one of four operable units associated with the 100 D/DR Area at the Hanford Site. The 100-DR-1 Operable Unit encompasses approximately 1.5 km 2 (0.59 mi 2 ) and is located immediately adjacent to the Columbia River shoreline. In general, it contains waste facilities associated with the original plant facilities constructed to support D Reactor facilities, as well as cooling water retention basin systems for both D and DR Reactors. The 100-DR-1 LFI began the investigative phase of the remedial investigation for a select number of high-priority sites. The LFI was performed to provide additional data needed to support selection, design and implementation of IRM, if needed. The LFI included data compilation, nonintrusive investigations, intrusive investigations, summarization of 100 Area aggregate studies, and data evaluation

  7. Fluoride Salt-Cooled High-Temperature Demonstration Reactor Point Design

    Energy Technology Data Exchange (ETDEWEB)

    Qualls, A. L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Betzler, Benjamin R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Carbajo, Juan [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Hale, Richard Edward [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Harrison, Thomas J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Powers, Jeffrey J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Robb, Kevin R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Terrell, Jerry W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Wysocki, Aaron J. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2016-02-01

    The fluoride salt-cooled high-temperature reactor (FHR) demonstration reactor (DR) is a concept for a salt-cooled reactor with 100 megawatts of thermal output (MWt). It would use tristructural-isotropic (TRISO) particle fuel within prismatic graphite blocks. FLiBe (2 LiF-BeF2) is the reference primary coolant. The FHR DR is designed to be small, simple, and affordable. Development of the FHR DR is a necessary intermediate step to enable near-term commercial FHRs. Lower risk technologies are purposely included in the initial FHR DR design to ensure that the reactor can be built, licensed, and operated within an acceptable budget and schedule. These technologies include TRISO particle fuel, replaceable core structural material, the use of that same material for the primary and intermediate loops, and tube-and-shell primary-to-intermediate heat exchangers. Several preconceptual and conceptual design efforts that have been conducted on FHR concepts bear a significant influence on the FHR DR design. Specific designs include the Oak Ridge National Laboratory (ORNL) advanced high-temperature reactor (AHTR) with 3400/1500 MWt/megawatts of electric output (MWe), as well as a 125 MWt small modular AHTR (SmAHTR) from ORNL. Other important examples are the Mk1 pebble bed FHR (PB-FHR) concept from the University of California, Berkeley (UCB), and an FHR test reactor design developed at the Massachusetts Institute of Technology (MIT). The MIT FHR test reactor is based on a prismatic fuel platform and is directly relevant to the present FHR DR design effort. These FHR concepts are based on reasonable assumptions for credible commercial prototypes. The FHR DR concept also directly benefits from the operating experience of the Molten Salt Reactor Experiment (MSRE), as well as the detailed design efforts for a large molten salt reactor concept and its breeder variant, the Molten Salt Breeder Reactor. The FHR DR technology is most representative of the 3400 MWt AHTR

  8. Dr Robert Aymar, Director of the International Thermonuclear Experimental Reactor (ITER), was nominated to succeed Professor Luciano Maiani as CERN's Director General, to take office on 1 January 2004.

    CERN Document Server

    2002-01-01

    Dr Robert Aymar, Director of the International Thermonuclear Experimental Reactor (ITER), was nominated to succeed Professor Luciano Maiani as CERN's Director General, to take office on 1 January 2004.

  9. Removal Action Work Plan for 105-DR and 105-F Building Interim Safe Storage Projects and Ancillary Buildings

    International Nuclear Information System (INIS)

    Morton, M.R.

    2000-01-01

    This document contains the removal action work plan for the 105-DR and 105-F Reactor buildings and ancillary facilities. These buildings and facilities are located in the 100-D/DR and 100-F Areas of the Hanford Site, which is owned and operated by the US Department of Energy (DOE), in Benton County, Washington. The 100 Areas (including the 100-D/DR and 100-F Areas) of the Hanford Site were placed on the US Environmental Protection Agency's (EPA's) National Priorities List under the ''Comprehensive Environmental Response, Compensation, and Liability Act of 1980'' (CERCLA). The DOE has determined that hazardous substances in the 105-DR and 105-F Reactor buildings and four ancillary facilities present a potential threat to human health or the environment. The DOE has also determined that a non-time critical removal action is warranted at these facilities. Alternatives for conducting a non-time critical removal action were evaluated in the ''Engineering Evaluation/Cost Analysis for the 105-DR and 105-F Reactor Facilities and Ancillary Facilities'' (DOE-RL 1998a). The engineering evaluation/cost analysis (EE/CA) resulted in the recommendation to decontaminate and demolish the contaminated reactor buildings (except for the reactor blocks) and the ancillary facilities and to construct a safe storage enclosure (SSE) over the reactor blocks. The recommendation was approved in an action memorandum (Ecology et al. 1998) signed by the Washington State Department of Ecology (Ecology), EPA, and DOE. The DOE is the agency responsible for implementing the removal actions in the 105-D/DR and 105-F Areas. Ecology is the lead regulatory agency for facilities in the 100-D/DR Area, and EPA is the lead regulatory agency for facilities in the 100-F Area. The term ''lead regulator agency'' hereinafter, refers to these authorities. This removal action work plan supports implementation of the non-time critical removal action

  10. DR3 regulation of apoptosis of naive T-lymphocytes in children with acute infectious mononucleosis.

    Science.gov (United States)

    Filatova, Elena Nikolaevna; Anisenkova, Elena Viktorovna; Presnyakova, Nataliya Borisovna; Utkin, Oleg Vladimirovich

    2016-09-01

    Acute infectious mononucleosis (AIM) is a widespread viral disease that mostly affects children. Development of AIM is accompanied by a change in the ratio of immune cells. This is provided by means of different biological processes including the regulation of apoptosis of naive T-cells. One of the potential regulators of apoptosis of T-lymphocytes is a death receptor 3 (DR3). We have studied the role of DR3 in the regulation of apoptosis of naive CD4 + (nTh) and CD8 + (nCTL) T-cells in healthy children and children with AIM. In healthy children as well as in children with AIM, the activation of DR3 is accompanied by inhibition of apoptosis of nTh. In healthy children, the stimulation of DR3 resulted in the increase in apoptosis of nCTL. On the contrary, in children with AIM, the level of apoptosis of nCTL decreased after DR3 activation, which is a positive contribution to the antiviral immune response. In children with AIM, nCTL are characterized by reduced level of apoptosis as compared with healthy children. These results indicate that DR3 can be involved in the reduction of sensitivity of nCTL to apoptosis in children with AIM.

  11. Early onset of diabetes in the proband is the major determinant of risk in HLA DR3-DQ2/DR4-DQ8 siblings.

    Science.gov (United States)

    Gillespie, Kathleen M; Aitken, Rachel J; Wilson, Isabel; Williams, Alistair J K; Bingley, Polly J

    2014-03-01

    Islet autoimmunity is initiated in infancy, and primary prevention trials require children at high genetic risk to be identified before autoantibodies appear. To inform screening strategies, we evaluated risks of autoimmunity and diabetes associated with HLA DR3-DQ2/DR4-DQ8 in U.K. families. Extended HLA haplotypes were determined in 2,134 siblings from the Bart's-Oxford Study followed to a median age of 22 years. Risks of diabetes and islet autoimmunity (more than two antibodies) were estimated by survival analysis. Of 138 informative DR3-DQ2/DR4-DQ8 siblings, 63% shared both haplotypes with their diabetic proband, 29% shared one, and 8% shared neither. In HLA-identical DR3-DQ2/DR4-DQ8 siblings, the cumulative risk of diabetes by age 15 was 17% (vs. 6% in those sharing one haplotype or none; P = 0.095). Risk varied, however, with the age at the onset of diabetes in the proband; the cumulative risk of autoimmunity and/or diabetes by age 15 was 61% in siblings of probands diagnosed when younger than 10 years old compared with only 4.7% in those diagnosed after age 10 years (P sibling risk. This suggests that non-HLA genes or epigenetic/environmental factors that accelerate the progression of type 1 diabetes in the proband strongly affect risk in siblings.

  12. State Environmental Policy Act (SEPA) Checklist for the 105-DR Large Sodium Fire Facility Closure Plan

    Energy Technology Data Exchange (ETDEWEB)

    1990-09-01

    The Hanford Site, located northwest of the city of Richland, Washington, houses reactors, chemical-separation systems, and related facilities used for the production of special nuclear materials, as well as for activities associated with nuclear energy development. The 105-DR Large Sodium Fire Facility (LSFF), which was in operation from about 1972 to 1986, was a research laboratory that occupied the former ventilation supply room on the southwest side of the 105-DR Reactor facility. The LSFF was established to provide means of investigating fire and safety aspects associated with large sodium or other metal alkali fires in the liquid metal fast breeder reactor (LMFBR) facilities. The 105-DR Reactor facility was designed and built in the 1950's and is located in the 100-D Area of the Hanford Site. The building housed the DR defense reactor, which was shut down in 1964. The LSFF is subject to the regulatory requirements for the storage and treatment of dangerous wastes. Clean closure is the proposed method of closure for the LSFF. Closure will be conducted pursuant to the requirements of the Washington Administrative Code (WAC) 173-303-610 (Ecology 1989). This closure plan presents a description of the facility, the history of wastes managed, and the procedures that will be followed to close the LSFF as an Alkali Metal Treatment Facility. No future use of the LSFF is expected.

  13. Human radiation studies: Remembering the early years. Oral history of Dr. George Voelz, M.D., November 29, 1994

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1995-05-01

    Dr. George Voelz was interviewed by representatives of the US DOE Office of Human Radiation Experiments (OHRE). This oral history covers Dr. Voelz`s research on Manhattan Engineering District plutonium workers, the acute and long term effects of radiation, his inhalation studies, and his activities at the 1961 INL reactor accident (SL-1 Reactor). After a brief biographical sketch, Dr. Voelz his remembrances on tissue studies of plutonium workers, the plutonium injection studies of 1945-1946, the controlled environmental radioiodine tests of 1963-1968, and tracer studies with human volunteers at Los Alamos. Dr. Voelz states his opinions concerning misconceptions about the Los Alamos Human Radiation Experiments.

  14. Human radiation studies: Remembering the early years. Oral history of Dr. George Voelz, M.D., November 29, 1994

    International Nuclear Information System (INIS)

    1995-05-01

    Dr. George Voelz was interviewed by representatives of the US DOE Office of Human Radiation Experiments (OHRE). This oral history covers Dr. Voelz's research on Manhattan Engineering District plutonium workers, the acute and long term effects of radiation, his inhalation studies, and his activities at the 1961 INL reactor accident (SL-1 Reactor). After a brief biographical sketch, Dr. Voelz his remembrances on tissue studies of plutonium workers, the plutonium injection studies of 1945-1946, the controlled environmental radioiodine tests of 1963-1968, and tracer studies with human volunteers at Los Alamos. Dr. Voelz states his opinions concerning misconceptions about the Los Alamos Human Radiation Experiments

  15. Department of reactor technology

    International Nuclear Information System (INIS)

    1980-01-01

    The activities of the Department of Reactor Technology at Risoe during 1979 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  16. DrSPINE - New approach to data reduction and analysis for neutron spin echo experiments from pulsed and reactor sources

    International Nuclear Information System (INIS)

    Zolnierczuk, P.A.; Ohl, M.; Holderer, O.; Monkenbusch, M.

    2015-01-01

    Neutron spin echo (NSE) method at a pulsed neutron source presents new challenges to the data reduction and analysis as compared to the instruments installed at reactor sources. The main advantage of the pulsed source NSE is the ability to resolve the neutron wavelength and collect neutrons over a wider bandwidth. This allows us to more precisely determine the symmetry phase and measure the data for several Q-values at the same time. Based on the experience gained at the SNS NSE - the first, and to date the only one, NSE instrument installed at a pulsed spallation source, we propose a novel and unified approach to the NSE data processing called DrSPINE. The goals of the DrSPINE project are: -) exploit better symmetry phase determination due to the broader bandwidth at a pulsed source; -) take advantage of larger Q coverage for TOF instruments; -) use objective statistical criteria to get the echo fits right; -) provide robust reduction with report generation; -) incorporate absolute instrument calibration; and -) allow for background subtraction. The software must be able to read the data from various instruments, perform data integrity, consistency and compatibility checks and combine the data from compatible sets, partial scans, etc. We chose to provide a console-based interface with the ability to process macros (scripts) for batch evaluation. And last and not the least, a good software package has to provide adequate documentation. DrSPINE software is currently under development

  17. Deletion mutant defines DQ beta variants with DR4 positive DQw3 positive haplotypes

    International Nuclear Information System (INIS)

    Nepom, B.S.; Kim, S.J.; Nepom, G.T.

    1986-01-01

    We describe the production of an HLA deletion mutation by radiation mutagenesis of a DR4- and DQw3-homozygous, Dw4- and Dw14-heterozygous cell line designed to analyze polymorphisms associated with DR4 and DQw3. Southern blot analysis confirms a deletion of class I and class II genes on one haplotype. Variation in DQ beta alleles associated with DQw3 was previously described by characteristic RFLP patterns for a DQ beta bene. One pattern, which correlated precisely with A-10-83 monoclonal antibody reactivity (TA10), defined an allele which we call DQ''3.1''. The mutant cell line has lost the polymorphic bands on Southern blots corresponding to the DQ''3.1'' allele, while the intact Dw14 haplotype retains the alternate allele at DQ beta which is DQw-3 positive. TA10-negative. These data demonstrate the segregation of two DQw3 positive DQ beta allelic variants, both associated with DR4, which can be distinguished on the basis of both RFLP and monoclonal antibody reactivity

  18. Multifunctional PMMA@Fe3O4@DR Magnetic Materials for Efficient Adsorption of Dyes

    Directory of Open Access Journals (Sweden)

    Bing Yu

    2017-10-01

    Full Text Available Magnetic porous microspheres are widely used in modern wastewater treatment technology due to their simple and quick dye adsorption and separation functions. In this article, we prepared porous polymethylmethacrylate (PMMA microspheres by the seed-swelling method, followed by in situ formation of iron oxide (Fe3O4 nanoparticles within the pore. Then, we used diazo-resin (DR to encapsulate the porous magnetic microspheres and achieve PMMA@Fe3O4@DR magnetic material. We studied the different properties of magnetic microspheres by different dye adsorption experiments before and after the encapsulation and demonstrated that the PMMA@Fe3O4@DR microspheres can be successfully used as a reusable absorbent for fast and easy removal of anionic and aromatic dyes from wastewater and can maintain excellent magnetic and adsorption properties in harsh environments.

  19. JENDL-3.3 thermal reactor benchmark test

    International Nuclear Information System (INIS)

    Akie, Hiroshi

    2001-01-01

    Integral tests of JENDL-3.2 nuclear data library have been carried out by Reactor Integral Test WG of Japanese Nuclear Data Committee. The most important problem in the thermal reactor benchmark testing was the overestimation of the multiplication factor of the U fueled cores. With several revisions of the data of 235 U and the other nuclides, JENDL-3.3 data library gives a good estimation of multiplication factors both for U and Pu fueled thermal reactors. (author)

  20. Radiation protection measures during the decommissioning of DR 2

    International Nuclear Information System (INIS)

    Larsen, Thommy Ingemann; Hedemann Jensen, Per; Sogaard-Hansena, Jens; Lauridsen, Bente

    2008-01-01

    DR 2 (Danish Reactor 2), one of the research reactors at the Riso site, has been in the process of being decommissioned during the last two years. The decommissioning will be completed in 2008. The reactor went critical for the first time in late 1958 and was shut down in 1975. The construction was a 5 MW light-water moderated and cooled tank type reactor. Although the process of decommissioning was formally initiated in 2005, it was preceded by a characterization project with the purpose of determining activity contents in key materials and dose rates at relevant spots in the reactor. The paper describes the removal of neutron beam plugs, grid plate and a thermal column with focus on radiation protection issues. The primary objective is, however, to describe the measures taken to control radiation doses during the removal of the reactor block concrete and the reactor tank.The demolition and removal of concrete was done by an external contractor. The contractor had to comply with a comprehensive set of requirements. This included splitting activated concrete from concrete containing activities below clearance levels with no use of fluids of any kind, as the risk of not being able to control diffusion of contaminated fluids was an important issue. The experience from the decommissioning of the DR 1 reactor in 2005 showed that water-cooled cutting made it very difficult to monitor the levels of air contamination as the filters of the air monitors were blocked frequently. Certainly, dry cutting turned out to be a great technical challenge to the external contractor. Another demand was that the work should take place inside a de-pressurized containment in order to control air contamination and thereby minimize internal doses. The experience gathered from the practical implementation of dose reducing measures will be discussed. Problems involving the use of external contractors will be discussed, including training of personnel with no prior knowledge of radioactivity

  1. Removal Action Workplan for the 105-DR and 105-F Building Interim Safe Storage Projects and Ancillary Buildings

    International Nuclear Information System (INIS)

    Rodovsky, T. J.

    1999-01-01

    This document is the removal action workplan (RAW) for the 105-DR and 105-F Reactor Buildings and ancillary facilities. These buildings and facilities are located in the 100-D/DR and 100-F Areas of the Hanford Site in Benton County, Washington, which is owned and operated by the U.S. Department of Energy (DOE). The 100 Areas (including 100-D/DR and 100-F Areas) of the Hanford Site were placed on the U.S. Environmental Protection Agency's (EPA) National Priorities List under the Comprehensive Environmental Response, Compensation,and Liability Act of 1980 (CERCLA). DOE has determined that hazardous substances in the 105-DR and 105-F Reactor Buildings and four ancillary facilities present a potential threat to human health or the environment DOE has also determined that a non-time critical removal action is warranted at these facilities

  2. Direct ex vivo detection of HLA-DR3-restricted cytomegalovirus- and Mycobacterium tuberculosis-specific CD4+ T cells.

    Science.gov (United States)

    Bronke, Corine; Palmer, Nanette M; Westerlaken, Geertje H A; Toebes, Mireille; van Schijndel, Gijs M W; Purwaha, Veenu; van Meijgaarden, Krista E; Schumacher, Ton N M; van Baarle, Debbie; Tesselaar, Kiki; Geluk, Annemieke

    2005-09-01

    In order to detect epitope-specific CD4+ T cells in mycobacterial or viral infections in the context of human class II major histocompatibility complex protein human leukocyte antigen (HLA)-DR3, two HLA-DR3 tetrameric molecules were successfully produced. One contained an immunodominant HLA-DR3-restricted T-cell epitope derived from the 65-kDa heat-shock protein of Mycobacterium tuberculosis, peptide 1-13. For the other tetramer, we used an HLA-DR3-restricted T-cell epitope derived from cytomegalovirus (CMV) pp65 lower matrix protein, peptide 510-522, which induced high levels of interferon (IFN)-gamma-producing CD4+ T cells in three of four HLA-DR3-positive CMV-seropositive individuals up to 0.84% of CD4+ T cells by intracellular cytokine staining. In peripheral blood mononuclear cells from M. tuberculosis-exposed, Mycobacterium bovis bacille Calmette-Guérin (BCG)-vaccinated, or CMV-seropositive individuals, we were able to directly detect with both tetramers epitope-specific T cells up to 0.62% and 0.45% of the CD4+ T-cell population reactive to M. tuberculosis and CMV, respectively. After a 6-day culture with peptide p510-522, the frequency of CMV-specific tetramer-binding T cells was expanded up to 9.90% tetramer+ CFSElow (5,6-carboxyfluorescein diacetate succinimidyl ester) cells within the CD4+ T-cell population, further confirming the specificity of the tetrameric molecules. Thus, HLA-DR3/peptide tetrameric molecules can be used to investigate HLA-DR3-restricted antigen-specific CD4+ T cells in clinical disease or after vaccination.

  3. Dynamics of TRIGA-3 Salazar Reactor

    International Nuclear Information System (INIS)

    Gallardo S, L.F.

    1990-01-01

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author)

  4. FOREWORD: Dr Trevor J Hicks Dr Trevor J Hicks

    Science.gov (United States)

    Goossens, Darren

    2009-03-01

    This issue of Journal of Physics: Condensed Matter has been assembled to recognize the valuable contribution of Dr Trevor J Hicks to the field of neutron scattering and magnetism. Trevor began his study of magnetism as a PhD student at Monash University in Melbourne in the early 1960s, working with Professor Jack Smith. From the very beginning magnetism in alloys, and disordered systems in general, became a key aspect of his career. After a postdoctoral position at Harwell working with Dr Graeme Low Trevor returned to Australia and took up a position with Monash. He soon became a key figure in developing the capability for neutron scattering using the HIFAR reactor at the Australian Atomic Energy Commission, now the Australian Nuclear Science and Technology Organisation, ANSTO. The instrumentation was always developed to further his studies of magnetism. The development of polarization analysis measurements of diffuse magnetic scattering, first using iron filters and then his own design of supermirror benders for beam polarization, took place through the 1970s, 1980s and into the 1990s. Throughout this time, Trevor mentored a series of PhD students and postdoctoral fellows, many of whom have contributed to this issue (and, indeed, guest edited it). As befits a scientist and university academic for whom teaching has always been important, Trevor has not only created a strong body of significant research, he has also made a major contribution to preparing several generations of neutron scattering scientists, and this issue reflects that. When I approached Journal of Physics: Condensed Matter with a proposal for an issue in honour of Trevor, the response was immediate and positive. It is with great pleasure that I present the result of that proposal. The great diversity of the content, all centred on neutron scattering and magnetism, reflects the breadth of Trevor's own career and of the scientists with whom he has interacted. Finally, I would like to make some

  5. Analysis of DR4 haplotypes in insulin dependent diabetes (IDD)

    International Nuclear Information System (INIS)

    Monos, D.S.; Radka, S.F.; Zmijewski, C.M.; Kamoun, M.

    1986-01-01

    Population studies indicate that HLA-DR4 is implicated in the susceptibility of IDD. However, biochemical characterization of the serologically defined DR4 haplotype from normal individuals revealed five DR4 and three DQW3 molecular forms. Hence, in this study, they investigated the heterogeneity of the DR4 haplotype, using B-lymphoblastoid cell lines (B-LCL) generated from patients with IDD and seropositive for DR4. Class II molecules, metabolically labeled with 35 S-methionine, were immunoprecipitated with monoclonal antibodies specific for DR(L243), DQ(N297), DQW3(IVD12) or DR and DQ(SG465) and analyzed by two-dimensional polyacrylamide gel electrophoresis (2D-PAGE). The isoelectrofocusing (IEF) conditions employed in this study allow representation only of the DR4 haplotype from either DR3/4 or DR4/4 cell lines. The analysis of six different DR4 haplotypes from seven IDD patients, revealed the presence of two DR4 β and two DQW3 β chains. Three of the six DR4 β haplotypes analyzed shared the same DR4 β chain and three others shared a different one. Additionally five of the six haplotypes shared a different one. Additionally five of the six haplotypes shared the same DQW3 β chain and only one was carrying a different one. Different combinations of the two DR4 and two DQW3 β chains constitute three distinct patterns of DR4 haplotypes. These results suggest the prevalence of a DQW3 β chain in the small sample of IDD patients studied. Studies of a large number of patients should clarify whether IDD is associated with unique variants of DR4 or DQW3 β chains

  6. Irradiation tests of THTR fuel elements in the DRAGON reactor (irradiation experiment DR-K3)

    International Nuclear Information System (INIS)

    Burck, W.; Duwe, R.; Groos, E.; Mueller, H.

    1977-03-01

    Within the scope of the program 'Development of Spherical Fuel Elements for HTR', similar fuel elements (f.e.) have been irradiated in the DRAGON reactor. The f.e. were fabricated by NUKEM and were to be tested under HTR conditions to scrutinize their employability in the THTR. The fuel was in the form of coated particles moulded into A3 matrix. The kernels of the particles were made of mixed oxide of uranium and thorium with an U 235 enrichment of 90%. One aim of the post irradiation examination was the investigation of irradiation induced changes of mechanical properties (dimensional stability and elastic behaviour) and of the corrosion behaviour which were compared with the properties determined with unirradiated f.e. The measurement of the fission gas release in annealing tests and ceramografic examinations exhibited no damage of the coated particles. The measured concentration distribution of fission metals led to conclusions about their release. All results showed, that neither the coated particles nor the integral fuel spheres experienced any significant changes that could impair their utilization in the THTR. (orig./UA) [de

  7. Paraquat induces extrinsic pathway of apoptosis in A549 cells by induction of DR5 and repression of anti-apoptotic proteins, DDX3 and GSK3 expression.

    Science.gov (United States)

    Hathaichoti, Sasiphen; Visitnonthachai, Daranee; Ngamsiri, Pronrumpa; Niyomchan, Apichaya; Tsogtbayar, Oyu; Wisessaowapak, Churaibhon; Watcharasit, Piyajit; Satayavivad, Jutamaad

    2017-08-01

    Paraquat (PQ) is a bipyridyl derivative herbicide known to cause lung toxicity partly through induction of apoptosis. Here we demonstrated that PQ caused apoptosis in A549 cells. PQ increased cleavage of caspase-8 and Bid, indicating caspase-8 activation and truncated Bid, the two key mediators of extrinsic apoptosis. Additionally, PQ treatment caused an increase in DR5 (death receptor-5) and caspase-8 interaction, indicating formation of DISC (death-inducing signaling complex). These results indicate that PQ induces apoptosis through extrinsic pathway in A549 cells. Moreover, PQ drastically increased DR5 expression and membrane localization. Furthermore, PQ caused prominent concentration dependent reductions of DDX3 (the DEAD box protein-3) and GSK3 (glycogen synthase kinase-3) which can associate with DR5 and prevent DISC formation. Additionally, PQ decreased DR5-DDX3 interaction, suggesting a reduction of DDX3/GSK3 anti-apoptotic complex. Inhibition of GSK3, which is known to promote extrinsic apoptosis by its pharmacological inhibitor, BIO accentuated PQ-induced apoptosis. Moreover, GSK3 inhibition caused a further decrease in PQ-reduced DR5-DDX3 interaction. Taken together, these results suggest that PQ may induce extrinsic pathway of apoptosis in A549 cells through upregulation of DR5 and repression of anti-apoptotic proteins, DDX3/GSK3 leading to reduction of anti-apoptotic complex. Copyright © 2017 Elsevier Ltd. All rights reserved.

  8. Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration

    Energy Technology Data Exchange (ETDEWEB)

    J. Wesley Hines; Belle R. Upadhyaya; J. Michael Doster; Robert M. Edwards; Kenneth D. Lewis; Paul Turinsky; Jamie Coble

    2011-05-31

    on meeting two of the eight needs outlined in the recently published 'Technology Roadmap on Instrumentation, Control, and Human-Machine Interface (ICHMI) to Support DOE Advanced Nuclear Energy Programs' which was created 'to provide a systematic path forward for the integration of new ICHMI technologies in both near-term and future nuclear power plants and the reinvigoration of the U.S. nuclear ICHMI community and capabilities.' The research consortium is led by The University of Tennessee (UT) and is focused on three interrelated topics: Topic 1 (simulator development and measurement sensitivity analysis) is led by Dr. Mike Doster with Dr. Paul Turinsky of North Carolina State University (NCSU). Topic 2 (multivariate autonomous control of modular reactors) is led by Dr. Belle Upadhyaya of the University of Tennessee (UT) and Dr. Robert Edwards of Penn State University (PSU). Topic 3 (monitoring, diagnostics, and prognostics system development) is led by Dr. Wes Hines of UT. Additionally, South Carolina State University (SCSU, Dr. Ken Lewis) participated in this research through summer interns, visiting faculty, and on-campus research projects identified throughout the grant period. Lastly, Westinghouse Science and Technology Center (Dr. Mario Carelli) was a no-cost collaborator and provided design information related to the IRIS demonstration platform and defining needs that may be common to other SMR designs. The results of this research are reported in a six-volume Final Report (including the Executive Summary, Volume 1). Volumes 2 through 6 of the report describe in detail the research and development under the topical areas. This volume serves to introduce the overall NERI-C project and to summarize the key results. Section 2 provides a summary of the significant contributions of this project. A list of all the publications under this project is also given in Section 2. Section 3 provides a brief summary of each of the five volumes (2-6) of

  9. Association of HLA-DR3 with human immune response to Lol p I and Lol p II allergens in allergic subjects.

    Science.gov (United States)

    Freidhoff, L R; Ehrlich-Kautzky, E; Meyers, D A; Ansari, A A; Bias, W B; Marsh, D G

    1988-04-01

    Associations between HLA type and IgE or IgG antibody (Ab) responses to two well-characterized, antigenetically non-crossreactive components of Lolium perenne (rye grass) pollen extract, Lol p I (Rye I) and Lol p II (Rye II) were studied in two groups of skin-test positive (ST+) Caucasoid adults. By both nonparametric and parametric statistical methods, significant associations were found between Ab responses to both Lol I and Lol II and the possession of HLA-DR3. In view of the well-known associations of both DR3 and B8 (which are in linkage disequilibrium) with many autoimmune diseases, differences in anti-Lol I and anti-Lol II mean log[Ab] levels between B8+, DR3- vs B8-, DR3- subjects and B8+, DR3+ vs B8-, DR3+ subjects were investigated. No differences were found. Our data, along with recent RFLP and DNA sequence studies, suggest that an Ia molecule involved in immune recognition of a similar major Ia recognition site of both the Lol molecules may consist of a DR3 alpha-beta I pair. Abbreviations used: Ab: Antibody. HLA: Human leukocyte antigen. Lol p I, Lol I: Group I allergen from Lolium perenne pollen (Rye I). Lol p II, Lol II: Group II allergen from Lolium perenne pollen (Rye II). Mr: Relative molecular mass. Rx: Immunotherapy with grass pollen extracts. ST: Skin test.

  10. The cold neutron source in DR 3

    International Nuclear Information System (INIS)

    Jensen, K.; Leth, j.A.

    1980-09-01

    A description of the cold neutron source in DR 3 is given. The moderator of the cold neutron source is supercritical hydrogen at about 30degK and 15 bar abs. The necessary cooling capacity is supplied by two Philips Stirling B20 cryogenerators. The hydrogen is circulated between the cryogenerators and the in-pile moderator chamber by small fans. The safety of the facility is based on the use of triple containment preventing contact between hydrogen and air. The triple containment is achieved by enclosing the high vacuum system, surrounging the hydrogen system, in a helium blanket. The achieved spectrum of the thermal neutron flux and the gain factor are given as well as the experience from more than 5 years of operation. Finally some work on extension of the facility to operate two cold sources is reported. (author)

  11. Farewell to a reactor

    International Nuclear Information System (INIS)

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  12. Decay ratio estimation in pressurized water reactor

    International Nuclear Information System (INIS)

    Por, G.; Runkel, J.

    1990-11-01

    The well known decay ratio (DR) from stability analysis of boiling water reactors (BWR) is estimated from the impulse response function which was evaluated using a simplified univariate autoregression method. This simplified DR called modified DR (mDR) was applied on neutron noise measurements carried out during five fuel cycles of a 1300 MWe PWR. Results show that this fast evaluation method can be used for monitoring of the growing oscillation of the neutron flux during the fuel cycles which is a major concern of utilities in PWRs, thus it can be used for estimating safety margins. (author) 17 refs.; 10 figs

  13. Progranulin-derived Atsttrin directly binds to TNFRSF25 (DR3 and inhibits TNF-like ligand 1A (TL1A activity.

    Directory of Open Access Journals (Sweden)

    Cui Liu

    Full Text Available Atsttrin, a progranulin (PGRN-derived molecule composed of three TNFR-binding domains of PGRN, binds to TNF receptors (TNFR and is therapeutic against inflammatory arthritis. Here we screened the associations of Atsttrin and other members in TNFR subfamily, which led to the discovery of TNFRSF25 (DR3 as an additional Atsttrin-interacting member in TNFR family. Similar to TNFR1 and TNFR2, DR3 also directly bound to Atsttrin. The first three cysteine-rich domains (CRD in the extracellular portion of DR3 were required for this interaction. Atsttrin inhibited the interaction between DR3 and its TNF-Like Ligand 1A (TL1A. In addition, Atsttrin inhibited TL1A-stimulated target gene expressions and neutralized TL1A-enhanced osteoclastogenesis in vitro. Furthermore, Atsttrin ameliorated the pathology in dextran sulfate sodium induced colitis. Taken together, these findings not only provide the new insights into Atsttrin's therapeutic action in inflammatory arthritis, but may also present Atsttrin as a novel biological agent for treating various types of diseases associated with TL1A/DR3 pathway.

  14. Realizing vision of Dr. Homi Bhabha - first stage of nuclear power programme

    International Nuclear Information System (INIS)

    Bhardwaj, S.A.

    2009-01-01

    Full text: Dr. Homi Bhabha had a vision to harness nuclear energy for peaceful uses of mankind. Considering typical nuclear resources in the country, Dr Bhabha conceptualized the three stage nuclear power programme and gave a road map for its implementation. The robustness of the vision is such that the programme has not undergone a change in last five decades. The first stage of the three-stage programme, based on natural uranium fuelled Pressurised Heavy Water Reactors (PHWRs) has been precursor to the nuclear power programme in India. This paper describes the developments in the last five decades. The establishment of research laboratories and reactors, training school for the manpower needs, industrial infrastructure and establishment of regulatory framework are briefly described. Setting up of first nuclear power reactor in the country as turnkey project and experience on operation of these reactors in India are discussed. The learning phase consisting of setting up of first PHWR in technical collaboration with Canada and design of 220 MWe PHWRs for MAPS is described. The safety features consistent with development of nuclear power globally were incorporated in Narora design and this became a standardized 220 MWe reactor of which many PHWRs of 220 MWe were set up. The experiences with operation of these small size reactors leading to internationally best operational experience in the year 2002 are discussed. The efforts of plant life extension, in-core maintenance jobs and other renovation and modernization jobs are discussed. The increase in unit size of 540 MWe, of which two reactors have been already set up, is explained in detail. The economies of scale demanded increase in the unit size and design of 700 MWe PHWR has been established and the salient features of this design are also discussed in detail. Eight reactors of 700 MWe each would complete the first stage of about 10,000 MWe PHWR programme and plans for setting up of these reactors are discussed

  15. Data Reconciliation and Gross Error Detection for Troubleshooting of Ammonia Reactor

    Directory of Open Access Journals (Sweden)

    Adhi Tri Partono

    2018-01-01

    Full Text Available Data reconciliation (DR and gross error detection are two common tools used in industry to provide accurate and reliable data, which is useful to analyse plant performance and basis for troubleshooting. DR techniques improve the accuracy of measurements by using redundancies in material and energy balances. This provides reliable information that could help decision making regarding plant operation, which potentially leads to financial benefit. This paper presents the utilization of plant data to perform troubleshooting of ammonia reactor, in particular the profile of catalyst activity. Bad plant data are collected and then analysed using DR to produces reconciled data, which could be used to detect and identify the gross error measurements. The input data for DR and gross error detection were gathered from Aspen HYSYS V8.8 simulations by modelling the single-bed ammonia reactor. The result presents that bad plant data could define actual system condition such as gross error measurements in normal condition or catalyst activity problem. Both conditions are modelled by DR to indicate actual system condition using statistical analysis and to perform troubleshooting. Appropriate troubleshooting could save time and provide financial benefits by avoiding wrong accusation of system problem, specifically in ammonia reactor evaluated in this paper.

  16. Shepard Award Winners, Part 3: Dr. Larissa Roux

    Centers for Disease Control (CDC) Podcasts

    2009-09-22

    This podcast highlights the accomplishments of Dr. Larissa Roux, recipient of the prestigious 2009 CDC Charles C. Shepard Award.  Created: 9/22/2009 by Centers for Disease Control and Prevention (CDC).   Date Released: 9/22/2009.

  17. HLA-DR expression and disease activity in ulcerative colitis

    DEFF Research Database (Denmark)

    Poulsen, L O; Elling, P; Sørensen, Flemming Brandt

    1986-01-01

    In 12 patients with active ulcerative colitis (UC) the rectal epithelial cells were analyzed for HLA-DR antigens by an immunohistochemical technique. The clinical, rectoscopic, and histologic stages were also determined. The investigations were carried out at the beginning of the study and 2 weeks...... and 3 months later. The rectal epithelial cells were HLA-DR-positive in all patients at the first two examinations. After 3 months five patients had changed to an HLA-DR-negative stage, whereas the other seven patients remained HLA-DR-positive. Closer analyses showed that expression/nonexpression of HLA-DR...... antigens on rectal epithelial cells of patients with UC could not be predicted from the clinical, rectoscopic, or histologic findings. HLA-DR expression is normally restricted to immunocompetent cells. The presence of HLA-DR antigens on epithelial cells may be a consequence of immunological reactions...

  18. HLA-DR expression and disease activity in ulcerative colitis

    DEFF Research Database (Denmark)

    Poulsen, L O; Elling, P; Sørensen, Flemming Brandt

    1986-01-01

    and 3 months later. The rectal epithelial cells were HLA-DR-positive in all patients at the first two examinations. After 3 months five patients had changed to an HLA-DR-negative stage, whereas the other seven patients remained HLA-DR-positive. Closer analyses showed that expression/nonexpression of HLA...

  19. 95 GHz methanol masers near DR 21 and DR 21(OH)

    International Nuclear Information System (INIS)

    Plambeck, R.L.; Menten, K.M.

    1990-01-01

    The BIMA array is used to map the 95-GHz 8(0) to 7 1A(+) transition of methanol and the 98-GHz J = 2-1 transition of CS toward the DR 21(OH) and DR 21 star-forming regions. Several strong methanol masers were found. The positions of the two brightest masers were measured with an accuracy of about + or - 0.3 arcsec. Toward DR 21(OH), the positions, velocities, and line shapes of the 95 GHz masers are in excellent agreement with those of the 84-GHz 5(-1) to 4 () methanol masers previously mapped by Batrla and Menten (1988), demonstrating that maser emission in both transitions originates from the same clumps of gas. The methanol masers are offset from CS emission peaks and from other known infrared and maser sources; they may possibly be clustered along the interface between outflows, traced by shock-excited H2 emission, and dense ambient gas, traced by CS emission. 25 refs

  20. Waste Management Plan for the Drilling Within the Chromium Plume West of 100-D/DR Reactors

    International Nuclear Information System (INIS)

    R.E. Peterson

    1997-01-01

    This waste management plan provides guidance for managing drilling spoils generated during the installation of groundwater wells in the 100-D/DR Area, which is part of the 100-HR-3 Operable Unit. The wells are being installed to meet two objectives: (1) better define the nature and extent of a previously identified chromium plume in the area, and (2) act as groundwater extraction wells if the contamination warrants

  1. Analysis of the interim safe storage of reactors at the Hanford site

    International Nuclear Information System (INIS)

    Wang Hailiang

    2014-01-01

    The nine production reactors, i.e. B, C, D, DR, F, H, KE, KW and N, at the Hanford site are all water-cooled and graphite-moderated reactors with natural uranium fuel. In 1993, the U.S. Department of Energy (DOE) decided to put eight production reactors (except for B) into Interim Safe Storage (ISS) for 75 years followed by deferred one-piece removal. Reactor B will remain as a national historical landmark. By the end of 2013, six reactors C, F, D, DR, H and N had been successfully put into the ISS. Reactors KE and KW will be put into the ISS in the coming years. Taking reactor C as an example, this paper mainly talks about how to put the production reactors in the Interim Safe Storage, e.g. how to make site preparation, how to construct the safe storage enclosure (SSE) and how to perform surveillance and maintenance during the ISS period, etc. (authors)

  2. Decommissioning of a small reactor (BR3 reactor, Belgium)

    International Nuclear Information System (INIS)

    Dadoumont, J.; Massaut, V.; Klein, M.; Demeulemeester, Y.

    2002-01-01

    Since 1989, SCK-CEN has been dismantling its PWR reactor BR3 (Belgian Reactor No. 3). After gaining a great deal of experience in remote dismantling of highly radioactive components during the actual dismantling of the two sets of internals, the BR3 team completed the cutting of its reactor pressure vessel (RPV). During the feasibility phase of the RPV dismantling, a decision was made to cut it under water in the refuelling pool of the plant, after having removed it from its cavity. The RPV was cut into segments using a milling cutter and a bandsaw machine. These mechanical techniques have shown their ability for this kind of operations. Prior to the segmentation, the thermal insulation situated around the RPV was remotely removed and disposed of. The paper will describe all these operations. The BR3 decommissioning activities also include the dismantling of contaminated loops and equipment. After a careful sorting of the pieces, optimized management routes are selected in order to minimize the final amount of radioactive waste to be disposed of. Some development of different methods of decontamination were carried out: abrasive blasting (or sand blasting), chemical decontamination (Oxidizing-Reducing process using Cerium). The main goal of the decontamination program is to recycle most of the metallic materials either in the nuclear world or in the industrial world by reaching the respective recycling or clearance level. Overall the decommissioning of the BR3 reactor has shown the feasibility of performing such a project in a safe and economical way. Moreover, BR3 has developed methodologies and decontamination processes to economically reduce the amount of radwaste produced. (author)

  3. Haplotype Analysis Discriminates Genetic Risk for DR3-Associated Endocrine Autoimmunity and Helps Define Extreme Risk for Addison’s Disease

    Science.gov (United States)

    Baker, Peter R.; Baschal, Erin E.; Fain, Pam R.; Triolo, Taylor M.; Nanduri, Priyaanka; Siebert, Janet C.; Armstrong, Taylor K.; Babu, Sunanda R.; Rewers, Marian J.; Gottlieb, Peter A.; Barker, Jennifer M.; Eisenbarth, George S.

    2010-01-01

    Context: Multiple autoimmune disorders (e.g. Addison’s disease, type 1 diabetes, celiac disease) are associated with HLA-DR3, but it is likely that alleles of additional genes in linkage disequilibrium with HLA-DRB1 contribute to disease. Objective: The objective of the study was to characterize major histocompatability complex (MHC) haplotypes conferring extreme risk for autoimmune Addison’s disease (AD). Design, Setting, and Participants: Eighty-six 21-hydroxylase autoantibody-positive, nonautoimmune polyendocrine syndrome type 1, Caucasian individuals collected from 1992 to 2009 with clinical AD from 68 families (12 multiplex and 56 simplex) were genotyped for HLA-DRB1, HLA-DQB1, MICA, HLA-B, and HLA-A as well as high density MHC single-nucleotide polymorphism (SNP) analysis for 34. Main Outcome Measures: AD and genotype were measured. Result: Ninety-seven percent of the multiplex individuals had both HLA-DR3 and HLA-B8 vs. 60% of simplex AD patients (P = 9.72 × 10−4) and 13% of general population controls (P = 3.00 × 10−19). The genotype DR3/DR4 with B8 was present in 85% of AD multiplex patients, 24% of simplex patients, and 1.5% of control individuals (P = 4.92 × 10−191). The DR3-B8 haplotype of AD patients had HLA-A1 less often (47%) than controls (81%, P = 7.00 × 10−5) and type 1 diabetes patients (73%, P = 1.93 × 10−3). Analysis of 1228 SNPs across the MHC for individuals with AD revealed a shorter conserved haplotype (3.8) with the loss of the extended conserved 3.8.1 haplotype approximately halfway between HLA-B and HLA-A. Conclusion: Extreme risk for AD, especially in multiplex families, is associated with haplotypic DR3 variants, in particular a portion (3.8) but not all of the conserved 3.8.1 haplotype. PMID:20631027

  4. Brahm Prakash, Dr

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1972 Section: Engineering & Technology. Brahm Prakash, Dr Ph.D. (Panjab), FNA 1974-76. Date of birth: 21 August 1912. Date of death: 3 January 1984. Specialization: Metallurgy. YouTube; Twitter; Facebook; Blog ...

  5. Advanced Instrumentation and Control Methods for Small and Medium Reactors with IRIS Demonstration. Final Report. Volume 1

    International Nuclear Information System (INIS)

    Hines, J. Wesley; Upadhyaya, Belle R.; Doster, J. Michael; Edwards, Robert M.; Lewis, Kenneth D.; Turinsky, Paul; Coble, Jamie

    2011-01-01

    on meeting two of the eight needs outlined in the recently published 'Technology Roadmap on Instrumentation, Control, and Human-Machine Interface (ICHMI) to Support DOE Advanced Nuclear Energy Programs' which was created 'to provide a systematic path forward for the integration of new ICHMI technologies in both near-term and future nuclear power plants and the reinvigoration of the U.S. nuclear ICHMI community and capabilities.' The research consortium is led by The University of Tennessee (UT) and is focused on three interrelated topics: Topic 1 (simulator development and measurement sensitivity analysis) is led by Dr. Mike Doster with Dr. Paul Turinsky of North Carolina State University (NCSU). Topic 2 (multivariate autonomous control of modular reactors) is led by Dr. Belle Upadhyaya of the University of Tennessee (UT) and Dr. Robert Edwards of Penn State University (PSU). Topic 3 (monitoring, diagnostics, and prognostics system development) is led by Dr. Wes Hines of UT. Additionally, South Carolina State University (SCSU, Dr. Ken Lewis) participated in this research through summer interns, visiting faculty, and on-campus research projects identified throughout the grant period. Lastly, Westinghouse Science and Technology Center (Dr. Mario Carelli) was a no-cost collaborator and provided design information related to the IRIS demonstration platform and defining needs that may be common to other SMR designs. The results of this research are reported in a six-volume Final Report (including the Executive Summary, Volume 1). Volumes 2 through 6 of the report describe in detail the research and development under the topical areas. This volume serves to introduce the overall NERI-C project and to summarize the key results. Section 2 provides a summary of the significant contributions of this project. A list of all the publications under this project is also given in Section 2. Section 3 provides a brief summary of each of the five volumes (2-6) of the report. The

  6. Department of Reactor Technology annual progress report 1 January - 31 December 1978

    International Nuclear Information System (INIS)

    1979-04-01

    The activities of the department of reactor technology at Risoe during 1978 are described. The work is presented in five chapters: Reactor Engineering, Reactor Physics and Dynamics, Heat Transfer and Hydraulics, The DR 1 Reactor, and Non-Nuclear Activities. A list of the staff and of publications is included. (author)

  7. Dr Luigi Orlando, Dr Sergio Ceccuzzi, Dr. Armando Sbrana, Europa Metalli, Italy, Dr Albert Scherger, Member of KM Europa Metal AG, Osnabr ck, Germany, Prof. Filippo Menzinger, Scientific Attaché, Permanent Mission of Italy in Geneva

    CERN Multimedia

    Patrice Loïez

    2001-01-01

    Photo 01: Dr Lyn Evans and Dr Luigi Orlando Photo 04: L. to r.: Dr Lyn Evans, Dr Luigi Orlando, Prof. Luciano Maiani and Prof. Filippo Menzinger Photo 06: L. to r.: Prof. Philippo Menzinger, Dr Armando Sbrana, Prof. Luciano Maiani, Dr Albert Scherger, Dr Lyn Evans, Dr Luigi Orlando, Dr Sergio Ceccuzzi, visiting the LHC superconducting magnet test hall, SM18

  8. Decommissioning of DR 2. Final report

    Energy Technology Data Exchange (ETDEWEB)

    Strufe, N.

    2009-02-15

    This report describes the work of dismantling and demolishing reactor DR 2, the waste volumes generated, the health physical conditions and the clearance procedures used for removed elements and waste. Since the ultimate goal for the decommissioning project was not clearance of the building, but downgrading the radiological classification of the building with a view to converting it to further nuclear use, this report documents how the lower classification was achieved and the known occurrence of remaining activity. The report emphasises some of the deliberations made and describes the lessons learned through this decommissioning project. The report also intends to contribute towards the technical basis and experience basis for further decommissioning of the nuclear facilities in Denmark. (au)

  9. 105-F and DR Phase 1 Sampling and Analysis Plan

    International Nuclear Information System (INIS)

    Curry, L.R.

    1998-06-01

    This SAP presents the rationale and strategy for characterization of specific rooms within the 105-F and 105-DR reactor buildings. Figures 1-1 and 1-2 identify the rooms that are the subject of this SAP. These rooms are to be decontaminated and demolished as an initial step (Phase 1 ) in the Interim Safe Storage process for these reactors. Section 1.0 presents the background and sites history for the reactor buildings and summarizes the data quality objective process, which provides the logical basis for this SAP. Preliminary surveys indicate that little radiochemical contamination is present. Section 2.0 presents the quality assurance project plan, which includes a project management structure, sampling methods and quality control, and oversight of the sampling process. Section 2.2.1 summarizes the sampling methods, reflecting the radiological and chemical sampling designs presented in Tables 1-17 and 1-18. Section 3.0 presents the Field Sampling Plan for Phase 1. The sampling design is broken into two stages. Stage 1 will verify the list of radioactive constituents of concern and generate the isotopic distribution. The objectives of Stage 2 are to estimate the radionuclide inventories of room debris, quantify chemical contamination, and survey room contents for potential salvage or recycle. Table 3-1 presents the sampling activities to be performed in Stage 1. Tables 1-17 and 1-18 identify samples to be collected in Stage 2. Stage 2 will consist primarily of survey data collection, with fixed laboratory samples to be collected in areas showing visible stains. Quality control sampling requirements are presented in Table 3-2

  10. Department of Reactor Technology annual progress report 1 January -31 December 1977

    International Nuclear Information System (INIS)

    1978-04-01

    The work of the Department of Reactor Technology within the following fields is described: reactor engineering, reactor operation, structural reliability, system reliability, reactor physics, fuel management, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, experimental activation measurements and neutron radiography at the DR 1 reactor, underground storage of gas, solar heating and underground heat storage, wind power. (author)

  11. User's Manual for FEMOM3DR. Version 1.0

    Science.gov (United States)

    Reddy, C. J.

    1998-01-01

    FEMoM3DR is a computer code written in FORTRAN 77 to compute radiation characteristics of antennas on 3D body using combined Finite Element Method (FEM)/Method of Moments (MoM) technique. The code is written to handle different feeding structures like coaxial line, rectangular waveguide, and circular waveguide. This code uses the tetrahedral elements, with vector edge basis functions for FEM and triangular elements with roof-top basis functions for MoM. By virtue of FEM, this code can handle any arbitrary shaped three dimensional bodies with inhomogeneous lossy materials; and due to MoM the computational domain can be terminated in any arbitrary shape. The User's Manual is written to make the user acquainted with the operation of the code. The user is assumed to be familiar with the FORTRAN 77 language and the operating environment of the computers on which the code is intended to run.

  12. Dræb, dræb, dræb! Nej ... liiiige et øjeblik: De machiavelliske følelser i Game of Thrones

    DEFF Research Database (Denmark)

    Schubart, Rikke

    2013-01-01

    Blogindlæg om Machiavelliske følelser i HBO tv-serien Game of Thrones: "Dræb, dræb, dræb! Nej ... liiiige et øjeblik: De machiavelliske følelser i Game of Thrones"......Blogindlæg om Machiavelliske følelser i HBO tv-serien Game of Thrones: "Dræb, dræb, dræb! Nej ... liiiige et øjeblik: De machiavelliske følelser i Game of Thrones"...

  13. Integral test of JENDL-3.3 for fast reactors

    International Nuclear Information System (INIS)

    Chiba, Gou

    2003-01-01

    An integral test of JENDL-3.3 was performed for fast reactors. Various types of fast reactors were analyzed. Calculation values of the nuclear characteristics were greatly especially affected by the revisions of the cross sections of U-235 capture and elastic scattering reactions. The C/E values were improved for ZPPR cross where plutonium is mainly fueled, but not for BFS cores where uranium is mainly fueled. (author)

  14. Use of research reactors in Soviet atomic centres

    International Nuclear Information System (INIS)

    1964-01-01

    The manner of controlling and directing research reactors in the USSR was described in October at the IAEA seminar for atomic energy administrators by Dr. U. V. Archangelski, Department Chief, State Committee for Utilization of Atomic Energy, USSR. He also enumerated the research reactors in operation. In addition to the portions of the paper which are quoted below, he gave details of the scientific work being carried out in these reactors.

  15. ROLE OF CD95 AND DR3 RECEPTORS IN NA VE T-LYMPHOCYTES APOPTOSIS IN CHILDREN WITH INFECTIOUS MONONUCLEOSIS DURING CONVALESCENCE

    Directory of Open Access Journals (Sweden)

    E. N. Filatova

    2017-01-01

    Full Text Available Infectious mononucleosis is a widespread disease caused by certain members of Herpesviridae family. Acute infectious mononucleosis develops predominantly in children and is accompanied by an increase of the number of circulating naive CD4+ and naive CD8+ T-lymphocytes in the peripheral blood. The normalization of immunological parameters is achieved within 4–6 months after recovery and that is an indicator of a proper functioning of the immune system. CD95 and DR3 death receptors are involved in the initiation of apoptosis of naive T-lymphocytes in healthy people and in patients with infectious mononucleosis. The aim of the study was to evaluate the ability of CD95 and DR3 receptors to initiate apoptosis of naive CD4+ and naive CD8+ T-lymphocytes in children with infectious mononucleosis during convalescence. The material for the study was the samples of the peripheral blood of children who previously had infectious mononucleosis. The blood sampling was carried out again after 4–6 months after the disease. At the time of the study, children did not display clinical and laboratory signs of infectious mononucleosis. Same children who were examined earlier in the period of the development of acute infectious mononucleosis, as well as relatively healthy children were used as the comparison groups. Isolation of naive CD4+ and naive CD8+ T-lymphocytes was performed by negative magnetic immunoseparation. For specific stimulation of CD95 and DR3 receptors monoclonal antibodies were used. The level of apoptosis and expression of death receptors were evaluated by flow cytometry. Freshly isolated cells were analyzed, as well as cells cultured with the addition of appropriate monoclonal antibodies. It was shown that the recovery period was accompanied by increased apoptosis of freshly isolated naive CD4+ and naive CD8+ T-lymphocytes compared with the acute phase of infectious mononucleosis. Thus in both populations of naive T-cells showed an increase of

  16. The sedimentology and uranium mineralisation of the DR-3 deposit, Laingsburg district

    International Nuclear Information System (INIS)

    Le Roux, J.P.

    1982-08-01

    As part of its research program in the Karoo, NUCOR carried out a sedimentological investigation of the DR-3 deposit, discovered by JCI. It is located on the farm Drie Vaderlandsche Rietvalleyen, 40 km north of Laingsburg, in an unnamed sandstone package of the Abrahamskraal Formation. The orebody lies in an area affected by southward-dipping monoclines, which possibly originated because of basement faults during subsidence of the Karoo trough. These monoclines may be have locally altered the courses of rivers flowing from the source areas to the south-west. The S1-sandstone which hosts the uranium was probably deposited in a braided river environment of the Donjek type. The vector mean azimuth is towards 075 degrees for S1 and 062 degrees for the studied sequence as a whole, but towards the east there is a marked change in the palaeocurrent direction. On a more regional scale, preliminary investigations indicate the braided river system was at least 5 km wide. Uranium mineralisation on DR-3 is concentrated within a major east-west-trending channel, with the best-developed ore at the junctions of this channel with tributaries from the south. This is probably due to plant material settling out in the areas of reduced current velocities where opposing streams meet

  17. Chandrasekaran, Dr Chidambara

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1945 Section: Mathematical Sciences. Chandrasekaran, Dr Chidambara Ph.D. (London) 1962-64. Date of birth: 30 October 1911. Date of death: 4 January 2000. Specialization: Statistics, Public Health and Demography Last known address: 'Sri Kripa', 79/3, Benson Cross Road, Bengaluru 560 046.

  18. Jameel, Dr Shahid

    Indian Academy of Sciences (India)

    Jameel, Dr Shahid Ph.D. (Washington State Univ.), FNASc, FNA. Date of birth: 8 August 1957. Specialization: Molecular Biology and Molecular Virology Address: Chief Executive Officer, The Wellcome Trust/DBT India Alliance, 8-2-684/3/K/19, Kaushik Society, Road NO. 12, Banjara Hills, Hyderabad 500 034, A.P.. Contact:

  19. Mapping the radiation fields at a research reactor

    International Nuclear Information System (INIS)

    Soegaard-Hansen, Jens; Warming, Lisbeth

    1999-01-01

    The DR 3 reactor at Risoe National Laboratory is a multipurpose research reactor. It has the status of a Large European Beam facility therefor its neutron scattering spectrometers are used by many visiting scientists. As a supplement to the routine health physics monitoring programmes a special survey has been made to get more detailed information of the radiation levels in the hall and of the most important sources of the radiation. The special survey consisted of three sorts of measurements: an extra set of thermoluminescence dosimeters, a set of continuous measurements of the dose rate at selected places and spot measurements with handheld instruments around the spectrometers. Some of the results from the survey are presented. (au)

  20. Department of Reactor Technology: annual progress report 1 January - 31 December 1976

    International Nuclear Information System (INIS)

    1977-06-01

    The work of the Department of Reactor Technology within the following fields is described: reactor engineering, structural reliability, system reliability, radiation fiels in nuclear power plants, reactor physics, fuel management, fission product decay analysis, steady-state thermo-hydraulics, reactor accident analysis for LOCA and ECC, containment analysis, experimental heat transfer, reactor core dynamics and power plant simulators, control rod ejection accident analysis, economic studies for power plants, experimental activation measurements and neutron radiography at the DR 1 reactor. (author)

  1. Budhani, Dr Ramesh Chandra

    Indian Academy of Sciences (India)

    Budhani, Dr Ramesh Chandra Ph.D. (IIT, Delhi), FNASc, FNA. Date of birth: 3 February 1955. Specialization: Renewable Energy, Nanoscale Systems, Experimental Condensed Matter Physics, Superconductivity and Magnetism Address: Department of Physics, Lasers & Photonics, Indian Institute of Technology, Kanpur 208 ...

  2. Association of differentiated thyroid carcinoma with HLA-DR7

    International Nuclear Information System (INIS)

    Sridama, V.; Hara, Y.; Fauchet, R.; DeGroot, L.J.

    1985-01-01

    Seventy-four American white thyroid cancer patients were typed for HLA-A, B, and DR antigens. A significant increase in HLA-DR7 was found in the nonradiation-associated thyroid cancer patients (42.5%, 20/47 cases), compared to 22.8% of 979 normal controls. The association is stronger in the follicular and mixed papillary-follicular subgroup (52.0%, 13/25 cases, P corrected less than 0.01). The occurrence of various malignancies in family members was found in 57.9% of HLA-DR7 positive patients, versus 20% of HLA-DR7 negative patients, in a retrospective record review. Although the frequency of HLA-DR7 was not increased in the radiation-associated thyroid cancer patients (22.2%, 6/27 cases), the interval from the irradiation date to the onset date of thyroid cancer was shorter in HLA-DR7 positive cases (17.3 +/- 6.2 years) than in HLA-DR7 negative patients (29.4 +/- 11.5 years). This data suggest that HLA-DR7 is associated with and may influence development of thyroid cancer

  3. Dynamics of TRIGA-3 Salazar Reactor.; Dinamica del Reactor TRIGA Mark III del Centro Nuclear de Mexico.

    Energy Technology Data Exchange (ETDEWEB)

    Gallardo S, L F

    1991-12-31

    The theoretical study of temporal behavior of a nuclear reactor is of great importance, since it allows to know, in advance, the conditions to which a reactor is going to be submitted. The reliability of two computer codes (AIREK-JEN and PLANKIN) designed to reproduce the temporal behavior of nuclear reactors, generally power reactors, when they are applied to reproduce the dynamic behavior of TRIGA-3 Salazar Reactor is analyzed. In the first chapters, the fundamental equations that solve this computer codes are deduced, and also the main characteristics of TRIGA-3 Salazar Reactor and the necessary data to run the programs are presented; later the results obtained with the computer codes and the experimental results reported in the operational logbook of the reactor are compared, with the result that such computer codes are applicable to the temporal study of TRIGA-3 Salazar Reactor. (Author).

  4. 3D CAD model of the subcritical nuclear reactor of IPN; Modelo CAD 3D del reactor nuclear subcritico del IPN

    Energy Technology Data Exchange (ETDEWEB)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A. [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico); Ibarra R, G.; Del Valle G, E.; Sanchez R, A., E-mail: narehc@hotmail.com [IPN, Escuela Superior de Fisica y Matematicas, Av. IPN, Edif. 9, Unidad Profesional Adolfo Lopez Mateos, San Pedro Zacatenco, 07738 Ciudad de Mexico (Mexico)

    2016-09-15

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  5. Direct harvesting of Helium-3 (3He) from heavy water nuclear reactors

    International Nuclear Information System (INIS)

    Bentoumi, G.; Didsbury, R.; Jonkmans, G.; Rodrigo, L.; Sur, B.

    2013-01-01

    The thermal neutron activation of deuterium inside a heavy-water-moderated or -cooled nuclear reactor produces a build-up of tritium in the heavy water. The in situ decay of tritium can, for certain reactor types and operating conditions, produce potentially useable amounts of 3 He, which can be directly extracted via the heavy-water cover gas without first separating, collecting and storing tritium outside the reactor. It is estimated that the amount of 3 He available for recovery from the moderator cover gas of a 700 MWe class Pressurized Heavy Water Reactor (PHWR) ranges from 0.1 to 0.7 m 3 (STP) per annum, varying with the tritium activity buildup in the moderator. The harvesting of 3 He would generate approximately 12.7 m 3 (STP) of 3 He, worth more than $30M at current market rates, over a typical 25-year operating cycle of the PHWR. This paper discusses the production of 3 He in the moderator of a PHWR and its extraction from the 4 He moderator cover gas system using conventional methods. (author)

  6. Dr. Mainte. Integrated simulator of maintenance optimization of LWRs

    International Nuclear Information System (INIS)

    Isobe, Yoshihiro; Sagisaka, Mitsuyuki; Etoh, Junji; Matsunaga, Takashi; Kosaka, Toru; Matsumoto, Satoshi; Yoshimura, Shinobu

    2014-01-01

    Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) has been developed based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for representative components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability and economic efficiency, environmental impact and social acceptance. For the further improvement of the safety and availability, the effect of human error and its reduction on the optimization of plant maintenance activities and approaches of reducing it have been studied. (author)

  7. D-3He fuel cycles for neutron lean reactors

    International Nuclear Information System (INIS)

    Kernbichler, W.; Miley, G.H.; Heindler, M.

    1989-01-01

    The intrinsic potential of D-3He as a reactor fuel is investigated for a large range of 3He to D density ratios. A steady-state zero-dimensional reactor model is developed in which much care is attributed to a proper treatment of fast fusion products. Useful ranges of reactor parameters as well as temperature-density windows for driven and ignited operation are identified. Various figures of merit are calculated, such as power densities, net power production, neutron production, tritium load and radiative power. These results suggest several optimistic conclusions about the performance of D-3He as a reactor fuel

  8. Prediction of the stability of BWR reactors during the start-up process; Prediccion de la estabilidad de reactores BWR durante el proceso de arranque

    Energy Technology Data Exchange (ETDEWEB)

    Ruiz E, J.A.; Castillo D, R. [ININ, Km. 36.5 Carretera Mexico-Toluca, 52045 Salazar, Estado de Mexico (Mexico); Blazquez M, J.B. [Centro de Investigaciones Energetics, Medioambientales y Tecnologicas, Av Complutense 22, 28040 Madrid (Spain)

    2004-07-01

    The Boiling Water Reactors (BWR) are susceptible of uncertainties of power when they are operated to low flows of coolant (W) and high powers (P), being presented this situation mainly in the start-up process. The start-up process could be made but sure if the operator knew the value of the stability index Decay reason (Dr) before going up power and therefore to guarantee the stability. The power and the flow are constantly measures, the index Dr could also be considered its value in real time. The index Dr depends on the power, flow and many other values, such as, the distribution of the flow axial and radial neutronic, the temperature of the feeding water, the fraction of holes and other thermohydraulic and nuclear parameters. A simple relationship of Dr is derived leaving of the pattern reduced of March-Leuba, where three independent variables are had that are the power, the flow and a parameter that it contains the rest of the phenomenology, that is to say all the other quantities that affect the value of Dr. This relationship developed work presently and verified its prediction with data of start-up of commercial reactors could be used for the design of a practical procedure practice of start-up, what would support to the operator to prevent this type of events of uncertainty. (Author)

  9. Chitnis, Dr Chetan Eknath

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2009 Section: Medicine. Chitnis, Dr Chetan Eknath Ph.D. (UC, Berkeley), FNA. Date of birth: 3 April 1961. Specialization: Molecular Parasitology, Vaccine Development for Malaria and Molecular & Cell Biology Address: Head, Malaria Parasite Biology & Vaccine, Institut Pasteur, 28, ...

  10. Sharma, Dr Surendra Kumar

    Indian Academy of Sciences (India)

    Elected: 2010 Section: Medicine. Sharma, Dr Surendra Kumar Ph.D. (AIIMS), MD (PGIMER, Chandigarh), FNASc, FNA. Date of birth: 22 February 1951. Specialization: Environmental Medicine, Infectious Diseases, Internal Medicine, Pulmonary & Critical Care and Sleep Medicine Address: B-5/3, B Block, Sector 13, RK ...

  11. Stellar Stream Candidates in the Solar Neighborhood Found in the LAMOST DR3 and TGAS

    Science.gov (United States)

    Liang, X. L.; Zhao, J. K.; Oswalt, T. D.; Chen, Y. Q.; Zhang, L.; Zhao, G.

    2017-08-01

    We have cross-matched the LAMOST DR3 with the Gaia DR1 TGAS catalogs and obtained a sample of 166,827 stars with reliable kinematics. A technique based on the wavelet transform was applied to detect significant overdensities in velocity space among five subsamples divided by spatial position. In total, 16 significant overdensities of stars with very similar kinematics were identified. Among these, four are new stream candidates and the rest are previously known groups. Both the U-V velocity and metallicity distributions of the local sample show a clear gap between the Hercules structure and the Hyades-Pleiades structure. The U-V positions of these peaks shift with the spatial position. Following a description of our analysis, we speculate on possible origins of our stream candidates.

  12. Galande, Dr Sanjeev

    Indian Academy of Sciences (India)

    Elected: 2010 Section: General Biology. Galande, Dr Sanjeev Ph.D. (IISc). Date of birth: 20 September 1967. Specialization: Epigenetics, Chromatin Biology, Gene Regulation, Genomics and Proteomics Address: Centre for Excellence in Epigenetics, Indian Institute of Science Education, & Research, Dr Homi Bhabha Road, ...

  13. Ocular myasthenia gravis induced by human acetylcholine receptor ϵ subunit immunization in HLA DR3 transgenic mice.

    Science.gov (United States)

    Wu, Xiaorong; Tuzun, Erdem; Saini, Shamsher S; Wang, Jun; Li, Jing; Aguilera-Aguirre, Leopoldo; Huda, Ruksana; Christadoss, Premkumar

    2015-12-01

    Extraocular muscles (EOM) are preferentially involved in myasthenia gravis (MG) and acetylcholine receptor (AChR) antibody positive MG patients may occasionally present with isolated ocular symptoms. Although experimental autoimmune myasthenia gravis (EAMG) induced by whole AChR immunization closely mimics clinical and immunopathological aspects of MG, EOM are usually not affected. We have previously developed an EAMG model, which imitates EOM symptoms of MG by immunization of human leukocyte antigen (HLA) transgenic mice with α or γ-subunits of human AChR (H-AChR). To investigate the significance of the ϵ-subunit in ocular MG, we immunized HLA-DR3 and HLA-DQ8 transgenic mice with recombinant H-AChR ϵ-subunit expressed in Escherichia coli. HLA-DR3 transgenic mice showed significantly higher clinical ocular and generalized MG severity scores and lower grip strength values than HLA-DQ8 mice. H-AChR ϵ-subunit-immunized HLA-DR3 transgenic mice had higher serum anti-AChR antibody (IgG, IgG1, IgG2b, IgG2c and IgM) levels, neuromuscular junction IgG and complement deposit percentages than ϵ-subunit-immunized HLA-DQ8 transgenic mice. Control mice immunized with E. coli extract or complete Freund adjuvant (CFA) did not show clinical and immunopathological features of ocular and generalized EAMG. Lymph node cells of ϵ-subunit-immunized HLA-DR3 mice showed significantly higher proliferative responses than those of ϵ-subunit-immunized HLA-DQ8 mice, crude E. coli extract-immunized and CFA-immunized transgenic mice. Our results indicate that the human AChR ϵ-subunit is capable of inducing myasthenic muscle weakness. Diversity of the autoimmune responses displayed by mice expressing different HLA class II molecules suggests that the interplay between HLA class II alleles and AChR subunits might have a profound impact on the clinical course of MG. Copyright © 2015 European Federation of Immunological Societies. Published by Elsevier B.V. All rights reserved.

  14. Gaia DR2 documentation

    Science.gov (United States)

    van Leeuwen, F.; de Bruijne, J. H. J.; Arenou, F.; Bakker, J.; Blomme, R.; Busso, G.; Cacciari, C.; Castañeda, J.; Cellino, A.; Clotet, M.; Comoretto, G.; Eyer, L.; González-Núñez, J.; Guy, L.; Hambly, N.; Hobbs, D.; van Leeuwen, M.; Luri, X.; Manteiga, M.; Pourbaix, D.; Roegiers, T.; Salgado, J.; Sartoretti, P.; Tanga, P.; Ulla, A.; Utrilla Molina, E.; Abreu, A.; Altmann, M.; Andrae, R.; Antoja, T.; Audard, M.; Babusiaux, C.; Bailer-Jones, C. A. L.; Barache, C.; Bastian, U.; Beck, M.; Berthier, J.; Bianchi, L.; Biermann, M.; Bombrun, A.; Bossini, D.; Breddels, M.; Brown, A. G. A.; Busonero, D.; Butkevich, A.; Cantat-Gaudin, T.; Carrasco, J. M.; Cheek, N.; Clementini, G.; Creevey, O.; Crowley, C.; David, M.; Davidson, M.; De Angeli, F.; De Ridder, J.; Delbò, M.; Dell'Oro, A.; Diakité, S.; Distefano, E.; Drimmel, R.; Durán, J.; Evans, D. W.; Fabricius, C.; Fabrizio, M.; Fernández-Hernández, J.; Findeisen, K.; Fleitas, J.; Fouesneau, M.; Galluccio, L.; Gracia-Abril, G.; Guerra, R.; Gutiérrez-Sánchez, R.; Helmi, A.; Hernandez, J.; Holl, B.; Hutton, A.; Jean-Antoine-Piccolo, A.; Jevardat de Fombelle, G.; Joliet, E.; Jordi, C.; Juhász, Á.; Klioner, S.; Löffler, W.; Lammers, U.; Lanzafame, A.; Lebzelter, T.; Leclerc, N.; Lecoeur-Taïbi, I.; Lindegren, L.; Marinoni, S.; Marrese, P. M.; Mary, N.; Massari, D.; Messineo, R.; Michalik, D.; Mignard, F.; Molinaro, R.; Molnár, L.; Montegriffo, P.; Mora, A.; Mowlavi, N.; Muinonen, K.; Muraveva, T.; Nienartowicz, K.; Ordenovic, C.; Pancino, E.; Panem, C.; Pauwels, T.; Petit, J.; Plachy, E.; Portell, J.; Racero, E.; Regibo, S.; Reylé, C.; Rimoldini, L.; Ripepi, V.; Riva, A.; Robichon, N.; Robin, A.; Roelens, M.; Romero-Gómez, M.; Sarro, L.; Seabroke, G.; Segovia, J. C.; Siddiqui, H.; Smart, R.; Smith, K.; Sordo, R.; Soria, S.; Spoto, F.; Stephenson, C.; Turon, C.; Vallenari, A.; Veljanoski, J.; Voutsinas, S.

    2018-04-01

    The second Gaia data release, Gaia DR2, encompasses astrometry, photometry, radial velocities, astrophysical parameters (stellar effective temperature, extinction, reddening, radius, and luminosity), and variability information plus astrometry and photometry for a sample of pre-selected bodies in the solar system. The data collected during the first 22 months of the nominal, five-year mission have been processed by the Gaia Data Processing and Analysis Consortium (DPAC), resulting into this second data release. A summary of the release properties is provided in Gaia Collaboration et al. (2018b). The overall scientific validation of the data is described in Arenou et al. (2018). Background information on the mission and the spacecraft can be found in Gaia Collaboration et al. (2016), with a more detailed presentation of the Radial Velocity Spectrometer (RVS) in Cropper et al. (2018). In addition, Gaia DR2 is accompanied by various, dedicated papers that describe the processing and validation of the various data products. Four more Gaia Collaboration papers present a glimpse of the scientific richness of the data. In addition to this set of refereed publications, this documentation provides a detailed, complete overview of the processing and validation of the Gaia DR2 data. Gaia data, from both Gaia DR1 and Gaia DR2, can be retrieved from the Gaia archive, which is accessible from https://archives.esac.esa.int/gaia. The archive also provides various tutorials on data access and data queries plus an integrated data model (i.e., description of the various fields in the data tables). In addition, Luri et al. (2018) provide concrete advice on how to deal with Gaia astrometry, with recommendations on how best to estimate distances from parallaxes. The Gaia archive features an enhanced visualisation service which can be used for quick initial explorations of the entire Gaia DR2 data set. Pre-computed cross matches between Gaia DR2 and a selected set of large surveys are

  15. Conceptual design of D-3He FRC reactor 'ARTEMIS'

    International Nuclear Information System (INIS)

    Momota, H.; Ishida, A.; Kohzaki, Y.

    1991-07-01

    A comprehensive design study of the D- 3 He fueled field-reversed configuration (FRC) reactor 'ARTEMIS' is carried out for the purpose of proving its attractive characteristics and clarifying the critical issues for a commercial fusion reactor. The FRC burning plasma is stabilized and sustained in a steady equilibrium by means of a preferential trapping of D- 3 He fusion-produced energetic protons. A novel direct energy converter for 15MeV protons is also presented. On the bases of a consistent scenario of the fusion plasma production and simple engineering, a compact and simple reactor concept is presented. The design of the D- 3 He FRC power plant definitely offers the most attractive prospect for energy development. It is environmentally acceptable in view of radio-activity and fuel resources; and the estimated cost of electricity is low compared to a light water reactor. Critical issues concerning physics or engineering for the development of the D- 3 He FRC reactor are clarified. (author)

  16. Modulation of TRAIL resistance in colon carcinoma cells: Different contributions of DR4 and DR5

    International Nuclear Information System (INIS)

    Geelen, Caroline MM van; Pennarun, Bodvael; Le, Phuong TK; Vries, Elisabeth GE de; Jong, Steven de

    2011-01-01

    rhTRAIL is a therapeutic agent, derived from the TRAIL cytokine, which induces apoptosis in cancer cells by activating the membrane death receptors 4 and 5 (DR4 and DR5). Here, we investigated each receptor's contribution to rhTRAIL sensitivity and rhTRAIL resistance. We assessed whether agonistic DR4 or DR5 antibodies could be used to circumvent rhTRAIL resistance, alone or in combination with various chemotherapies. Our study was performed in an isogenic model comprised of the SW948 human colon carcinoma cell line and its rhTRAIL resistant sub-line SW948-TR. Effects of rhTRAIL and agonistic DR4/DR5 antibodies on cell viability were measured using MTT assays and identification of morphological changes characteristic of apoptosis, after acridine orange staining. Sensitivity to the different death receptor ligands was stimulated using pretreatment with the cytokine IFN-gamma and the proteasome inhibitor MG-132. To investigate the mechanisms underlying the changes in rhTRAIL sensitivity, alterations in expression levels of targets of interest were measured by Western blot analysis. Co-immunoprecipitation was used to determine the composition of the death-inducing signalling complex at the cell membrane. SW948 cells were sensitive to all three of the DR-targeting agents tested, although the agonistic DR5 antibody induced only weak caspase 8 cleavage and limited apoptosis. Surprisingly, agonistic DR4 and DR5 antibodies induced equivalent DISC formation and caspase 8 cleavage at the level of their individual receptors, suggesting impairment of further caspase 8 processing upon DR5 stimulation. SW948-TR cells were cross-resistant to all DR-targeting agents as a result of decreased caspase 8 expression levels. Caspase 8 protein expression was restored by MG-132 and IFN-gamma pretreatment, which also re-established sensitivity to rhTRAIL and agonistic DR4 antibody in SW948-TR. Surprisingly, MG-132 but not IFN-gamma could also increase DR5-mediated apoptosis in SW948

  17. Modulation of TRAIL resistance in colon carcinoma cells: Different contributions of DR4 and DR5

    Directory of Open Access Journals (Sweden)

    de Vries Elisabeth GE

    2011-01-01

    Full Text Available Abstract Background rhTRAIL is a therapeutic agent, derived from the TRAIL cytokine, which induces apoptosis in cancer cells by activating the membrane death receptors 4 and 5 (DR4 and DR5. Here, we investigated each receptor's contribution to rhTRAIL sensitivity and rhTRAIL resistance. We assessed whether agonistic DR4 or DR5 antibodies could be used to circumvent rhTRAIL resistance, alone or in combination with various chemotherapies. Methods Our study was performed in an isogenic model comprised of the SW948 human colon carcinoma cell line and its rhTRAIL resistant sub-line SW948-TR. Effects of rhTRAIL and agonistic DR4/DR5 antibodies on cell viability were measured using MTT assays and identification of morphological changes characteristic of apoptosis, after acridine orange staining. Sensitivity to the different death receptor ligands was stimulated using pretreatment with the cytokine IFN-gamma and the proteasome inhibitor MG-132. To investigate the mechanisms underlying the changes in rhTRAIL sensitivity, alterations in expression levels of targets of interest were measured by Western blot analysis. Co-immunoprecipitation was used to determine the composition of the death-inducing signalling complex at the cell membrane. Results SW948 cells were sensitive to all three of the DR-targeting agents tested, although the agonistic DR5 antibody induced only weak caspase 8 cleavage and limited apoptosis. Surprisingly, agonistic DR4 and DR5 antibodies induced equivalent DISC formation and caspase 8 cleavage at the level of their individual receptors, suggesting impairment of further caspase 8 processing upon DR5 stimulation. SW948-TR cells were cross-resistant to all DR-targeting agents as a result of decreased caspase 8 expression levels. Caspase 8 protein expression was restored by MG-132 and IFN-gamma pretreatment, which also re-established sensitivity to rhTRAIL and agonistic DR4 antibody in SW948-TR. Surprisingly, MG-132 but not IFN

  18. Dr. Wernher von Braun and Dr. Ernst Stuhlinger Sign Citizenship Certificates

    Science.gov (United States)

    1955-01-01

    The members of the Peenemuende team and their family members were awarded the United States citizenship on April 14, 1955. Pictured here is Dr. Ernst Stuhlinger (middle) and Dr. Wernher von Braun signing U.S. citizenship certificates. Martin Schilling is at left.

  19. Decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors

    International Nuclear Information System (INIS)

    1994-08-01

    The meeting was convened by the International Atomic Energy Agency on the recommendation of the IAEA's International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Poland, the Russian Federation, Switzerland, the United Kingdom and the United States of America. The meeting was chaired by Prof. Dr. K. Kugeler and Prof. Dr. E. Hicken, Directors of the Institute for Safety Research Technology of the KFA Research Center, and covered the following: Design and licensing requirements for gas cooled reactors; concepts for decay heat removal in modern gas cooled reactors; analytical methods for predictions of thermal response, accuracy of predictions; experimental data for validation of predictive methods - operational experience from gas cooled reactors and experimental data from test facilities. Refs, figs and tabs

  20. Basu, Dr Sandip Kumar

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1992 Section: General Biology. Basu, Dr Sandip Kumar Ph.D. (Calcutta), FNASc, FNA, FTWAS Council Service: 1995-97. Date of birth: 1 January 1944. Specialization: Cell Biology, Molecular Biology and Microbial Genetics Address: FD-426, Sector 3, Bidhan Nagar, Kolkata 700 106, W.B.. Contact:

  1. Association between HLA-DR antigens and rheumatoid arthritis in Arabs.

    OpenAIRE

    Sattar, M A; al-Saffar, M; Guindi, R T; Sugathan, T N; Behbehani, K

    1990-01-01

    Eighty five Arab patients with classical and definite rheumatoid arthritis were typed to determine the prevalence of HLA A, B, C, and DR antigens. A significant increase in the prevalence of HLA-A10, B8, B21, and DR3 was found in comparison with a control population matched for age and sex. HLA-DR5 was significantly decreased in the patient group. The classical association of HLA-DR4 with rheumatoid arthritis could not be confirmed in the Arab patients resident in Kuwait, supporting reported ...

  2. Dr Math at your service

    CSIR Research Space (South Africa)

    Butgereit, L

    2012-10-01

    Full Text Available In this presentation the author explains how the Dr Math service works; how tutors are recruited to act as Dr Math; and how school pupils can reach Dr Math for help with their mathematics homework....

  3. Draft environmental impact statement siting, construction, and operation of New Production Reactor capacity. Volume 4, Appendices D-R

    Energy Technology Data Exchange (ETDEWEB)

    None

    1991-04-01

    This Environmental Impact Statement (EIS) assesses the potential environmental impacts, both on a broad programmatic level and on a project-specific level, concerning a proposed action to provide new tritium production capacity to meet the nation`s nuclear defense requirements well into the 21st century. A capacity equivalent to that of about a 3,000-megawatt (thermal) heavy-water reactor was assumed as a reference basis for analysis in this EIS; this is the approximate capacity of the existing production reactors at DOE`s Savannah River Site near Aiken, South Carolina. The EIS programmatic alternatives address Departmental decisions to be made on whether to build new production facilities, whether to build one or more complexes, what size production capacity to provide, and when to provide this capacity. Project-specific impacts for siting, constructing, and operating new production reactor capacity are assessed for three alternative sites: the Hanford Site near Richland, Washington; the Idaho National Engineering Laboratory near Idaho Falls, Idaho; and the Savannah River Site. For each site, the impacts of three reactor technologies (and supporting facilities) are assessed: a heavy-water reactor, a light-water reactor, and a modular high-temperature gas-cooled reactor. Impacts of the no-action alternative also are assessed. The EIS evaluates impacts related to air quality; noise levels; surface water, groundwater, and wetlands; land use; recreation; visual environment; biotic resources; historical, archaeological, and cultural resources; socioeconomics; transportation; waste management; and human health and safety. The EIS describes in detail the potential radioactive releases from new production reactors and support facilities and assesses the potential doses to workers and the general public. This volume contains 15 appendices.

  4. Removal in a lump of JRR-3 nuclear reactor

    International Nuclear Information System (INIS)

    Ohnishi, Nobuaki; Suzuki, Masanori; Nagase, Tetsuo; Watanabe, Morinari.

    1989-01-01

    The research reactor JRR-3 in Japan Atomic Energy Research Institute is called 'Home made No.1 reactor' as all except fuel and heavy water as the moderator and coolant were manufactured in Japan. The JRR-3 attained the criticality in 1962, and the cumulative time of operation reached 47135.5 hours, and the cumulative power output reached 419073.5 MWh. It was stopped in 1983. During the period, it was utilized for beam experiment, irradiation of fuel and materials, RI production and others. In order to cope with the expansion of utilization and the advance of utilizing technology of the research reactor, the reconstruction works are in progress, and the criticality of the reconstructed reactor is expected in 1990. On the site where the old reactor is removed, the reactor of different type is installed, and the first large cold neutron source is equipped. In this report, as to the removal of the old reactor proper, the method of working and the results are described. Considering the period of working, the cost and the management of the removed reactor, in the case of the JRR-3, the method of carrying it out in a lump was adopted as the optimum removal method. The plan, procedure and results of the removal working are reported. (K.I.)

  5. 3D simulation of CANDU reactor regulating system

    International Nuclear Information System (INIS)

    Venescu, B.; Zevedei, D.; Jurian, M.

    2013-01-01

    Present paper shows the evaluation of the performance of the 3-D modal synthesis based reactor kinetic model in a closed-loop environment in a MATLAB/SIMULINK based Reactor Regulating System (RRS) simulation platform. A notable advantage of the 3-D model is the level of details that it can reveal as compared to the coupled point kinetic model. Using the developed RRS simulation platform, the reactor internal behaviours can be revealed during load-following tests. The test results are also benchmarked against measurements from an existing (CANDU) power plant. It can be concluded that the 3-D reactor model produces more realistic view of the core neutron flux distribution, which is closer to the real plant measurements than that from a coupled point kinetic model. It is also shown that, through a vectorization process, the computational load of the 3-D model is comparable with that of the 14-zone coupled point kinetic model. Furthermore, the developed Graphical User Interface (GUI) software package for RRS implementation represents a user friendly and independent application environment for education training and industrial utilizations. (authors)

  6. Analyses for MARIA Research Reactor with RELAP/MOD3 code

    International Nuclear Information System (INIS)

    Szczurek, J.; Czerski, P.

    2004-01-01

    This paper deals with the application of the RELAP5/MOD3 code to the transient analyses for MARIA research reactor. Poland's MARIA Research Reactor is water and beryllium moderated, water-cooled reactor of a pool type with pressurized fuel channels containing concentric multi-tube assemblies of highly enriched uranium clad in aluminium. The RELAP5/MOD3 input data model includes the whole primary cooling circuit of the MARIA reactor. The model was qualified against the reactor data at steady state conditions and additionally against the existing reliable experimental data for a transient initiated by the reactor scram. The RELAP transient simulation was performed for loss of forced flow accidents including two scenarios with protected and unprotected (no scram) reactor core. Calculations allow estimating time margin for reactor scram initiation and reactivity feedbacks contribution to the results. (author)

  7. Drømmejobbet

    DEFF Research Database (Denmark)

    Harrebye, Silas

    2012-01-01

    Medarbejdere vil i fremtiden også kunne arbejde, mens de sover. Virksomheder tilbyder snart deres ansatte interne kurser i ‘lucid dreaming’. Disse giver mulighed for, at man i sine drømme bliver bevidst om, at man drømmer og således kan manipulere dem. Det skal nu udnyttes. Management...

  8. David, Dr Joy Caesarina

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1982 Section: Medicine. David, Dr Joy Caesarina M.B.B.S., M.S. (Madras). Date of birth: 3 May 1927. Date of death: 20 April 2004. Specialization: Neuropharmacology Last known address: 292, 4th Main, 1st Block, Koramangala, Bengaluru 560 034. YouTube; Twitter; Facebook ...

  9. Completion of reconstruction for Japan Research Reactor No.3

    International Nuclear Information System (INIS)

    Kakefuda, K.; Tani, M.; Isshiki, M.

    1992-01-01

    The works of the reconstruction for the Japan Research Reactor No.3 (JRR-3) started in 1985 and initial criticality of the new reactor achieved in March, 1990. After commissioning test, the new JRR-3 has been operated some operational cycles since November, 1990. This paper presents outline of the removal work on the old JRR-3 and the new JRR-3. (author)

  10. Nuclear Reactor Physics

    Science.gov (United States)

    Stacey, Weston M.

    2001-02-01

    An authoritative textbook and up-to-date professional's guide to basic and advanced principles and practices Nuclear reactors now account for a significant portion of the electrical power generated worldwide. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. Nuclear reactor physics is the core discipline of nuclear engineering, and as the first comprehensive textbook and reference on basic and advanced nuclear reactor physics to appear in a quarter century, this book fills a large gap in the professional literature. Nuclear Reactor Physics is a textbook for students new to the subject, for others who need a basic understanding of how nuclear reactors work, as well as for those who are, or wish to become, specialists in nuclear reactor physics and reactor physics computations. It is also a valuable resource for engineers responsible for the operation of nuclear reactors. Dr. Weston Stacey begins with clear presentations of the basic physical principles, nuclear data, and computational methodology needed to understand both the static and dynamic behaviors of nuclear reactors. This is followed by in-depth discussions of advanced concepts, including extensive treatment of neutron transport computational methods. As an aid to comprehension and quick mastery of computational skills, he provides numerous examples illustrating step-by-step procedures for performing the calculations described and chapter-end problems. Nuclear Reactor Physics is a useful textbook and working reference. It is an excellent self-teaching guide for research scientists, engineers, and technicians involved in industrial, research, and military applications of nuclear reactors, as well as government regulators who wish to increase their understanding of nuclear reactors.

  11. Large Customers (DR Sellers)

    Energy Technology Data Exchange (ETDEWEB)

    Kiliccot, Sila [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

    2011-10-25

    State of the large customers for demand response integration of solar and wind into electric grid; openADR; CAISO; DR as a pseudo generation; commercial and industrial DR strategies; California regulations

  12. EL3 reactor description and safety analysis report

    International Nuclear Information System (INIS)

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10 14 neutrons/cm 2 /sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements [fr

  13. Course of operators of the RA-3 reactor

    International Nuclear Information System (INIS)

    Caligiuri, G.A.

    1983-01-01

    Description of the fundamental principles of the nuclear reactors' control systems. The RA-3 reactor's control and measurement systems are principally described, without setting aside the basic criteria for the design of an appropriate instrumentation for the control of a nuclear reactor, as well as the theory on which the functioning of the several detectors and equipments used in a nuclear instrumentation are based. The main purpose of this course is that of serving, preferentially as a text, for the training of personnel which shall perform operation tasks in this reactor. The work includes three well-defined sections. The first two ones make an introduction to the subject, while the third one, extending to more than half-work, deals with the general description of the system in which the control and operation logic of RA-3 are included. (R.J.S) [es

  14. New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses

    Energy Technology Data Exchange (ETDEWEB)

    Nikitin, Evgeny [Ecole Polytechnique Federale de Lausanne (Switzerland); Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany); Fridman, Emil; Bilodid, Yuri; Kliem, Soeren [Helmholtz-Zentrum Dresden-Rossendorf (HZDR) e.V., Dresden (Germany)

    2017-07-15

    The reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.

  15. Confessions of a Dr Math tutor

    CSIR Research Space (South Africa)

    Butgereit, L

    2015-06-01

    Full Text Available Mathematics look different on a small 3-inch screen of an inexpensive cell phone when compared to a 3-meter whiteboard in a mathematics classroom. Dr Math uses cell phone or mobile data "chat" technologies to assist primary and secondary school...

  16. Prava trećih država u gospodarskom pojasu obalne države

    Directory of Open Access Journals (Sweden)

    Marina Vokić Žužul

    2003-12-01

    Full Text Available Predmet ovoga rada je analiza prava koja u gospodarskom pojasu obalne države mogu ostvarivati sve obalne i neobalne države. uz detaljan prikaz pravnog uređenja materije u odredbama Konvencije o pravu mora iz 1982., razmatraju se i vladajuća gledišta međunarodnopravne doktrine te rješenja u zakonodavstvima pojedinih zemalja. Posebna pozornost je posvećena ostvarivanju tuh prava u potencijalnom hrvatskom gospodarskom pojasu, prvenstveno mogućim zahtjevima od strane susjednih neobalnih država i država u nepovoljnom geografskom položaju. Sva pitanja razmatrana u ovom radu upućuju na zaključak da ispunjavanje dužnosti prema drugim državama u budućem gospodarskom pojasu RH ne bi trebalo imati utjecaja na donošenje odluke o njegovom proglašenju.

  17. Value of HLA-DR genotype in systemic lupus erythematosus and lupus nephritis: a meta-analysis.

    Science.gov (United States)

    Niu, Zhili; Zhang, Pingan; Tong, Yongqing

    2015-01-01

    Human leukocyte antigen (HLA)-DRB1 allele polymorphisms have been reported to be associated with systemic lupus erythematosus (SLE) susceptibility, but the results of these previous studies have been inconsistent. The purpose of the present study was to systematically summarize and explore whether specific HLA-DRB1 alleles confer susceptibility or resistance to SLE and lupus nephritis. This review was guided by the preferred reporting items for systematic reviews and meta-analyses (PRISMA) approach. A comprehensive search was made for articles from PubMed, Medline, Elsevier Science, Springer Link and Cochrane Library database. A total of 25 case-control studies on the relationship between gene polymorphism of HLA-DRB l and SLE were performed and data were analyzed and processed using Review Manager 5.2 and Stata 11.0. At the allelic level, HLA-DR4, DR11 and DR14 were identified as protective factors for SLE (0.79 [0.69,0.91], P  0.05). DR4 and 11 (OR, 0.55 [0.39, 0.79], P  0.05; 0.90 [0.64, 1.27], P > 0.05; 0.61 [0.36, 1.03], P > 0.05, respectively) were not statistically significant between the lupus nephritis and control groups. The HLA-DR4, DR11, DR14 alleles might be protective factors for SLE and HLA-DR3, DR9, DR15 were potent risk factors. In addition, HLA-DR4 and DR11 alleles might be protective factors for lupus nephritis and DR3 and DR15 suggest a risk role. These results proved that HLA-DR3, DR15, DR4 and DR11 might be identified as predictors for lupus nephritis and SLE. © 2014 Asia Pacific League of Associations for Rheumatology and Wiley Publishing Asia Pty Ltd.

  18. Prediction of the stability of BWR reactors during the start-up process

    International Nuclear Information System (INIS)

    Ruiz E, J.A.; Castillo D, R.; Blazquez M, J.B.

    2004-01-01

    The Boiling Water Reactors (BWR) are susceptible of uncertainties of power when they are operated to low flows of coolant (W) and high powers (P), being presented this situation mainly in the start-up process. The start-up process could be made but sure if the operator knew the value of the stability index Decay reason (Dr) before going up power and therefore to guarantee the stability. The power and the flow are constantly measures, the index Dr could also be considered its value in real time. The index Dr depends on the power, flow and many other values, such as, the distribution of the flow axial and radial neutronic, the temperature of the feeding water, the fraction of holes and other thermohydraulic and nuclear parameters. A simple relationship of Dr is derived leaving of the pattern reduced of March-Leuba, where three independent variables are had that are the power, the flow and a parameter that it contains the rest of the phenomenology, that is to say all the other quantities that affect the value of Dr. This relationship developed work presently and verified its prediction with data of start-up of commercial reactors could be used for the design of a practical procedure practice of start-up, what would support to the operator to prevent this type of events of uncertainty. (Author)

  19. Kepler: A Search for Terrestrial Planets - SOC 9.3 DR25 Pipeline Parameter Configuration Reports

    Science.gov (United States)

    Campbell, Jennifer R.

    2017-01-01

    This document describes the manner in which the pipeline and algorithm parameters for the Kepler Science Operations Center (SOC) science data processing pipeline were managed. This document is intended for scientists and software developers who wish to better understand the software design for the final Kepler codebase (SOC 9.3) and the effect of the software parameters on the Data Release (DR) 25 archival products.

  20. Application of NDT and ISI to research reactor in the Czech Republic

    International Nuclear Information System (INIS)

    Peterka, F.

    2001-01-01

    Full text: The objectives of the proposed research project are: (a) to review the present status of ISI and NDT to VR-1 and LVR-15 research reactors. (b) to be involved in the development of the ISI programme for VR-1 and LVR-15 research reactors and medium and high power research reactors of WWER type. Dr. Peterka briefly described the activities on the VR-1 and LWR-15 reactors and presented an example of a procedure to apply liquid penetrant testing. (author)

  1. Enrico Fermi Awards Ceremony for Dr. Mildred S. Dresselhaus and Dr. Burton Richter, May 2012 (Presentations, including remarks by Energy Secretary, Dr. Steven Chu)

    International Nuclear Information System (INIS)

    Chu, Steven

    2012-01-01

    The Fermi Award is a Presidential award and is one of the oldest and most prestigious science and technology honors bestowed by the U.S. Government. On May 7, 2012 it was conferred upon two exceptional scientists: Dr. Mildred Dresselhaus, 'for her scientific leadership, her major contributions to science and energy policy, her selfless work in science education and the advancement of diversity in the scientific workplace, and her highly original and impactful research,' and Dr. Burton Richter, 'for the breadth of his influence in the multiple disciplines of accelerator physics and particle physics, his profound scientific discoveries, his visionary leadership as SLAC Director, his leadership of science, and his notable contributions in energy and public policy.' Dr. John Holder, Director of the White House Office of Science and Technology Policy, opened the ceremony, and Dr. Bill Brinkman, Director of DOE's Office of Science introduced the main speaker, Dr. Steven Chu, U.S. Energy Secretary.

  2. Application of Dr. Mainte, integrated simulator of maintenance optimization, to LWRs

    International Nuclear Information System (INIS)

    Isobe, Yoshihiro; Sagisaka, Mitsuyuki; Etoh, Junji; Matsunaga, Takashi; Kosaka, Toru; Matsumoto, Satoshi; Yoshimura, Shinobu

    2015-01-01

    Dr. Mainte, an integrated simulator for maintenance optimization of LWRs (Light Water Reactors) is based on PFM (Probabilistic Fracture Mechanics) analyses. The concept of the simulator is to provide a decision-making system to optimize maintenance activities for typical components and piping systems in nuclear power plants totally and quantitatively in terms of safety, availability, economic rationality, environmental impact and social acceptance. For the further improvement of the safety and availability of nuclear power plants, the effect of human error and its reduction on the optimization of maintenance activities have been studied. In addition, an approach of reducing human error is proposed. (author)

  3. The proposed use of low enriched uranium fuel in the High Flux Australian Reactor (HIFAR)

    International Nuclear Information System (INIS)

    Vittorio, D.; Durance, G.

    2002-01-01

    The Australian Nuclear Science and Technology Organisation (ANSTO) operates the High Flux Australian Reactor (HIFAR). HIFAR commenced operation in the late 1950's with fuel elements containing uranium enriched to 93%. From that time the level of enrichment has gradually decreased to the current level of 60%. It is now proposed to further reduce the enrichment of HIFAR fuel to <20% by utilising LEU fuel assemblies manufactured by RISO National Laboratory, that were originally intended for use in the DR-3 reactor. Minor modifications have been made to the assemblies to adapt them for use in HIFAR. A detailed design review has been performed and initial safety analysis and reactor physics calculations are to be submitted to ARPANSA as part of a four-stage approval process. (author)

  4. Dr. Tulp's Anatomy Lesson by Rembrandt: the third day hypothesis.

    Science.gov (United States)

    Afek, Arnon; Friedman, Tal; Kugel, Chen; Barshack, Iris; Lurie, Doron J

    2009-07-01

    An autopsy was an important event in 17th century Holland. Autopsies were held in an 'anatomy theater' and performed according to a fixed protocol that often took up to 3 days to complete. Of the five group portraits painted by Rembrandt over the course of his career, two were anatomy lessons given by Dr. Tulp and Dr. Deyman. An examination of Rembrandt's painting Dr. Tulp's Anatomy Lesson (1632) and an X-ray image of the painting, as compared to other paintings of anatomy lessons from the same period, reveal interesting differences, such as positioning, and light and shadow. Not only was the autopsy not performed according to the usual protocol, but in this painting Rembrandt created a unique dramatic scene in his effort to tell a story. We suggest that Dr. Tulp and Rembrandt "modified" the painting of Dr. Tulp's anatomy lesson to emphasize Dr. Tulp's position as the greatest anatomist of his era--"Vesalius of Amsterdam," and as a way of demonstrating God's greatness by highlighting the hand as a symbol of the most glorious of God's creations.

  5. 3 Investment Scenarios for Fast Reactors

    International Nuclear Information System (INIS)

    Shoai Tehrani, Bianka; Da Costa, Pascal

    2013-01-01

    Results: • 4 families of scenarios: – In each of them, 3 options for national nuclear policy → 12 scenarios; – 3 favorable to FRs: - “climate constraint” with strong pro-nuclear policy - “climate constraint” with moderate pro-nuclear policy - “totally green” with strong pro-nuclear policy. • Business As Usual is not favorable to Fast Reactors; Fast reactors deployment: - Needs strong climate policy - Is viable in case of important renewable progress as long as climate policy is strong. International perspective: • Results are valid for Europe, other drivers being likely to be more important in other countries : high growth and demand (Asia); • With strong contrasts between European countries. Further research: • Finer modeling of drivers with unclear influence (clustered and excluded variables): Influence of weak signals

  6. D-3He fueled FRC reactor 'ARTEMIS-L'

    International Nuclear Information System (INIS)

    Momota, Hiromu; Tomita, Yukihiro; Ishida, Akio; Kohzaki, Yasuji; Nakao, Yasuyuki; Nishikawa, Masabumi; Ohi, Shoichi; Ohnishi, Masami.

    1992-09-01

    A neutron-lean D- 3 He fueled field reversed configuration (FRC) fusion reactor is studied on the bases of former high-efficiency ARTEMIS design. Certain improvements such as effective axial contracting plasma heating and cusp-type direct energy converters as well as an empirical scale of the energy confinement are introduced. The resultant total neutron load onto the first wall of the plasma chamber is as low as 0.1 MW/m 2 , which enable the life of the first wall or the structural materials to be longer than the whole life of the reactor. The attractive characteristics of the neutron-lean reactor follow in the ARTEMIS design: it is socially acceptable in views of radioactivity and fuel resources, and the cost of electricity appears to be cheap compared with that from a light water reactor. Critical physics and engineering issues for performing the ARTEMIS-L reactor are clarified. (author)

  7. Description of the RA-3 research reactor as a model facility

    International Nuclear Information System (INIS)

    Vicens, Hugo E.; Quintana, Jorge A.

    2001-01-01

    The Argentine RA-3 reactor is described as a model facility for the information to be provided to the IAEA in accordance with the requirements of the Model Additional Protocol. RA-3 reactor was designed as a 5 MW swimming pool reactor, moderated and cooled with light water. Its fuel was 90% enriched uranium. The reactor started its operation in 1967, has been modified and improved in many components, including the core, that now is fueled with moderately enriched uranium

  8. The simplified P3 approach on a trigonal geometry in the nodal reactor code DYN3D

    International Nuclear Information System (INIS)

    Duerigen, S.; Fridman, E.

    2011-01-01

    DYN3D is a three-dimensional nodal diffusion code for steady-state and transient analyses of Light-Water Reactors with square and hexagonal fuel assembly geometries. Currently, several versions of the DYN3D code are available including a multi-group diffusion and a simplified P 3 (SP 3 ) neutron transport option. In this work, the multi-group SP 3 method based on trigonal-z geometry was developed. The method is applicable to the analysis of reactor cores with hexagonal fuel assemblies and allows flexible mesh refinement, which is of particular importance for WWER-type Pressurized Water Reactors as well as for innovative reactor concepts including block type High-Temperature Reactors and Sodium Fast Reactors. In this paper, the theoretical background for the trigonal SP 3 methodology is outlined and the results of a preliminary verification analysis are presented by means of a simplified WWER-440 core test example. The accordant cross sections and reference solutions were produced by the Monte Carlo code SERPENT. The DYN3D results are in good agreement with the reference solutions. The average deviation in the nodal power distribution is about 1%. (Authors)

  9. 3D computer visualization and animation of CANDU reactor core

    International Nuclear Information System (INIS)

    Qian, T.; Echlin, M.; Tonner, P.; Sur, B.

    1999-01-01

    Three-dimensional (3D) computer visualization and animation models of typical CANDU reactor cores (Darlington, Point Lepreau) have been developed using world-wide-web (WWW) browser based tools: JavaScript, hyper-text-markup language (HTML) and virtual reality modeling language (VRML). The 3D models provide three-dimensional views of internal control and monitoring structures in the reactor core, such as fuel channels, flux detectors, liquid zone controllers, zone boundaries, shutoff rods, poison injection tubes, ion chambers. Animations have been developed based on real in-core flux detector responses and rod position data from reactor shutdown. The animations show flux changing inside the reactor core with the drop of shutoff rods and/or the injection of liquid poison. The 3D models also provide hypertext links to documents giving specifications and historical data for particular components. Data in HTML format (or other format such as PDF, etc.) can be shown in text, tables, plots, drawings, etc., and further links to other sources of data can also be embedded. This paper summarizes the use of these WWW browser based tools, and describes the resulting 3D reactor core static and dynamic models. Potential applications of the models are discussed. (author)

  10. Experiment for search for sterile neutrino at SM-3 reactor

    Science.gov (United States)

    Serebrov, A. P.; Ivochkin, V. G.; Samoylov, R. M.; Fomin, A. K.; Zinoviev, V. G.; Neustroev, P. V.; Golovtsov, V. L.; Gruzinsky, N. V.; Solovey, V. A.; Cherniy, A. V.; Zherebtsov, O. M.; Martemyanov, V. P.; Zinoev, V. G.; Tarasenkov, V. G.; Aleshin, V. I.; Petelin, A. L.; Pavlov, S. V.; Izhutov, A. L.; Sazontov, S. A.; Ryazanov, D. K.; Gromov, M. O.; Afanasiev, V. V.; Matrosov, L. N.; Matrosova, M. Yu.

    2016-11-01

    In connection with the question of possible existence of sterile neutrino the laboratory on the basis of SM-3 reactor was created to search for oscillations of reactor antineutrino. A prototype of a neutrino detector with scintillator volume of 400 l can be moved at the distance of 6-11 m from the reactor core. The measurements of background conditions have been made. It is shown that the main experimental problem is associated with cosmic radiation background. Test measurements of dependence of a reactor antineutrino flux on the distance from a reactor core have been made. The prospects of search for oscillations of reactor antineutrino at short distances are discussed.

  11. Integral test of JENDL-3.3 on fast reactors

    International Nuclear Information System (INIS)

    Chiba, Gou; Hazama, Taira

    2003-05-01

    An integral test has been carried out to evaluate a performance of evaluated nuclear data library JENDL-3.3, which was newly released, in a view of applying neutronics analyses of fast reactors. Japan Nuclear Cycle Development Institute has a large amount of data of critical assembly experiments (ZPPR, BFS, MOZART and FCA) and power reactor tests (JOYO). The database was utilized in this test. In plutonium loaded cores, an improvement was observed about 0.3% ε k in criticality and 5% in the non-leakage term of sodium void reactivity by a revision form JENDL-3.2 to -3.3. These results shoed that the revision is valid in plutonium loaded cores. In uranium loaded cores, dependence of C/E values on control rod position became smaller in control rod worth in ZPPR cores. On the other hand, C/E values became worse both in criticality (0.6%εk) and in sodium void reactivity (30%) in BFS cores. The main cause was a revision of uranium-235 capture cross section, and it could not be concluded whether the revision is valid or not in uranium loaded cores. It is necessary to carry out a validation test at other independent critical experiments in which uranium fuel is used. (author)

  12. Gaia DR1 documentation

    Science.gov (United States)

    van Leeuwen, F.; de Bruijne, J. H. J.; Arenou, F.; Comoretto, G.; Eyer, L.; Farras Casas, M.; Hambly, N.; Hobbs, D.; Salgado, J.; Utrilla Molina, E.; Vogt, S.; van Leeuwen, M.; Abreu, A.; Altmann, M.; Andrei, A.; Babusiaux, C.; Bastian, U.; Biermann, M.; Blanco-Cuaresma, S.; Bombrun, A.; Borrachero, R.; Brown, A. G. A.; Busonero, D.; Busso, G.; Butkevich, A.; Cantat-Gaudin, T.; Carrasco, J. M.; Castañeda, J.; Charnas, J.; Cheek, N.; Clementini, G.; Crowley, C.; Cuypers, J.; Davidson, M.; De Angeli, F.; De Ridder, J.; Evans, D.; Fabricius, C.; Findeisen, K.; Fleitas, J. M.; Gracia, G.; Guerra, R.; Guy, L.; Helmi, A.; Hernandez, J.; Holl, B.; Hutton, A.; Klioner, S.; Lammers, U.; Lecoeur-Taïbi, I.; Lindegren, L.; Luri, X.; Marinoni, S.; Marrese, P.; Messineo, R.; Michalik, D.; Mignard, F.; Montegriffo, P.; Mora, A.; Mowlavi, N.; Nienartowicz, K.; Pancino, E.; Panem, C.; Portell, J.; Rimoldini, L.; Riva, A.; Robin, A.; Siddiqui, H.; Smart, R.; Sordo, R.; Soria, S.; Turon, C.; Vallenari, A.; Voss, H.

    2017-12-01

    We present the first Gaia data release, Gaia DR1, consisting of astrometry and photometry for over 1 billion sources brighter than magnitude 20.7 in the white-light photometric band G of Gaia. The Gaia Data Processing and Analysis Consortium (DPAC) processed the raw measurements collected with the Gaia instruments during the first 14 months of the mission, and turned these into an astrometric and photometric catalogue. Gaia DR1 consists of three parts: an astrometric data set which contains the positions, parallaxes, and mean proper motions for about 2 million of the brightest stars in common with the Hipparcos and Tycho-2 catalogues (the primary astrometric data set) and the positions for an additional 1.1 billion sources (the secondary astrometric data set). The primary set forms the realisation of the Tycho-Gaia Astrometric Solution (TGAS). The second part of Gaia DR1 is the photometric data set, which contains the mean G-band magnitudes for all sources. The third part consists of the G-band light curves and the characteristics of 3000 Cepheid and RR Lyrae stars observed at high cadence around the south ecliptic pole. The positions and proper motions in the astrometric data set are given in a reference frame that is aligned with the International Celestial Reference Frame (ICRF) to better than 0.1 mas at epoch J2015.0, and non-rotating with respect to the ICRF to within 0.03 mas yr^-1. For the primary astrometric data set, the typical standard error for the positions and parallaxes is about 0.3 mas, while for the proper motions the typical standard error is about 1 mas yr^-1. Whereas it has been suggested in Gaia Collaboration et al. (2016a) that a systematic component of ∼0.3 mas should be 'added' (in quadrature) to the parallax uncertainties, Brown (2017) clarifies that reported parallax standard errors already include local systematics as a result of the calibration of the TGAS parallax uncertainties by comparison to Hipparcos parallaxes. For the subset of

  13. In Memoriam: Dr. Frank John Fenner

    Centers for Disease Control (CDC) Podcasts

    This podcast reflects on one of the greatest pioneers in virology, Dr. Frank John Fenner. Dr. Frederick Murphy, a member of EID's editorial board and the Institute of Medicine, and professor of Pathology at the University of Texas Medical Branch in Galveston, shares professional and personal stories of Dr. Frank Fenner.

  14. Parameter definition for reactor physics calculation of Obrigheim KWO PWR type reactor using the Gels and Erebus codes

    International Nuclear Information System (INIS)

    Faya, A.G.; Nakata, H.; Rodrigues, V.G.; Oosterkamp, W.J.

    1974-01-01

    The main variables for Obrigheim Reactor - KWO diffusion theory calculations, using the EREBUS code were defined. The variables under consideration were: mesh spacing for reactor description, time-step in burn-up calculation, and the temperature in both the moderator and the fuel. The best mesh spacing and time-step were defined considering the relative deviations and the computer time expended in each case. It has been verified that the error involved in the mean fuel temperature calculation (1317 0 K as given by SIEMENS and 1028 0 K as calculated by Dr. Penndorf) does not change substancially the calculation results

  15. Identification and distribution of three serologically undetected alleles of HLA-DR by oligonucleotide x DNA typing analysis

    International Nuclear Information System (INIS)

    Tiercy, J.M.; Gorski, J.; Jeannet, M.; Mach, B.

    1988-01-01

    Recent progress in the molecular biology of human major histocompatibility complex class II genes (HLA-DP, -DQ, -DR) have shown that the genetic complexity and allelic polymorphism are greater than expected. In the case of HLA-DR, three DR β-chain loci have been identified and linked, two of which (DR βI and DR βIII, now assigned names HLA-DR1B and HLA-DR3B) are functional. The authors have shown that the HLA micropolymorphism detected at the DNA sequence level can easily be analyzed by hybridization with allele-specific oligonucleotides (HLA oligotyping). In the case of the HLA DRw52 supertypic specificity, which includes the DR3, DR5, DRw6, and DRw8 haplotypes, three alleles, referred to as DRw52a, DRw52b, and DRw52c, have recently been identified at the HLA-DR3B locus by DNA sequencing. Hybridization with locus- and allele-specific oligonucleotide probes (designated 52a, 52b, and 52c) has been performed on DNA from normal individuals forming a panel of 82 haplotypes to establish the distribution of these three alleles. Individuals of the DR3 haplotype had either the DRw52a or DRw52b allele, and individuals of extended haplotype HLA-A1,B8,DR3 had only the DRw52a allele. DR5 individuals all had the DRw52b allele, while individuals of DRw6 haplotype had the DRw52a, -52b, or -52c allele. None of these three alleles are found in DRw8 individuals. Analysis of this micropolymorphism, undetectable by common typing procedures, is therefore now operational for more accurate HLA matching for transplantation and for improving correlations between HLA and disease susceptibility

  16. Power reactor noise

    International Nuclear Information System (INIS)

    Thie, J.A.

    1981-01-01

    Noise analysis is a growing field that offers advantages such as simplicity, low cost, and natural multivariable interactions. A major advantage, continuous and undisturbed monitoring, supplies a means of obtaining early warnings of possible reactor malfunctions, thus preventing further complications by alerting opeators to a problem - and aiding in the diagnosis of that problem - before it demands major repairs. Dr. Thie hopes to further, through detailed explanations and over 70 illustrations, the acceptance of the use of noise analysis by the nuclear utility industry. Following an introductory chapter, the theoretical basis for the various methods of noise analysis is explained, and full chapters are devoted to the fundamentals of statistics for time-domain analysis and Fourier series and related topics for frequency-domain analysis. General experimental techniques and associated theoretical considerations are reviewed, leading to discussions of practical applications in the latter half of the book. Besides chapters giving examples of neutron noise and acoustical noise, chapters are also devoted to extensive examples from pressurized water reactor and boiling water reactor power plants

  17. Dr Stanislaw Huskowski, Mayor of Wroclaw, Poland

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    Dr Stanislaw Huskowski, Mayor of Wroclaw, Poland visiting the ATLAS magnet assembly hall, building 180 with Mr Carlo Lamprecht, State Councillor, Dr Stanislaw Huskowski and Dr Peter Jenni, ATLAS Spokesperson

  18. Gaia DR2 documentation Chapter 3: Astrometry

    Science.gov (United States)

    Hobbs, D.; Lindegren, L.; Bastian, U.; Klioner, S.; Butkevich, A.; Stephenson, C.; Hernandez, J.; Lammers, U.; Bombrun, A.; Mignard, F.; Altmann, M.; Davidson, M.; de Bruijne, J. H. J.; Fernández-Hernández, J.; Siddiqui, H.; Utrilla Molina, E.

    2018-04-01

    This chapter of the Gaia DR2 documentation describes the models and processing steps used for the astrometric core solution, namely, the Astrometric Global Iterative Solution (AGIS). The inputs to this solution rely heavily on the basic observables (or astrometric elementaries) which have been pre-processed and discussed in Chapter 2, the results of which were published in Fabricius et al. (2016). The models consist of reference systems and time scales; assumed linear stellar motion and relativistic light deflection; in addition to fundamental constants and the transformation of coordinate systems. Higher level inputs such as: planetary and solar system ephemeris; Gaia tracking and orbit information; initial quasar catalogues and BAM data are all needed for the processing described here. The astrometric calibration models are outlined followed by the details processing steps which give AGIS its name. We also present a basic quality assessment and validation of the scientific results (for details, see Lindegren et al. 2018).

  19. Dr Stanislaw Huskowski, Mayor of Wroclaw, Poland

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    Dr Stanislaw Huskowski, Mayor of Wroclaw, Poland visiting the ATLAS magnet assembly hall, building 180. From l to r: Mr Carlo Lamprecht, State Councillor, Dr Stanislaw Huskowski and Dr Peter Jenni, ATLAS Spokesperson

  20. 3D CAD model of the subcritical nuclear reactor of IPN

    International Nuclear Information System (INIS)

    Pahuamba V, F. de J.; Delfin L, A.; Gomez T, A.; Ibarra R, G.; Del Valle G, E.; Sanchez R, A.

    2016-09-01

    The three-dimensional (3D) CAD model of the subcritical reactor Chicago model 9000 of Instituto Politecnico Nacional (IPN) allows obtaining a 3D view with the dimensions of each of its components, such as: natural uranium cylindrical rods, fuel elements, hexagonal reactor core arrangement, cylindrical stainless steel tank containing the core, fuel element support grids and reactor water cleaning system. As a starting point for the development of the model, the Chicago model 9000 subcritical reactor manual provided by the manufacturer was used, the measurement and verification of the components to adapt the geometric, physical and mechanical characteristics was carried out and materials standards were used to obtain a design that allows to elaborate a new manual according to the specifications. In addition, the 3D models of the building of the Advanced Physics Laboratory, neutron generator, cobalt source and the corridors connecting to the subcritical reactor facility were developed, allowing an animated ride, developed by computer-aided design software. The manual provided by the company Nuclear Chicago, dates from the year 1959 and presents diverse deviations in the design and dimensions of the reactor components. The model developed; in addition to supporting the development of the new manual represents a learning tool to visualize the reactor components. (Author)

  1. Dr Pugh: a poisoner?

    Science.gov (United States)

    Paull, J D; Morris, G M

    2012-07-01

    On 16 February 1845 the Reverend W. H. Browne, rector of St John's Church in Launceston, Van Diemen's Land, wrote in his journal, "My dear Wife died very suddenly almost immediately after and in consequence of taking a preparation of Hyd. Cyan. Acid prepared & supplied by Dr Pugh". This journal entry raises a number of questions. Was Dr Pugh treating a condition which he thought merited that treatment or was it a ghastly mistake? Was Caroline Browne suffering from pulmonary tuberculosis? Was hydrocyanic acid an accepted treatment at that time? Did Mrs Browne take the wrong dose? Was an incorrect concentration of the drug prepared by Dr Pugh? Did he use the wrong pharmacopoeia in preparing the hydrocyanic acid? Why was there no inquest? Only some of these questions can be answered.

  2. Synthesis of 2',4-dihydroxy-3-methoxychalcone and 2',4',4-trihydroxy-3-methoxychalcone as a candidate anticancer against cervical (WiDr), colon (HeLa), and breast (T47d) cancer cell lines in vitro

    Science.gov (United States)

    Matsjeh, Sabirin; Swasono, Respati Tri; Anwar, Chairil; Solikhah, Eti Nurwening; Lestari, Endang

    2017-03-01

    The compound 2',4-dihydroxy-3-methoxychalcone and 2',4',4-trihydroxy-3-methoxychalcone have been synthesized through Claisen-Schmidt reaction from 2-hydroxyacetophenone and 2,4-dihydroxyacetophenone with 4-hydroxy-3-methoxy benzaldehida (vanillin) in aqueous KOH 40% and KSF montmorillonite as catalyst in methanol. All these products were characterized by FT-IR, TLC Scanner, GC-MS, MS-Direct, and 1H-NMR and 13C-NMR spectrometer. Both of these compounds were tested citotoxycity activity as an anticancer against cervical, colon, and breast cancer cells (Hela, WiDr, and T47D cell lines) using MTT assay in vitro. Dose series given test solution concentration on Hela, WiDr, and T47D cells started from 6,25; 25; 50 and 100 µg/mL with incubation treatment for 24 hours. The result of study showed that the 2',4-dihydroxy-3-methoxychalcone as bright yellow crystal with the melting point of 114-115 °C and the yield of 13.77% and the 2',4',4-trihydroxy-3-methoxychalcone as bright yellow crystals with the melting point of 195-197 °C and the yield of 6%. Other 2',4-dihydroxy-3-methoxychalcone and 2',4',4-trihydroxy-3-methoxychalcone also exhibited cytotoxic activity against the cancer cell lines, with the 2',4',4-trihydroxy-3-methoxychalcone showed greater activities than the 2',4-dihydroxy-3-methoxychalcone in WiDr cell lines. The 2',4-dihydroxy-3-methoxychalcone and 2',4',4-trihydroxy-3-methoxychalcone exhibited strong anticancer activities with IC50 value below 20 µg/mL. The activity of 2',4',4-trihydroxy-3-methoxychalcone showed the most active against Hela and WiDr cell lines with IC50 value 8.53 and 2.66 µg/mL respectively, than T47D cell lines with IC50 value 24.61 µg/mL. The test results cytotoxic of 2',4-dihydroxy-3-methoxychalcone showed the most active against Hela and WiDr cell lines with IC50 value 12.80, 19.57 µg/mL than T47D cell lines with IC50 value of 20.73 µg/mL. IC50 value indicated that 2',4-dihydroxy-3-methoxychalcone and 2',4',4-trihydroxy-3

  3. Study on the reactivity behavior partially loaded reactor cores using SIMULATE-3

    International Nuclear Information System (INIS)

    Holzer, Robert; Zeitz, Andreas; Grimminger, Werner; Lubczyk, Tobias

    2009-01-01

    The reactor core design for the NPP Gundremmingen unit B and C is performed since several years using the validated 3D reactor core calculation program SIMULATE-3. The authors describe a special application of the program to study the reactivity for different partial core loadings. Based on the comparison with results of the program CASMO-4 the program SIMULATE-3 was validated for the calculation of partially loaded reactor cores. For the planned reactor operation in NPP Gundremmingen using new MOX fuel elements the reactivity behavior was studied with respect to the KTA-Code requirements.

  4. Pathogenesis of Human Diffusely Adhering Escherichia coli Expressing Afa/Dr Adhesins (Afa/Dr DAEC): Current Insights and Future Challenges

    Science.gov (United States)

    2014-01-01

    SUMMARY The pathogenicity and clinical pertinence of diffusely adhering Escherichia coli expressing the Afa/Dr adhesins (Afa/Dr DAEC) in urinary tract infections (UTIs) and pregnancy complications are well established. In contrast, the implication of intestinal Afa/Dr DAEC in diarrhea is still under debate. These strains are age dependently involved in diarrhea in children, are apparently not involved in diarrhea in adults, and can also be asymptomatic intestinal microbiota strains in children and adult. This comprehensive review analyzes the epidemiology and diagnosis and highlights recent progress which has improved the understanding of Afa/Dr DAEC pathogenesis. Here, I summarize the roles of Afa/Dr DAEC virulence factors, including Afa/Dr adhesins, flagella, Sat toxin, and pks island products, in the development of specific mechanisms of pathogenicity. In intestinal epithelial polarized cells, the Afa/Dr adhesins trigger cell membrane receptor clustering and activation of the linked cell signaling pathways, promote structural and functional cell lesions and injuries in intestinal barrier, induce proinflammatory responses, create angiogenesis, instigate epithelial-mesenchymal transition-like events, and lead to pks-dependent DNA damage. UTI-associated Afa/Dr DAEC strains, following adhesin-membrane receptor cell interactions and activation of associated lipid raft-dependent cell signaling pathways, internalize in a microtubule-dependent manner within urinary tract epithelial cells, develop a particular intracellular lifestyle, and trigger a toxin-dependent cell detachment. In response to Afa/Dr DAEC infection, the host epithelial cells generate antibacterial defense responses. Finally, I discuss a hypothetical role of intestinal Afa/Dr DAEC strains that can act as “silent pathogens” with the capacity to emerge as “pathobionts” for the development of inflammatory bowel disease and intestinal carcinogenesis. PMID:25278576

  5. Estimation of reactor pool water temperature after shutdown in JRR-3M

    International Nuclear Information System (INIS)

    Yagi, Masahiro; Sato, Mitsugu; Kakefuda, Kazuhiro

    1999-01-01

    The reactor pool water temperature increasing by the decay heat was estimated by calculation. The reactor pool water temperature was calculated by increased enthalpy that was estimated by the reactor decay heat, the heat released from the reactor biological shielding concrete, reactor pool water surface, the heat conduction from the canal and the core inlet piping. These results of calculation were compared with the past measured data. As the results of estimation, after the JRR-3M shutdown, the calculated reactor pool temperature first increased sharply. This is because the decay heat was the major contribution. And then, rate of increased reactor pool temperature decreased. This is because the ratio of heat released from reactor biological shielding concrete and core inlet piping to the decay heat increased. Besides, the calculated reactor pool water temperature agreed with the past measured data in consequence of correcting the decay heat and the released heat. The corrected coefficient k 1 of decay heat was 0.74 - 0.80. And the corrected coefficient k 2 of heat released from the reactor biological shielding concrete was 3.5 - 4.5. (author)

  6. From Mxit to Dr Math

    CSIR Research Space (South Africa)

    Botha, Adèle

    2013-02-01

    Full Text Available In 2007, Laurie Butgereit, a researcher at the CSIR Meraka Institute, started to use Mxit as a communication channel to tutor her son in mathematics. Her son and a number of his friends logged in, and Dr Math was born. At the inception of Dr Math...

  7. Pathogenesis of human diffusely adhering Escherichia coli expressing Afa/Dr adhesins (Afa/Dr DAEC): current insights and future challenges.

    Science.gov (United States)

    Servin, Alain L

    2014-10-01

    The pathogenicity and clinical pertinence of diffusely adhering Escherichia coli expressing the Afa/Dr adhesins (Afa/Dr DAEC) in urinary tract infections (UTIs) and pregnancy complications are well established. In contrast, the implication of intestinal Afa/Dr DAEC in diarrhea is still under debate. These strains are age dependently involved in diarrhea in children, are apparently not involved in diarrhea in adults, and can also be asymptomatic intestinal microbiota strains in children and adult. This comprehensive review analyzes the epidemiology and diagnosis and highlights recent progress which has improved the understanding of Afa/Dr DAEC pathogenesis. Here, I summarize the roles of Afa/Dr DAEC virulence factors, including Afa/Dr adhesins, flagella, Sat toxin, and pks island products, in the development of specific mechanisms of pathogenicity. In intestinal epithelial polarized cells, the Afa/Dr adhesins trigger cell membrane receptor clustering and activation of the linked cell signaling pathways, promote structural and functional cell lesions and injuries in intestinal barrier, induce proinflammatory responses, create angiogenesis, instigate epithelial-mesenchymal transition-like events, and lead to pks-dependent DNA damage. UTI-associated Afa/Dr DAEC strains, following adhesin-membrane receptor cell interactions and activation of associated lipid raft-dependent cell signaling pathways, internalize in a microtubule-dependent manner within urinary tract epithelial cells, develop a particular intracellular lifestyle, and trigger a toxin-dependent cell detachment. In response to Afa/Dr DAEC infection, the host epithelial cells generate antibacterial defense responses. Finally, I discuss a hypothetical role of intestinal Afa/Dr DAEC strains that can act as "silent pathogens" with the capacity to emerge as "pathobionts" for the development of inflammatory bowel disease and intestinal carcinogenesis. Copyright © 2014, American Society for Microbiology. All Rights

  8. In Memoriam: Dr. Frank John Fenner

    Centers for Disease Control (CDC) Podcasts

    2011-04-22

    This podcast reflects on one of the greatest pioneers in virology, Dr. Frank John Fenner. Dr. Frederick Murphy, a member of EID's editorial board and the Institute of Medicine, and professor of Pathology at the University of Texas Medical Branch in Galveston, shares professional and personal stories of Dr. Frank Fenner.  Created: 4/22/2011 by National Center for Emerging Zoonotic and Infectious Diseases (NCEZID).   Date Released: 4/26/2011.

  9. Dr. von Braun Briefing Walt Disney

    Science.gov (United States)

    1965-01-01

    Dr. von Braun began his association with Walt Disney in the 1950s when the rocket scientist appeared in three Disney television productions related to the exploration of space. Years later, Dr. von Braun invited Disney and his associates to tour the Marshall Space Flight Center (MSFC) in Huntsville, Alabama. This photograph is dated April 13, 1965. From left are R.J. Schwinghamer from the MSFC, Disney, B.J. Bernight, and Dr. von Braun.

  10. Association of leprosy with HLA-DR2 in a Southern Brazilian population

    Directory of Open Access Journals (Sweden)

    Visentainer J.E.L.

    1997-01-01

    Full Text Available The association between HLA specificities and leprosy was investigated in a Southern Brazilian population. One hundred and twenty-one patients and 147 controls were typed for HLA-A, B, Cw, DR and DQ. Patients were subdivided into the following subgroups, according to clinical, histological and immunological criteria: lepromatous (N = 55, tuberculoid (N = 32, dimorphous (N = 20, and indeterminate (N = 14. The frequencies of HLA specificities were compared between the total group of patients and controls, and between the same controls and each subgroup of patients. After correction of the probabilities, deviations were not significant, except for the DR2 specificity, which presented a frequency of 44.2% in the total group of patients and 56.3% in the subgroup of individuals with the tuberculoid form of the disease, compared to 23.3% in the controls. Stratified analysis showed that the increased DR2 frequency in the total group of patients was due to the subgroups with the tuberculoid and dimorphous forms. The relative risk of tuberculoid leprosy for DR2-positive individuals was 4.2, and the etiologic fraction of DR2 was 0.429. In conclusion, a positive association of the DR2 specificity with the tuberculoid form of leprosy, but not with the lepromatous, dimorphous, or indeterminate forms, was demonstrated in this Southern Brazilian population

  11. RELAP5/MOD 3.3 analysis of Reactor Coolant Pump Trip event at NPP Krsko

    International Nuclear Information System (INIS)

    Bencik, V.; Debrecin, N.; Foretic, D.

    2003-01-01

    In the paper the results of the RELAP5/MOD 3.3 analysis of the Reactor Coolant Pump (RCP) Trip event at NPP Krsko are presented. The event was initiated by an operator action aimed to prevent the RCP 2 bearing damage. The action consisted of a power reduction, that lasted for 50 minutes, followed by a reactor and a subsequent RCP 2 trip when the reactor power was reduced to 28 %. Two minutes after reactor trip, the Main Steam Isolation Valves (MSIV) were isolated and the steam dump flow was closed. On the secondary side the Steam Generator (SG) pressure rose until SG 1 Safety Valve (SV) 1 opened. The realistic RELAP5/MOD 3.3 analysis has been performed in order to model the particular plant behavior caused by operator actions. The comparison of the RELAP5/MOD 3.3 results with the measurement for the power reduction transient has shown small differences for the major parameters (nuclear power, average temperature, secondary pressure). The main trends and physical phenomena following the RCP Trip event were well reproduced in the analysis. The parameters that have the major influence on transient results have been identified. In the paper the influence of SG 1 relief and SV valves on transient results was investigated more closely. (author)

  12. Modelling of MOCVD Reactor: New 3D Approach

    Science.gov (United States)

    Raj, E.; Lisik, Z.; Niedzielski, P.; Ruta, L.; Turczynski, M.; Wang, X.; Waag, A.

    2014-04-01

    The paper presents comparison of two different 3D models of vertical, rotating disc MOCVD reactor used for 3D GaN structure growth. The first one is based on the reactor symmetry, while the second, novel one incorporates only single line of showerhead nozzles. It is shown that both of them can be applied interchangeably regarding the phenomena taking place within the processing area. Moreover, the importance of boundary conditions regarding proper modelling of showerhead cooling and the significance of thermal radiation on temperature field within the modelled structure are presented and analysed. The last phenomenon is erroneously neglected in most of the hitherto studies.

  13. Modelling of MOCVD reactor: new 3D approach

    International Nuclear Information System (INIS)

    Raj, E; Lisik, Z; Niedzielski, P; Ruta, L; Turczynski, M; Wang, X; Waag, A

    2014-01-01

    The paper presents comparison of two different 3D models of vertical, rotating disc MOCVD reactor used for 3D GaN structure growth. The first one is based on the reactor symmetry, while the second, novel one incorporates only single line of showerhead nozzles. It is shown that both of them can be applied interchangeably regarding the phenomena taking place within the processing area. Moreover, the importance of boundary conditions regarding proper modelling of showerhead cooling and the significance of thermal radiation on temperature field within the modelled structure are presented and analysed. The last phenomenon is erroneously neglected in most of the hitherto studies.

  14. Characteristics of D(-3)He fueled FRC reactor: ARTEMIS-L

    Science.gov (United States)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The characteristics of D(-3)He fueled commercial fusion reactor ARTEMIS-L are discussed. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L becomes compact and its veta-value is extremely high. Consequently, it is possible to construct an economical fusion power plant based on this concept. The life of the structural materials is found during the full reactor life (30 years) and the safety of the reactor is intrinsic to D(-3)He fuels. The amount of disposed materials is rather small and the level of the intruder dose is so low that the plant appears to be acceptable in regards to the environment.

  15. A major population of mucosal memory CD4+ T cells, coexpressing IL-18Rα and DR3, display innate lymphocyte functionality

    DEFF Research Database (Denmark)

    Holmkvist, P.; Roepstorff, K.; Uronen-Hansson, H.

    2015-01-01

    induction of IL-5, IL-13, GM-CSF, and IL-22 was IL-12 independent. IL-18Rα+DR3+CD4+ T cells with similar functionality were present in human skin, nasal polyps, and, in particular, the intestine, where in chronic inflammation they localized with IL-18-producing cells in lymphoid aggregates. Collectively......, these results suggest that human memory IL-18Rα+DR3+CD4+ T cells may contribute to antigen-independent innate responses at barrier surfaces.......Mucosal tissues contain large numbers of memory CD4+ T cells that, through T-cell receptor-dependent interactions with antigen-presenting cells, are believed to have a key role in barrier defense and maintenance of tissue integrity. Here we identify a major subset of memory CD4+ Tcells at barrier...

  16. PR-EDB: Power Reactor Embrittlement Database Version 3

    International Nuclear Information System (INIS)

    Wang, Jy-An John; Subramani, Ranjit

    2008-01-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. 'User-friendly' utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  17. PR-EDB: Power Reactor Embrittlement Database - Version 3

    Energy Technology Data Exchange (ETDEWEB)

    Wang, Jy-An John [ORNL; Subramani, Ranjit [ORNL

    2008-03-01

    The aging and degradation of light-water reactor pressure vessels is of particular concern because of their relevance to plant integrity and the magnitude of the expected irradiation embrittlement. The radiation embrittlement of reactor pressure vessel materials depends on many factors, such as neutron fluence, flux, and energy spectrum, irradiation temperature, and preirradiation material history and chemical compositions. These factors must be considered to reliably predict pressure vessel embrittlement and to ensure the safe operation of the reactor. Large amounts of data from surveillance capsules are needed to develop a generally applicable damage prediction model that can be used for industry standards and regulatory guides. Furthermore, the investigations of regulatory issues such as vessel integrity over plant life, vessel failure, and sufficiency of current codes, Standard Review Plans (SRPs), and Guides for license renewal can be greatly expedited by the use of a well-designed computerized database. The Power Reactor Embrittlement Database (PR-EDB) is such a comprehensive collection of data for U.S. designed commercial nuclear reactors. The current version of the PR-EDB lists the test results of 104 heat-affected-zone (HAZ) materials, 115 weld materials, and 141 base materials, including 103 plates, 35 forgings, and 3 correlation monitor materials that were irradiated in 321 capsules from 106 commercial power reactors. The data files are given in dBASE format and can be accessed with any personal computer using the Windows operating system. "User-friendly" utility programs have been written to investigate radiation embrittlement using this database. Utility programs allow the user to retrieve, select and manipulate specific data, display data to the screen or printer, and fit and plot Charpy impact data. The PR-EDB Version 3.0 upgrades Version 2.0. The package was developed based on the Microsoft .NET framework technology and uses Microsoft Access for

  18. Operating reactors licensing actions summary. Vol. 3, No. 3

    International Nuclear Information System (INIS)

    1983-04-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regularory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program

  19. Report on generation IV technical working group 3 : liquid metal reactors

    International Nuclear Information System (INIS)

    Lineberry, M. J.; Rosen, S. L.; Sagayama, Y.

    2002-01-01

    This paper reports on the first round of R and D roadmap activities of the Generation IV (Gen IV) Technical Working Group (TWG) 3, on liquid metal-cooled reactors. Liquid metal coolants give rise to fast spectrum systems, and thus the reactor systems considered in this TWG are all fast reactors. Gas-cooled fast reactors are considered in the context of TWG 2. As is noted in other Gen IV papers, this first round activity is termed ''screening for potential'', and includes collecting the most complete set of liquid metal reactor/fuel cycle system concepts possible and evaluating the concepts against the Gen IV principles and goals. Those concepts or concept groups that meet the Gen IV principles and which are deemed to have reasonable potential to meet the Gen IV goals will pass to the next round of evaluation. Although we sometimes use the terms ''reactor'' or ''reactor system'' by themselves, the scope of the investigation by TWG 3 includes not only the reactor systems, but very importantly the closed fuel recycle system inevitably required by fast reactors. The response to the DOE Request for Information (RFI) on liquid metal reactor/fuel cycle systems from principal investigators, laboratories, corporations, and other institutions, was robust and gratifying. Thirty three liquid metal concept descriptions, from eight different countries, were ultimately received. The variation in the scope, depth, and completeness of the responses created a significant challenge for the group, but the TWG made a very significant effort not to screen out concepts early in the process

  20. Benchmark tests of JENDL-3.2 for thermal and fast reactors

    International Nuclear Information System (INIS)

    Takano, Hideki

    1995-01-01

    Benchmark calculations for a variety of thermal and fast reactors have been performed by using the newly evaluated JENDL-3 Version-2 (JENDL-3.2) file. In the thermal reactor calculations for the uranium and plutonium fueled cores of TRX and TCA, the k eff and lattice parameters were well predicted. The fast reactor calculations for ZPPR-9 and FCA assemblies showed that the k eff , reactivity worth of Doppler, sodium void and control rod, and reaction rate distribution were in a very good agreement with the experiments. (author)

  1. Nuclear research reactor 0.5 to 3 MW

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1992-05-15

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW{sub TH}, with a minimum thermal neutron flux of approx, 10{sup 13} n/cm{sup 2}{center_dot}sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor

  2. Nuclear research reactor 0.5 to 3 MW

    International Nuclear Information System (INIS)

    1992-05-01

    This nuclear reactor has been designed for radioisotope production, basic and applied research in reactor physics and nuclear engineering, neutron-beam experimentation, irradiation of various materials and training of scientific and technical personnel. It is located in the 'Production Area' of the Nuclear Technology Center. It is equipped with the necessary facilities for large-scale production of radioisotopes to be used in medicine as well as for other scientific and industrial purposes. In addition, it has a Neutronography Facility and the required equipment to perform Neutron-Activation Analysis. It is an open pool-type reactor, moderated and cooled with light water, fuelled with 20% enriched uranium. Its reflector are graphite and water. It has plate-type fuel elements clad in aluminium. The reactor core is located near the bottom of the demineralized water pool. It includes fuel elements, reflector and sample-holding devices for materials to be irradiated. This kind of configuration, which is widely used in research reactors, provides a high degree of safety since it prevents the core from becoming exposed under any circumstance and does not require any cooling system during reactor shutdown. Power output is between 0.5 to 3 MW TH , with a minimum thermal neutron flux of approx, 10 13 n/cm 2 ·sec, at irradiation zone almost with no modifications. Heat extraction is achieved by means of a cooling circuit which comprises two circulation pumps and a plate-type heat exchanger. Final heat dissipation to the atmosphere is performed through another cooling circuit which includes two circulation pumps and a cooling tower. Reactor control is accomplished with five neutron-absorbing rods positioned by means of especially designed elements and governed by the reactor's instrumentation and control system. Should an abnormal situation arise, gravity causes the rods to fall automatically, thus extinguishing the nuclear reaction. The reactor building has a ventilation

  3. EL-3 dismantling of an experimental reactor

    International Nuclear Information System (INIS)

    1989-01-01

    The EL3 experimental reactor has been definitively stopped in march 1979. Its decommissioning has been pronounced in the end of 1982. This article is consecrated at decontamination and dismantling works necessited by its passage at the dismantling level 2 [fr

  4. Experimental and Kinetic Modeling Study of Ethyl Levulinate Oxidation in a Jet-Stirred Reactor

    KAUST Repository

    Wang, Jui-Yang

    2017-01-01

    levulinate chemical kinetic model was first developed by Dr. Stephen Dooley, Trinity College Dublin, and simulated under the same conditions, using the Perfect-Stirred Reactor code in Chemkin software. In comparing the simulation results with experimental

  5. Development of a real-time stability measurement system for boiling water reactors

    International Nuclear Information System (INIS)

    March-Leuba, J.; King, W.T.

    1987-01-01

    This paper describes the development of a portable, real time system for boiling water reactor (BWR) stability measurements. The system provides a means for the operator to monitor the reactor stability using existing plant instrumentation and commercially available hardware. The noise component (i.e., perturbations around steady state) of the neutron signal in BWRs has been shown to contain information about reactor stability, and several algorithms have been developed to extract that information. For the present work, the authors have used an algorithm that has been implemented on a portable personal computer. This algorithm uses the autocorrelation function of naturally occurring neutron noise (measured without special plant perturbations) and an autoregressive modeling technique to produce the asymptotic DR. For this real-time implementation, neutron noise data is preconditioned (i.e., filtered and amplified) and sampled at a 5-Hz sampling rate using a commercial data-acquisition system. Approximately every 1.5 min, the current (snapshot) autocorrelation function is computed directly from the data, and the average autocorrelation is updated. The current and average DR estimates are evaluated with the same periodicity and are displayed on the screen along with the autocorrelations and average power spectrum of the neutron noise

  6. Use of plate fuel elements for the RA3 reactor

    International Nuclear Information System (INIS)

    Parodi, C.; Parkanski, D.; Higa, M.; Marajofsky, A.

    1992-01-01

    The RA3 reactor is a pool reactor, redesigned for 5 MW dissipation. Nineteen plates are used in each fuel element. The utilization of 20% enriched U, gives the possibility of the development of rod type fuel with Al/U 3 O 8 cermets. The thermohydraulic and neutronic conditions are studied in this work in order to satisfy the stipulated power. In addition, the fabrication conditions of Al/U 3 O 8 and Al/U 3 O 8 /Zr H 2 cermets with densities within the limits imposed by the thermohydraulics and neutronics conditions are studied. (author)

  7. Analyize manifestations of DR and CT of 20 cases of bronchioloalveolar carcinoma

    International Nuclear Information System (INIS)

    Yang Zhongcheng

    2006-01-01

    Objective: Exploring the characters and changing rules between DR chest fluoroscopy and CT of bronchioloalveolar carcinoma. Methods: Collecting 20 cases DR chest fluoroscopies and CT scanning results of bron-chioloalveolar carcinoma, proved by biopsy, to reviewing analysis. Results: Bronchioloalveolar carcinoma divided into 3 types, nodular type, diffused type, infiltrated type. Nodular type focuses congregate and fused into node, density of the nodular shadow bad-distributed, vesical low-density shadow showed; Diffused type focus, multiple diffused nodish shadow gradually fused into patech consolidated shadow;Infiltrated focus distributed to pulmonary segment or lobes,like common pneumonia feature, existed airobronchogram, CT contrast scan shows typical 'CT angiogram'. Conclusion: No matter which type: nodular, diffused or infiltrated type, whose DR chest fluoroscopy and CT exists some features: Nodular type, DR chest fluoroscopy shows focuses mostly in periphery of pulmonary, margin with burr and plueral sunken sign, and whose HRCT manifestationshows typical small vesical sign in mediastinal window; Diffused type, DR chest fluoroscopy shows multiple diffused granular nodish shadow, however, CT manifestation can find more multiple focus than DR chest fluoroscopy, typical manifestation of HRCT is extensive small nodular shadow, with the thicken lobular interal; Infiltrated focus: DR chest fluoroscopy shows pulmonary consolidation and airobronchogram, And CT manifestations are CT angiogram and low-density consolidation shadow, wth specific property. Master all types of manifestation of DR and CT of bronchioloalveolar carcinoma, can help you improve the diagnosis of bronchioloalveolar carcinoma. (authors)

  8. Characteristics of D-3He fueled frc reactor: ARTEMIS-L

    International Nuclear Information System (INIS)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The paper introduces briefly the scenario and discuss the attractive characteristics of D-3He fueled commercial fusion reactor ARTEMIS-L. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L is compact and its beta-value is extremely high. One find consequently a possibility of constructing an economical fusion power power plant on this prospect. The life of the structural materials is sound during the full reactor life (30 years) and the safety of the reactor is intrinsic to D-3He fuels. The amount of disposed materials is rather small and the level of these intruder dose is so low that the plant appears to be acceptable in view of the environment. (author)

  9. Summary of the 3rd workshop on the reduced-moderation water reactor

    International Nuclear Information System (INIS)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  10. Summary of the 3rd workshop on the reduced-moderation water reactor

    Energy Technology Data Exchange (ETDEWEB)

    Ishikawa, Nobuyuki; Nakatsuka, Tohru; Iwamura, Takamichi [eds.

    2000-06-01

    The research activities of a Reduced-Moderation Water Reactor (RMWR) are being performed for a development of the next generation water-cooled reactor. A workshop on the RMWR was held on March 3rd 2000 aiming to exchange information between JAERI and other organizations such as universities, laboratories, utilities and vendors. This report summarizes the contents of lectures and discussions on the workshop. The 1st workshop was held on March 1998 focusing on the review of the research activities and future research plan. The succeeding 2nd workshop was held on March 1999 focusing on the topics of the plutonium utilization in water-cooled reactors. The 3rd workshop was held on March 3rd 2000, which was attended by 77 participants. The workshop began with a lecture titled 'Recent Situation Related to Reduced-Moderation Water Reactor (RMWR)', followed by 'Program on MOX Fuel Utilization in Light Water Reactors' which is the mainstream scenario of plutonium utilization by utilities, and 'Feasibility Studies on Commercialized Fast Breeder Reactor Cycle System' mainly conducted by Japan Nuclear Cycle Development Institute (JNC). Also, following lectures were given as the recent research activities in JAERI: 'Progress in Design Study on Reduced-Moderation Water Reactors', 'Long-Term Scenarios of Power Reactors and Fuel Cycle Development and the Role of Reduced Moderation Water Reactors', 'Experimental and Analytical Study on Thermal Hydraulics' and Reactor Physics Experiment Plan using TCA'. At the end of the workshop, a general discussion was performed about the research and development of the RMWR. This report includes the original papers presented at the workshop and summaries of the questions and answers for each lecture and general discussion, as well as presentation viewgraphs, program and participant list as appendixes. The 7 of the presented papers are indexed individually. (J.P.N.)

  11. Modulation of TRAIL resistance in colon carcinoma cells : Different contributions of DR4 and DR5

    NARCIS (Netherlands)

    van Geelen, Caroline M. M.; Pennarun, Bodvael; Le, Phuong T. K.; de Vries, Elisabeth G. E.; de Jong, Steven

    2011-01-01

    Background: rhTRAIL is a therapeutic agent, derived from the TRAIL cytokine, which induces apoptosis in cancer cells by activating the membrane death receptors 4 and 5 (DR4 and DR5). Here, we investigated each receptor's contribution to rhTRAIL sensitivity and rhTRAIL resistance. We assessed whether

  12. Dr. von Braun and Dr. Stuhlinger With a Model of the Nuclear-Electric Vehicles

    Science.gov (United States)

    2004-01-01

    In this photo, taken at the Walt Disney Studios in California, Dr. Wernher von Braun and Dr. Ernst Stuhlinger are shown discussing the concepts of nuclear-electric spaceships designed to undertake the mission to the planet Mars. As a part of the Disney 'Tomorrowland' series on the exploration of space, the nuclear-electric vehicles were shown in the last three television films, entitled 'Mars and Beyond,' which first aired in December 1957.

  13. Gaia: Mapping the Milky Way: The Scientific Promise of Gaia DR2

    Science.gov (United States)

    Walton, Nicholas; ESA Gaia, Data Processing and Analysis Consortium (DPAC)

    2018-06-01

    The ESA Gaia mission will release its first major all sky astrometric catalogue (Gaia DR2), of more than 1.3 billion stars in our Galaxy, on 25 April 2018.This presentation will provide an overview of the Gaia mission, focussing on the significant scientific potential of the Gaia DR2 release. This is based on 22 months of input data and allows for a full Gaia stand alone astrometric solution, including parallaxes and proper motions, of over 1.3 billion sources. The astrometric uncertainties in Gaia DR2 will be at the level of tens of micro-arcsec for sources Gproducts including the light curves of more than half a million variable stars, and the positions of more than thirteen thousand objects in our Solar System.Together with the Gaia DR2 data products and associated release documentation, a small number of performance verification papers, using Gaia DR2 data only to provide new insights into a number of key areas of Gaia science, will be published in a special edition of A&A. These will provide demonstrations of the scientific potential of the Gaia DR2 catalogue, and also highlight some of the issues and limitations involved in the use of the Gaia DR2 data.The Gaia mission and Gaia Data Releases are made possible through the dedication and expertise of the community scientists and engineers involved in the design, construction, and operation of Gaia (led by ESA) and the collaboration of some 450 scientists and software engineers responsible for the complex task of analysing the processed data (the DPAC). The role of both will be covered in the presentation.The presentation will conclude with a brief look ahead to the longer term Gaia data release schedule.

  14. Dr. Yu Wang, Director, Natural Science Division, National Science Council, Taiwan

    CERN Document Server

    Patrice Loïez

    2001-01-01

    Photo 01: L. to r.: Dr. Philippe Bloch, CERN CMS ECAL Deputy Project Manager, Dr. Yu Wang, Dr. Etiennette Auffray, CERN, responsible of the CERN ECAL Regional Centre. Photo 02: L. to r.: Dr. Yu Wang, Dr. Philippe Bloch, Dr. Apollo GO, National Central University, Taiwan, Dr. Etiennette Auffray.

  15. Dr. David Syz, State Secretary for Economic Affairs, Switzerland

    CERN Multimedia

    Patrice Loïez

    2003-01-01

    Photo 01: Dr. David Syz (left) with Professor Roger Cashmore, Research Director for Collider Programmes.Photo 02: Dr. David Syz signing the VIP visitors' book, with Prof. Roger Cashmore.Photo 03: Dr. David Syz signing the VIP visitors' book.Photo 04: Handshake between Dr. David Syz (left) and Prof. Roger Cashmore.

  16. An Interview with Dr. Walter Lear

    Directory of Open Access Journals (Sweden)

    The Editors

    2009-03-01

    Full Text Available In this issue of the English version of Social Medicine we are publishing the first of several pamphlets loaned to us by the US Health Activism History Collection. To introduce this collection we travelled to Philadelphia on June 18, 2008 to interview Dr. Walter J. Lear. Dr Lear, born in 1923, is the person responsible for the collection. In a wide-ranging interview in his home Dr. Lear discussed his personal background, the origins and purpose of the collection, the impact of the McCarthy period on the US health left, as well as his vision for the future.

  17. HLA Dr beta 1 alleles in Pakistani patients with rheumatoid arthritis

    International Nuclear Information System (INIS)

    Naqi, N.; Ahmed, T.A.; Bashir, M.M.

    2011-01-01

    Objective: To determine frequencies of HLA DR beta 1 alleles in rheumatoid arthritis in Pakistani patients. Study Design: Cross sectional / analytical study. Place and Duration of Study: Department of Immunology, Armed Forces Institute of Pathology, Rawalpindi in collaboration with Rheumatology departments of Military Hospital, Rawalpindi and Fauji Foundation Hospital, Rawalpindi, from January 2009 to January 2010. Methodology: HLA DR beta 1 genotyping of one hundred Pakistani patients, diagnosed as having RA as per American College of Rheumatology revised criteria 1987, was done. HLA DR beta 1 genotyping was carried out at allele group level (DR beta 1*01-DR beta 1*16) by sequence specific primers in RA patients. Comparison of HLA DR beta 1 allele frequencies between patients and control groups was made using Pearson's chi-square test to find possible association of HLA DR?1 alleles with RA in Pakistani rheumatoid patients. Results: HLA DR beta 1*04 was expressed with significantly increased frequency in patients with rheumatoid arthritis (p <0.05). HLA DR?1*11 was expressed statistically significantly more in control group as compared to rheumatoid patients indicating a possible protective effect. There was no statistically significant difference observed in frequencies of HLA DR beta 1 allele *01, DR beta 1 allele *03, DR beta 1 allele *07, DR beta 1 allele *08, DR beta 1 allele *09, DR beta 1 allele *10, DR beta 1 allele *12, DR beta 1 allele *13, DR beta 1 allele *14, DR?1 allele *15 and DR beta 1 allele *16 between patients and control groups. Conclusion: The identification of susceptible HLA DR beta 1 alleles in Pakistani RA patients may help physicians to make early decisions regarding initiation of early intensive therapy with disease modifying anti rheumatic medicines and biological agents decreasing disability in RA patients. (author)

  18. Comparaison du Srōš Drōn avec le Drōn Yašt

    OpenAIRE

    Redard, Céline

    2015-01-01

    This paper draws a parallel between two texts having the same textual base: The Srōš Drōn, derived from the Long Liturgy and the Drōn Yašt, belonging to the short liturgies. The goal is to establish the similarities and the discrepancies between these two texts. Peer reviewed

  19. T cell expression of IL-18R and DR3 is essential for non-cognate stimulation of Th1 cells and optimal clearance of intracellular bacteria.

    Science.gov (United States)

    Pham, Oanh H; O'Donnell, Hope; Al-Shamkhani, Aymen; Kerrinnes, Tobias; Tsolis, Renée M; McSorley, Stephen J

    2017-08-01

    Th1 cells can be activated by TCR-independent stimuli, but the importance of this pathway in vivo and the precise mechanisms involved require further investigation. Here, we used a simple model of non-cognate Th1 cell stimulation in Salmonella-infected mice to examine these issues. CD4 Th1 cell expression of both IL-18R and DR3 was required for optimal IFN-γ induction in response to non-cognate stimulation, while IL-15R expression was dispensable. Interestingly, effector Th1 cells generated by immunization rather than live infection had lower non-cognate activity despite comparable IL-18R and DR3 expression. Mice lacking T cell intrinsic expression of MyD88, an important adapter molecule in non-cognate T cell stimulation, exhibited higher bacterial burdens upon infection with Salmonella, Chlamydia or Brucella, suggesting that non-cognate Th1 stimulation is a critical element of efficient bacterial clearance. Thus, IL-18R and DR3 are critical players in non-cognate stimulation of Th1 cells and this response plays an important role in protection against intracellular bacteria.

  20. Dr. Martin Luther King, Jr. as Spiritual Leader

    Directory of Open Access Journals (Sweden)

    Andrea Pierce

    2013-09-01

    Full Text Available The purpose of this paper is to explore Dr. Martin Luther King Jr.’s spiritual leadership through his “I Have a Dream” speech. The paper explores the three characteristics of spiritual leadership as posed by Fry’s (2003 spiritual leadership theory: vision, hope/faith and altruistic love. The research draws upon these characteristics through qualitative content analysis of Dr. Martin Luther King Jr.’s “I Have a Dream” speech to illustrate Dr. King’s leadership as that of a spiritual leader. The research advances the spiritual leadership theory by establishing Dr. Martin Luther King Jr. as a spiritual leader. Through the illustration of Dr. King’s spiritual leadership, the characteristics of a spiritual leader are given tangible understanding.

  1. Integral test of JENDL-3.3 for thermal reactors

    International Nuclear Information System (INIS)

    Okumura, Keisuke; Mori, Takamasa

    2003-01-01

    Criticality benchmark testing was carried out for 59 experiments in various thermal reactors using a continues-energy Monte Carlo code MVP and its different libraries generated from JENDL-3.2, JENDL-3.3, JEF-2.2 and ENDF/B-VI (R8). From the benchmark results, we can say JENDL-3.3 generally gives better k eff values compared with other nuclear data libraries. However, further modification of JENDL-3.3 is expected to solve the following problems: 1) systematic underestimation of k eff depending on 235 U enrichment for the cores with low (less than 3wt.%) enriched uranium fueled cores, 2) dependence of C/E value of k eff on neutron spectrum and plutonium composition for MOX fueled cores. These are common problems for all of the nuclear data libraries used in this study. (author)

  2. Extension of the reactor dynamics code MGT-3D for pebblebed and blocktype high-temperature-reactors

    International Nuclear Information System (INIS)

    Shi, Dunfu

    2015-01-01

    The High Temperature Gas cooled Reactor (HTGR) is an improved, gas cooled nuclear reactor. It was chosen as one of the candidates of generation IV nuclear plants [1]. The reactor can be shut down automatically because of the negative reactivity feedback due to the temperature's increasing in designed accidents. It is graphite moderated and Helium cooled. The residual heat can be transferred out of the reactor core by inactive ways as conduction, convection, and thermal radiation during the accident. In such a way, a fuel temperature does not go beyond a limit at which major fission product release begins. In this thesis, the coupled neutronics and fluid mechanics code MGT-3D used for the steady state and time-dependent simulation of HTGRs, is enhanced and validated [2]. The fluid mechanics part is validated by SANA experiments in steady state cases as well as transient cases. The fuel temperature calculation is optimized by solving the heat conduction equation of the coated particles. It is applied in the steady state and transient simulation of PBMR, and the results are compared to the simulation with the old overheating model. New approaches to calculate the temperature profile of the fuel element of block-type HTGRs, and the calculation of the homogeneous conductivity of composite materials are introduced. With these new developments, MGT-3D is able to simulate block-type HTGRs as well. This extended MGT-3D is used to simulate a cuboid ceramic block heating experiment in the NACOK-II facility. The extended MGT-3D is also applied to LOFC and DLOFC simulation of GT-MHR. It is a fluid mechanics calculation with a given heat source. This calculation result of MGT-3D is verified with the calculation results of other codes. The design of the Japanese HTTR is introduced. The deterministic simulation of the LOFC experiment of HTTR is conducted with the Monte-Carlo code Serpent and MGT-3D, which is the LOFC Project organized by OECD/NEA [3]. With Serpent the burnup

  3. Tribute to Dr Jacques Rogge

    DEFF Research Database (Denmark)

    Bourgois, Jan G; Dumortier, Jasmien; Callewaert, Margot

    2017-01-01

    'A tribute to Dr J. Rogge' aims to systematically review muscle activity and muscle fatigue during sustained submaximal quasi-isometric knee extension exercise (hiking) related to Olympic dinghy sailing as a tribute to Dr Rogge's merits in the world of sports. Dr Jacques Rogge is not only...... of invasive needle electromyography (EMG) during a specific sailing technique (hiking) on a self-constructed sailing ergometer. Hiking is a bilateral and multi-joint submaximal quasi-isometric movement which dinghy sailors use to optimize boat speed and to prevent the boat from capsizing. Large stresses...... are generated in the anterior muscles that cross the knee and hip joint, mainly employing the quadriceps at an intensity of 30-40% maximal voluntary contraction (MVC), sometimes exceeding 100% MVC. Better sailing level is partially determined by a lower rate of neuromuscular fatigue during hiking and for ≈60...

  4. Development of the fast reactor group constant set JFS-3-J3.2R based on the JENDL-3.2

    CERN Document Server

    Chiba, G

    2002-01-01

    It is reported that the fast reactor group constant set JFS-3-J3.2 based on the newest evaluated nuclear data library JENDL3.2 has a serious error in the process of applying the weighting function. As the error affects greatly nuclear characteristics, and a corrected version of the reactor constant set, JFS-3-J3.2R, was developed, as well as lumped FP cross sections. The use of JFS-3-J3.2R improves the results of analyses especially on sample Doppler reactivity and reaction rate in the blanket region in comparison with those obtained using the JFS-3-J3.2.

  5. Development of 3D CFD simulation method in nuclear reactor safety analysis

    International Nuclear Information System (INIS)

    Rosli Darmawan; Mariah Adam

    2012-01-01

    One of the most prevailing issues in the operation of nuclear reactor is the safety of the system. Worldwide publicity on a few nuclear accidents as well as the notorious Hiroshima and Nagasaki bombing have always brought about public fear on anything related to nuclear. Most findings on the nuclear reactor accidents are closely related to the reactor cooling system. Thus, the understanding of the behaviour of reactor cooling system is very important to ensure the development and improvement on safety can be continuously done. Throughout the development of nuclear reactor technology, investigation and analysis on reactor safety have gone through several phases. In the early days, analytical and experimental methods were employed. For the last three decades 1D system level codes were widely used. The continuous development of nuclear reactor technology has brought about more complex system and processes of nuclear reactor operation. More detailed dimensional simulation codes are needed to assess these new reactors. This paper discusses the development of 3D CFD usage in nuclear reactor safety analysis worldwide. A brief review on the usage of CFD at Malaysia's Reactor TRIGA PUSPATI is also presented. (author)

  6. Effect of cell density and HLA-DR incompatibility on T-cell proliferation and forkhead box P3 expression in human mixed lymphocyte reaction.

    Science.gov (United States)

    Song, E Y; Han, S; Yang, B; Morris, G P; Bui, J D

    2015-04-01

    The proliferation rates of human T cells in vitro are affected by some factors such as initial T-cell number, dose of stimulating cells, and duration of culture. The transcription factor forkhead box P3 (FoxP3) has been used to identify regulatory T cells in humans and is thought to correlate with tolerance to allogeneic organ transplant. Thus, it is important to optimize conditions to expand FoxP3 cell proliferation to improve engraftment of allogeneic organ transplants. We studied proliferative responses and FoxP3 expression in divided T cells with the use of flow cytometric analysis of Ki-67 in culture of different concentrations of responding cells (6 × 10(6), 4 × 10(6), 2 × 10(6), 1 × 10(6), and 0.5 × 10(6)cells/mL), different types of stimulating cells (lymphocytes and low density cells), and different numbers of HLA mismatches. The proportion of CD3(+) cells, CD4(+)CD25(+) cells, and CD4(+)CD25(+)FoxP3(+) cells among mononuclear cells were highest at initial cell concentration of 2 × 10(6) responder cells/mL with lymphocytes as stimulators at day-5 mixed lymphocyte reaction (MLR). They were highest at a concentration of 4 × 10(6) responder cells/mL with low density cells as stimulators. The recovery (%), proportion of CD3(+) cells, CD4(+)CD25(+) cells, and CD4(+)CD25(+)FoxP3(+) cells with 2 HLA-DR incompatibility were significantly higher than those of 1 HLA-DR incompatibility at day-5 MLR. Initial cell concentration and HLA-DR incompatibility can affect the generation of FoxP3+ T cells in human MLR. These factors could be considered for efficient generation of Tregs for clinical trials in the future. Copyright © 2015 Elsevier Inc. All rights reserved.

  7. High Temperature Superconductors: From Delivery to Applications (Presentation from 2011 Ernest Orlando Lawrence Award-winner, Dr. Amit Goyal, and including introduction by Energy Secretary, Dr. Steven Chu)

    International Nuclear Information System (INIS)

    Goyal, Amit

    2012-01-01

    Dr. Amit Goyal, a high temperature superconductivity (HTS) researcher at Oak Ridge National Laboratory, was named a 2011 winner of the Department of Energy's Ernest Orlando Lawrence Award honoring U.S. scientists and engineers for exceptional contributions in research and development supporting DOE and its mission. Winner of the award in the inaugural category of Energy Science and Innovation, Dr. Goyal was cited for his work in 'pioneering research and transformative contributions to the field of applied high temperature superconductivity, including fundamental materials science advances and technical innovations enabling large-scale applications of these novel materials.' Following his basic research in grain-to-grain supercurrent transport, Dr. Goyal focused his energy in transitioning this fundamental understanding into cutting-edge technologies. Under OE sponsorship, Dr. Goyal co-invented the Rolling Assisted Bi-Axially Textured Substrate technology (RABiTS) that is used as a substrate for second generation HTS wires. OE support also led to the invention of Structural Single Crystal Faceted Fiber Substrate (SSIFFS) and the 3-D Self Assembly of Nanodot Columns. These inventions and associated R and D resulted in 7 R and D 100 Awards including the 2010 R and D Magazine's Innovator of the Year Award, 3 Federal Laboratory Consortium Excellence in Technology Transfer National Awards, a DOE Energy100 Award and many others. As a world authority on HTS materials, Dr. Goyal has presented OE-sponsored results in more than 150 invited talks, co-authored more than 350 papers and is a fellow of 7 professional societies.

  8. Decay heat removal and heat transfer under normal and accident conditions in gas cooled reactors. Proceedings of a specialists meeting held in Juelich, Germany, 6-8 July 1992

    Energy Technology Data Exchange (ETDEWEB)

    1994-08-15

    The meeting was convened by the International Atomic Energy Agency on the recommendation of the IAEA`s International Working Group on Gas Cooled Reactors. It was attended by participants from China, France, Germany, Japan, Poland, the Russian Federation, Switzerland, the United Kingdom and the United States of America. The meeting was chaired by Prof. Dr. K. Kugeler and Prof. Dr. E. Hicken, Directors of the Institute for Safety Research Technology of the KFA Research Center, and covered the following: Design and licensing requirements for gas cooled reactors; concepts for decay heat removal in modern gas cooled reactors; analytical methods for predictions of thermal response, accuracy of predictions; experimental data for validation of predictive methods - operational experience from gas cooled reactors and experimental data from test facilities. Refs, figs and tabs.

  9. VizieR Online Data Catalog: Gaia DR2 (Gaia Collaboration, 2018)

    Science.gov (United States)

    Gaia Collaboration

    2018-04-01

    Contents of Gaia DR2: The five-parameter astrometric solution - positions on the sky (alpha,delta), parallaxes, and proper motions - for more than 1.3 billion (109) sources, with a limiting magnitude of G=21 and a bright limit of G~=3. Parallax uncertainties are in the range of up to 0.04 milliarcsecond for sources at G2MASS PSC, SDSS DR9, Pan-STARRS1, GSC2.3, PPM-XL, AllWISE, and URAT-1 data on the other hand. Catalogue of radial velocity standard stars (Soubiran et al., 2018A&A..in.prep...): Individual and combined radial velocity measurements are presented for 4813 stars in rvstdcat.dat and rvstdmes.dat files. (20 data files).

  10. Implementing Python for DrRacket

    OpenAIRE

    Ramos, Pedro Palma; Leitão, António Menezes

    2014-01-01

    The Python programming language is becoming increasingly popular in a variety of areas, most notably among novice programmers. On the other hand, Racket and other Scheme dialects are considered excellent vehicles for introducing Computer Science concepts. This paper presents an implementation of Python for Racket and the DrRacket IDE. This allows Python programmers to use Racket libraries and vice versa, as well as using DrRacket's pedagogic features. In particular, it allows architects and d...

  11. Dr. David Syz, State Secretary for Economic Affairs, Switzerland

    CERN Multimedia

    Maximilien Brice

    2003-01-01

    Dr. David Syz, State Secretary for Economic Affairs, Switzerland, toured the assembly hall of the ATLAS experiment on a recent visit to CERN.Photos 01, 02: Dr. Peter Jenni, spokesperson for the ATLAS experiment (second from left), explains to Dr. David Syz (fourth from left) and accompanying visitors the process of integration of a 26-metre-long coil of the barrel toroid magnet system into its coil casing.Photo 03: Dr. Peter Jenni (extreme right) with Dr. David Syz (front row, fourth from right) behind a stack of 26-metre-long 'racetrack' coils awaiting integration into their coil casings.

  12. Large-signal, dynamic simulation of the slowpoke-3 nuclear heating reactor

    International Nuclear Information System (INIS)

    Tseng, C.M.; Lepp, R.M.

    1983-07-01

    A 2 MWt nuclear reactor, called SLOWPOKE-3, is being developed at the Chalk River Nuclear Laboratories (CRNL). This reactor, which is cooled by natural circulation, is designed to produce hot water for commercial space heating and perhaps generate some electricity in remote locations where the costs of alternate forms of energy are high. A large-signal, dynamic simulation of this reactor, without closed-loop control, was developed and implemented on a hybrid computer, using the basic equations of conservation of mass, energy and momentum. The natural circulation of downcomer flow in the pool was simulated using a special filter, capable of modelling various flow conditions. The simulation was then used to study the intermediate and long-term transient response of SLOWPOKE-3 to large disturbances, such as loss of heat sink, loss of regulation, daily load following, and overcooling of the reactor coolant. Results of the simulation show that none of these disturbances produce hazardous transients

  13. RA reactor exploitation, task 3.08/01

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-01-01

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report

  14. Hazarika, Dr Nabajit

    Indian Academy of Sciences (India)

    Hazarika, Dr Nabajit Ph.D. (Tezpur). Date of birth: 17 January 1986. Specialization: Remote Sensing, GIS Applications, Fluvial Geomorphology, Landuse Landcover Studies Address: Dept. of Environmental Science, Nagaland University, Lumami 798 627, Nagaland Contact: Residence: 94354 81256, 97066 71256

  15. Prakash, Dr Vishweshwaraiah

    Indian Academy of Sciences (India)

    Prakash, Dr Vishweshwaraiah Ph.D. (Mysore), FNASc, FNAE, FRSC,FNAAS. Date of birth: 23 November 1951. Specialization: S&T Policy, Physical Biochemistry, Chemistry of Macromolecules, Biophysics of Proteins, Enzymes & Thermodynamics, Food Chemistry, Nutrition, Food Biotechnology and Food Science Address: ...

  16. Dikshit, Dr Madhu

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2000 Section: Medicine. Dikshit, Dr Madhu Ph.D. (Kanpur), FNASc, FNA Council Service: 2016. Date of birth: 21 November 1957. Specialization: Redox Biology, Cardiovascular Pharmacology, Molecular Pharmacology, Neutrophiles and Nitric Oxide Synthase Address: Department ...

  17. Sethunathan, Dr Nambrattil

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1986 Section: Plant Sciences. Sethunathan, Dr Nambrattil Ph.D. (Madras), FNA, FNAAS, FNASc. Date of birth: 2 June 1937. Specialization: Environmental Microbiology Address: Flat No. 103, Ushodaya Apartments, Sri Venkateswara Officers' Colony, Ramakrishnapuram, Secunderabad 500 056, A.P.

  18. Mukerji, Dr Mitali

    Indian Academy of Sciences (India)

    Elected: 2014 Section: Medicine. Mukerji, Dr Mitali Ph.D. (IISc). Date of birth: 13 November 1967. Specialization: Functional Genomics, Population Genomics, Ayurgenomics Address: Sr Principal Scientist, Genomics & Molecualr Medicine, Institute of Genomics & Integrative Biology, Sukhdev Vihar, Mathura Road, New Delhi ...

  19. Characteristics of D-{sup 3}He fueled frc reactor: ARTEMIS-L

    Energy Technology Data Exchange (ETDEWEB)

    Momota, H.; Motojima, O.; Okamoto, M.; Sudo, S.; Tomita, Y.; Yamaguchi, S.; Iiyoshi, A.; Onozuka, M.; Ohnishi, M.; Uenosono, C.

    1993-11-01

    The paper introduces briefly the scenario and discuss the attractive characteristics of D-3He fueled commercial fusion reactor ARTEMIS-L. By using favorable characteristics of a field-reversed configuration, the fusion plasma of ARTEMIS-L is compact and its beta-value is extremely high. One find consequently a possibility of constructing an economical fusion power power plant on this prospect. The life of the structural materials is sound during the full reactor life (30 years) and the safety of the reactor is intrinsic to D-3He fuels. The amount of disposed materials is rather small and the level of these intruder dose is so low that the plant appears to be acceptable in view of the environment. (author).

  20. Fusion reactor control study. Volume 3. Tandem mirror reactors. Final report

    International Nuclear Information System (INIS)

    Chang, F.R.; DeCanio, F.; Fisher, J.L.; Madden, P.A.

    1982-03-01

    A study of the control requirements of the Tandem Mirror Reactor concept is reported. The study describes the development of a control simulator that is based upon a spatially averaged physics code of the reactor concept. The simulator portrays the evolution of the plasma through the complete reactor operating cycle; it includes models of the control and measurement system, thus allowing the exploration of various strategies for reactor control. Startup, shutdown, and control during the quasi-steady-state power producing phase were explored. Configurations are described which use a variety of control effectors including modulation of the refueling rate, beam current, and electron cyclotron resonance heating. Multivariable design techniques were used to design the control laws and compensators for the feedback controllers and presume the practical measurement of only a subset of the plasma and machine variables. Performance of the various controllers is explored using the nonlinear control simulator. Derivative control strategies using new or developed sensors and effectors appropriate to a power reactor environment are postulated, based upon the results of the control configurations tested. Research and development requirements for these controls are delineated

  1. Studies on the liquid fluoride thorium reactor: Comparative neutronics analysis of MCNP6 code with SRAC95 reactor analysis code based on FUJI-U3-(0)

    Energy Technology Data Exchange (ETDEWEB)

    Jaradat, S.Q., E-mail: sqjxv3@mst.edu; Alajo, A.B., E-mail: alajoa@mst.edu

    2017-04-01

    Highlights: • The verification for FUJI-U3-(0)—a molten salt reactor—was performed. • The MCNP6 was used to study the reactor physics characteristics for FUJI-U3 type. • The results from the MCNP6 were comparable with the ones obtained from literature. - Abstract: The verification for FUJI-U3-(0)—a molten salt reactor—was performed. The reactor used LiF-BeF2-ThF4-UF4 as the mixed liquid fuel salt, and the core was graphite moderated. The MCNP6 code was used to study the reactor physics characteristics for the FUJI-U3-(0) reactor. Results for reactor physics characteristic of the FUJI-U3-(0) exist in literature, which were used as reference. The reference results were obtained using SRAC95 (a reactor analysis code) coupled with ORIGEN2 (a depletion code). Some modifications were made in the reconstruction of the FUJI-U3-(0) reactor in MCNP due to unavailability of more detailed description of the reactor core. The assumptions resulted in two representative models of the reactor. The results from the MCNP6 models were compared with the reference results obtained from literature. The results were comparable with each other, but with some notable differences. The differences are because of the approximations that were done on the SRAC95 model of the FUJI-U3 to simplify the simulation. Based on the results, it is concluded that MCNP6 code predicts well the overall simulation of neutronics analysis to the previous simulation works using SRAC95 code.

  2. Systems analysis of the CANDU 3 Reactor

    Energy Technology Data Exchange (ETDEWEB)

    Wolfgong, J.R.; Linn, M.A.; Wright, A.L.; Olszewski, M.; Fontana, M.H. [Oak Ridge National Lab., TN (United States)

    1993-07-01

    This report presents the results of a systems failure analysis study of the CANDU 3 reactor design; the study was performed for the US Nuclear Regulatory Commission. As part of the study a review of the CANDU 3 design documentation was performed, a plant assessment methodology was developed, representative plant initiating events were identified for detailed analysis, and a plant assessment was performed. The results of the plant assessment included classification of the CANDU 3 event sequences that were analyzed, determination of CANDU 3 systems that are ``significant to safety,`` and identification of key operator actions for the analyzed events.

  3. Dr. Hans Chang, Director, Physics Research Committee, Stichting voor Fundamenteel Onderzoek der Materie (FOM), Dr. Joris Van Enst, Head of Science Policy Division, Ministry of Education, Culture and S cience, Dr. Jan Bezemer, NL Delegate CERN, Netherlands

    CERN Multimedia

    Patrice Loiez

    1999-01-01

    Dr. Hans Chang, Director, Physics Research Committee, Stichting voor Fundamenteel Onderzoek der Materie (FOM), Dr. Joris Van Enst, Head of Science Policy Division, Ministry of Education, Culture and S cience, Dr. Jan Bezemer, NL Delegate CERN, Netherlands

  4. Mukhopadhyay, Dr Sangita

    Indian Academy of Sciences (India)

    Elected: 2013 Section: Medicine. Mukhopadhyay, Dr Sangita Ph.D. (Utkal), FNASc. Date of birth: 1 January 1966. Specialization: Immunology, Cell Signalling, Communicable Diseases Address: Group Leader, Molecular Cell Biology, Centre for DNA Fingerprinting & Diagnostics, Nampally, Hyderabad 500 001, A.P.. Contact ...

  5. Mohanty, Dr Debasisa

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2012 Section: General Biology. Mohanty, Dr Debasisa Ph.D. (IISc), FNASc, FNA. Date of birth: 30 November 1966. Specialization: Bioinformatics, Computational & Structural Biology, Biophysics Address: National Institute of Immunology, Aruna Asaf Ali Marg, New Delhi 110 067, ...

  6. Banerjee, Dr Srikumar

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1990 Section: Engineering & Technology. Banerjee, Dr Srikumar Ph.D. (IIT, Kharagpur), FNA, FNAE, FNASc, FTWAS Council Service: 2007-12; Vice-President: 2010-12. Date of birth: 25 April 1946. Specialization: Materials Science, Physical Metallurgy, Phase Transformations, Nuclear Fuel Cycle, ...

  7. Authikesavalu, Dr Munisamy

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1948 Section: Medicine. Authikesavalu, Dr Munisamy MBBS (Madras), MS (Minneapolis), FRCS. Date of birth: 16 August 1906. Date of death: 22 September 1973. Specialization: Experimental Surgery, Ophthalmology, Otolaryngology Last known address: 5-C, Lavelle Cross Road, ...

  8. Santhanam, Dr Vaidyanathaswamy

    Indian Academy of Sciences (India)

    Elected: 1974 Section: Plant Sciences. Santhanam, Dr Vaidyanathaswamy Ph.D. (Madras). Date of birth: 31 July 1925. Specialization: Plant Breeding & Genetics, Research Management and Cotton Development Address: 'Shri Abhirami', 107, Venkataswamy Road West, R S Puram Post, Coimbatore 641 002, T.N.. Contact:

  9. Amarjit Singh, Dr

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1974 Section: Engineering & Technology. Amarjit Singh, Dr Ph.D. (Harvard). Date of birth: 19 November 1924. Specialization: Millimeter Wave Tubes, Microwave Tubes and Microwave Electronics Address: 12, Auburn Court, Vernon Hills, IL 60061, USA Contact: Residence: ...

  10. Chandy, Dr Mammen

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2008 Section: Medicine. Chandy, Dr Mammen MD (Madras), FRACP, FRCPA. Date of birth: 30 August 1949. Specialization: Hematology, Bone Marrow Transplantation and Molecular Genetics of Blood Diseases Address: Director, Tata Memorial Centre, 14, Major Arterial Road, ...

  11. Shivaji, Dr Sisinthy

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2011 Section: Animal Sciences. Shivaji, Dr Sisinthy Ph.D. (Delhi), FNASc. Date of birth: 17 June 1950. Specialization: Anti-Microbial Resistance, Gut Microbiome, Eye Disease, Conservation Biology, Mammalian Sperm Function, Bacterial Biodiversity of Cold Habitats, Cold ...

  12. Reactor core for LMFBR type reactors

    International Nuclear Information System (INIS)

    Masumi, Ryoji; Azekura, Kazuo; Kurihara, Kunitoshi; Bando, Masaru; Watari, Yoshio.

    1987-01-01

    Purpose: To reduce the power distribution fluctuations and obtain flat and stable power distribution throughout the operation period in an LMFBR type reactor. Constitution: In the inner reactor core region and the outer reactor core region surrounding the same, the thickness of the inner region is made smaller than the axial height of the reactor core region and the radial width thereof is made smaller than that of the reactor core region and the volume thereof is made to 30 - 50 % for the reactor core region. Further, the amount of the fuel material per unit volume in the inner region is made to 70 - 90 % of that in the outer region. The difference in the neutron infinite multiplication factor between the inner region and the outer region is substantially constant irrespective of the burnup degree and the power distribution fluctuation can be reduced to about 2/3, by which the effect of thermal striping to the reactor core upper mechanisms can be moderated. Further, the maximum linear power during operation can be reduced by 3 %, by which the thermal margin in the reactor core is increased and the reactor core fuels can be saved by 3 %. (Kamimura, M.)

  13. Characteristics of Rheumatoid Arthritis relative to HLA-DR in Saudi Arabia

    International Nuclear Information System (INIS)

    Al-Arfaj, Abdurhman S.

    2001-01-01

    The objective was to determine the clinical characteristics of rheumatoid arthritis in Saudi Arabia in relation to human leukocyte antigen type. A group of 91 rheumatoid arthritis patients, 72 females and 19 males were studied for the various clinical, laboratory and radiological parameters along with human leukocyte antigen-DR phenotypes. Since human leukocyte antigen-DR10 was most commonly associated with rheumatoid arthritis in our population, we compared those patients with human leukocyte antigen-DR10 to those without. The comparison yielded differences in the presence of rheumatoid nodules, erosions, corticosteroid treatment, and joint involvement at presentation, hemoglobin levels, and white cell count. Only the last 3 parameters showed a statistical significance. Human leukocyte antigen type of Saudi patients with rheumatoid arthritis influenced the course of the disease but only to a limited extent. (author)

  14. Potensi dan Efektivitas Pemungutan Retribusi RSUD Dr. Agoesdjam Ketapang

    OpenAIRE

    B61110063, JAMALUDIN

    2014-01-01

    This study entitled Potential and Effectiveness of retribution collecting in RSUD Dr. Agoesdjam Ketapang which aims to identify and analyze the potential retribution of RSUD Dr . Agoesdjam and also to investigate and analyze the effectiveness of the retribution collecting in RSUD Dr. Agoesdjam . This study uses secondary data , from 2008 to 2012 that were obtained from the Regional Revenue Office of Ketapang and RSUD Dr. Agoesdjam Ketapang . The method of this study is descriptive. To analyz...

  15. Ignition access in a D-3He helical reactor

    International Nuclear Information System (INIS)

    Mitarai, Osamu

    2003-01-01

    Ignition access in a D- 3 He helical reactor is studied based on 0-dimensional particle and power balance equations for deuterium, tritium, helium-3, alpha ash, proton ash, electron density and temperature. The calculations are based on the following experimental facts observed in LHD. (author)

  16. Dr. Irene Sänger-Bredt, a life for astronautics

    Science.gov (United States)

    Zaganescu, Nicolae-Florin

    2004-12-01

    Irene Bredt (b.1911 at Bonn) obtained her Doctorate in Physics in 1937; in the same year she became a scientific researcher at the German Research Center for Aviation at Trauen, led by Prof. Dr. Eugen Sänger. Soon, the young but efficient Dr. Irene Bredt became the first assistant of Dr. Sänger, who married her (1951). During 1973-1978, Dr. Bredt was in correspondence with Prof. Dr. Nikolae-Florin Zaganescu and helped him to familiarize the Romanian readers with Prof. Sänger's life and achievements. As for Dr. Bredt's life, she specified three main periods of her activity: 1937-1942, when she was researcher in charge of thermodynamic problems of liquid-fuelled rocket engines at Trauen 1942-1945, when she was Senior Researcher in charge of Ramjet in flight performances at Ainring, and also coauthored the Top Secret Technical report entitled 'A Rocket Engine for a Long-Range Bomber', which was finished in 1941 but edited only in 1944 the post world war II period, when she was Scientific Advisor or Director at various civil and military research institutes, universities, etc. Dr. Irene Sänger-Bredt helped her husband to develop many scientific theories like Ramjet thermodynamic theory, and photon rocket theory and also in establishing IAF and IAA. In 1970, Dr. Irene Sänger-Bredt was honored with 'Hermann Oberth Gold Medal' for her impressive scientific activity.

  17. Professor Bakytzhan Abdiraiym Rector of the L. Gumilov Eurasian National University, Astana, Kazakhstan accompanied by Prof. Kairat Kuterbekov, Dr Bekzat Prmantayeva, Dr Kuralay Maksut with the Director-General, Dr Tadeusz Kurtyka, Adviser for Non-Member States, Mrs Julia Andreeva, Department of Information Technologies and Dr Nikolai Zimine, ATLAS Collaboration, Joint Institute for Nuclear Research, Dubna

    CERN Document Server

    Maximilien Brice

    2011-01-01

    Professor Bakytzhan Abdiraiym Rector of the L. Gumilov Eurasian National University, Astana, Kazakhstan accompanied by Prof. Kairat Kuterbekov, Dr Bekzat Prmantayeva, Dr Kuralay Maksut with the Director-General, Dr Tadeusz Kurtyka, Adviser for Non-Member States, Mrs Julia Andreeva, Department of Information Technologies and Dr Nikolai Zimine, ATLAS Collaboration, Joint Institute for Nuclear Research, Dubna

  18. 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

  19. Chaddah, Dr Praveen

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1993 Section: Physics. Chaddah, Dr Praveen Ph.D. (Mumbai), FNA, FNASc. Date of birth: 20 December 1951. Specialization: Superconductivity, Low Temperature Physics and Phase Transitions Address: Flat 702, Block 24, Heritage City, MG Road (near Metro Station), Gurgaon ...

  20. Ranganathan, Dr Darshan

    Indian Academy of Sciences (India)

    Elected: 1991 Section: Chemistry. Ranganathan, Dr Darshan Ph.D. (Delhi), FNA. Date of birth: 4 June 1941. Date of death: 4 June 2001. Specialization: Organic Chemistry, Bio-Organic Chemistry and Supramolecular Chemistry Last known address: Scientist, Indian Institue of Chemical, Technology, Uppal Road, Hyderabad ...

  1. Description of Work for Borehole Sampling at the 116-DR-1and 116-DR-2 Trenches

    International Nuclear Information System (INIS)

    Bergstrom, K. A.

    1999-01-01

    This description of work (DOW) details the sampling and analysis activities for characterizing the deep zone soils below the 116-DR-1and 116-DR-2 trenches, which are located in the 100-DR- 1 Operable Unit (OU), and will serve as a guide for the personnel performing the work. The ''deep zone'' refers to the portion of the vadose zone between the bottom of the waste site and the water table. The scope of work includes drilling a borehole (B8786), sampling vadose zone and upper saturated zone soils at ∼ 1-m intervals, collecting a water sample below the top of the water table, and analyzing the samples for all contaminants of concern (COCs). Specific procedures for defined tasks are covered under the Bechtel Hanford, Inc. (BHI)manual, BHI-EE-01, Environmental Investigations Procedures

  2. Goldie Brangman Remembers the Operation to Save Dr King.

    Science.gov (United States)

    Koch, Evan; Brangman, Goldie

    2015-12-01

    In September 1958 the Rev Dr Martin Luther King Jr was stabbed and nearly assassinated. Surgeons at Harlem Hospital in New York City removed a 17.8-cm (7-in)-long letter opener from Dr King's chest. Certified Registered Nurse Anesthetist Goldie Brangman remembers this event because she participated in Dr King's anesthetic. This article correlates Brangman's memories with published accounts of the event. It also places the event within the context of the modern civil rights movement that Dr King led.

  3. Fusion blankets for catalyzed D--D and D--He3 reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β noncircular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphynyl coolant

  4. Fusion blankets for catalyzed D--D and D--3He reactors

    International Nuclear Information System (INIS)

    Fillo, J.A.; Powell, J.R.

    1977-01-01

    Blanket designs are presented for catalyzed D-D (Cat-D) and D-He 3 fusion reactors. Because of relatively low neutron wall loads and the flexibility due to non-tritium breeding, blankets potentially should operate for reactor life-times of approximately 30 years. Unscheduled replacement of failed blanket modules should be relatively rapid, due to very low residual activity, by operators working either through access ports in the shield (option 1) or directly in the plasma chamber (option 2). Cat-D blanket designs are presented for high (approximately 30%) and low (approximately 12%) β non-circular Tokamak reactors. The blankets are thick graphite screens, operating at high temperature to anneal radiation damage; the deposited neutron and gamma energy is thermally radiated along internal cavities and conducted to a bank of internal SiC coolant tubes (approximately 4 cm. ID) containing high pressure helium. In the D-He 3 Tokamak reactor design, the blanket consists of multiple layers (e.g., three) of thin (approximately 10 cm.) high strength aluminum (e.g., SAP), modular plates, cooled by organic terphenyl coolant

  5. RELAP5-3D code validation of RBMK-1500 reactor reactivity measurement transients

    International Nuclear Information System (INIS)

    Kaliatka, Algirdas; Bubelis, Evaldas; Uspuras, Eugenijus

    2003-01-01

    This paper deals with the modeling of transients taking place during the measurements of the void and fast power reactivity coefficients performed at Ignalina NPP. The simulation of these transients was performed using RELAP5-3D code model of RBMK-1500 reactor. At the Ignalina NPP void and fast power reactivity coefficients are measured on a regular basis and, based on the total reactor power, reactivity, control and protection system control rods positions and the main circulation circuit parameter changes during the experiments, the actual values of these reactivity coefficients are determined. Following the simulation of the two above mentioned transients with RELAP5-3D code, a conclusion was made that the obtained calculation results demonstrate reasonable agreement with Ignalina NPP measured data. Behaviors of the separate MCC thermal-hydraulic parameters as well as physical processes are predicted reasonably well to the real processes, occurring in the primary circuit of RBMK-1500 reactor. The calculated reactivity and the total reactor core power behavior in time are also in reasonable agreement with the measured plant data. Despite of the small differences, RELAP5-3D code predicts reactivity and the total reactor core power behavior during the transients in a reasonable manner. Reasonable agreement of the measured and the calculated total reactor power change in time demonstrates the correct modeling of the neutronic processes taking place in RBMK-1500 reactor core

  6. Dr. Steve Thompson, Chief Executive, The Royal Society of New Zealand

    CERN Multimedia

    Maximilien Brice

    2002-01-01

    L. to r.: Dr Austin Ball, Deputy Technical Coordinator, CMS experiment; Dr Roland Horisberger, Paul Scherrer Institute and CERN, CMS experiment; Dr Steve Thompson, Chief Executive, The Royal Society of New Zealand; Dr Michel Della Negra, Spokesman, CMS experiment and Dr Alick Macpherson, Paul Scherrer Institute and CERN, CMS experiment, in the CMS Silicon Tracker assembly hall.

  7. Bhandari, Dr Nita

    Indian Academy of Sciences (India)

    Elected: 2015 Section: Medicine. Bhandari, Dr Nita Ph.D. (JNU), FAMS. Date of birth: 9 November 1955. Specialization: Nutrition-Infection Interaction, Child Health, Nutritional Interventions, Clinical Evaluation of Vaccine Address: President & Director, Centre for Health R&D Society for Applied Studies, 45, Kalu Sarai, New ...

  8. Mukhopadhyay, Dr Amitabha

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 2010 Section: General Biology. Mukhopadhyay, Dr Amitabha Ph.D. (Jadavpur), FNASc, FNA. Date of birth: 5 February 1959. Specialization: Cell Biology, Host-Pathogen Interactions, Drug Delivery Address: Staff Scientist VII, National Institute of Immunology, Aruna Asaf Ali Marg, New Delhi 110 067, ...

  9. Chandy, Dr Jacob

    Indian Academy of Sciences (India)

    Elected: 1961 Section: Medicine. Chandy, Dr Jacob MBBS (Madras), FRCS (c) Council Service: 1962-70. Date of birth: 23 January 1910. Date of death: 23 June 2007. Specialization: Neurology, Neurosurgery and Medical Education Last known address: Paarra, Matteethra, Kottayam 686 004. YouTube; Twitter; Facebook ...

  10. Adhya, Dr Samit

    Indian Academy of Sciences (India)

    Elected: 1999 Section: General Biology. Adhya, Dr Samit Ph.D. (New York), FNA. Date of birth: 29 September 1953. Specialization: Mitochondrial Biology, Molecular Genetics of Parasites, Intracellular RNA Trafficking and DNA Diagnostics Address: CSIR Emeritus Scientist, Indian Inst. of Chemical Biology, 4, Raja S.C. ...

  11. INTAS Secretary General Dr. J. Sinnaeve visiting Athena experiment.

    CERN Multimedia

    Patrice Loiez

    2002-01-01

    Photo 1: INTAS Secretary General Dr. J. Sinnaeve, N. Koulberg, Prof. H. Bokemeyer Head of Physics at INTAS, D.O.Williams and Rolf Landua visiting ATHENA. Photo 2: Prof. H. Bokemeyer Head of Physics at INTAS, INTAS Secretary General J. Sinnaeve and Rolf Landua visiting ATHENA. Photo 3: In the control room of ATHENA, Rolf Landua, Prof. H. Bokemeyer Head of Physics at INTAS and INTAS Secretary General Dr. J. Sinnaeve. INTAS is an independent International Association formed by the European Community, European Union´s Member States and like minded countries acting to preserve and promote the valuable scientific potential of the NIS partner countries through East-West Scientific co-operation.

  12. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report

    International Nuclear Information System (INIS)

    1997-01-01

    Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest

  13. Review of the International Thermonuclear Experimental Reactor (ITER) detailed design report

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1997-04-18

    Dr. Martha Krebs, Director, Office of Energy Research at the US Department of Energy (DOE), wrote to the Fusion Energy Sciences Advisory Committee (FESAC), in letters dated September 23 and November 6, 1996, requesting that FESAC review the International Thermonuclear Experimental Reactor (ITER) Detailed Design Report (DDR) and provide its view of the adequacy of the DDR as part of the basis for the United States decision to enter negotiations with the other interested Parties regarding the terms and conditions for an agreement for the construction, operations, exploitation and decommissioning of ITER. The letter from Dr. Krebs, referred to as the Charge Letter, provided context for the review and a set of questions of specific interest.

  14. HLA-DR-expressing cells and T-lymphocytes in sural nerve biopsies

    DEFF Research Database (Denmark)

    Schrøder, H D; Olsson, T; Solders, G

    1988-01-01

    was confirmed. HLA-DR expression was found in all biopsies and thus was not restricted to any particular type of neuropathy. The HLA-DR expression appeared to correlate with severity and activity of the neuropathy. HLA-DR-expressing macrophages wrapping myelinated fibers were prominent in primary demyelinating......Thirty-five sural nerve biopsies were stained immunohistochemically for HLA-DR antigen. HLA-DR was expressed on nonmyelinating Schwann cells, macrophages, vascular endothelium, and perineurium. By means of double immunofluorescence staining the identity of the HLA-DR presenting structures...

  15. Varadarajan, Dr Srinivasan

    Indian Academy of Sciences (India)

    Elected: 1972 Section: Chemistry. Varadarajan, Dr Srinivasan Ph.D. (Delhi and Cantab), D.Sc. (h.c.), D.Litt. (h.c.), FNA, FNAE, FTWAS Council Service:1974-88; Vice-President: 1977-79; President: 1980-82. Date of birth: 31 March 1928. Specialization: Organic & Biological Chemistry, Molecular Biology, Engineering Design ...

  16. Sengupta, Dr Sagar

    Indian Academy of Sciences (India)

    Sengupta, Dr Sagar Ph.D. (IISc), FNA, FNASc. Date of birth: 23 June 1968. Specialization: Cancer Biology, Cell Signalling, Mytochondrial Biology Address: National Institute of Immunology, Aruna Asaf Ali Marg, New Delhi 110 067, U.T.. Contact: Office: (011) 2670 3786. Residence: (0124) 422 7107. Mobile: 93131 05470

  17. Sengupta, Dr Sagar

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 2017 Section: General Biology. Sengupta, Dr Sagar Ph.D. (IISc), FNA, FNASc. Date of birth: 23 June 1968. Specialization: Cancer Biology, Cell Signalling, Mytochondrial Biology Address: National Institute of Immunology, Aruna Asaf Ali Marg, New Delhi 110 067, U.T.. Contact: Office: (011) 2670 3786

  18. GRIMH3: A new reactor calculation code at Savannah River Site

    International Nuclear Information System (INIS)

    Le, T.T.; Pevey, R.E.

    1993-01-01

    The GRIMHX reactor code currently in use at the Savannah River Site (SRS) was written at a time when computer processing speed and memory storage were very limited. Recently, a new reactor code (GRIMH3) was written to take advantage of the hardware improvements (vectorization and higher memory capacities) as well as the range of available computers at SRS (workstations and supercomputers). The GRIMH3 code computes the solution of the static multigroup neutron diffusion equation in one-, two-, and three-dimensional hexagonal geometry. Either direct or adjoint solutions can be computed for k eff searches, buckling searches, external neutron sources, power flattening searches, or power normalization factor calculations with 1, 6, 24, 54, or 96 points per hex. The GRIMHX reactor code currently in use at the Savannah River Site (SRS) was written at a time when computer processing speed and memory storage were very limited. Recently, a new reactor code (GRIMH3) was written to take advantage of the hardware improvements (vectorization and higher memory capacities) as well as the range of available computers at SRS (workstations and supercomputers). The GRIMH3 code computes the solution of the static multigroup neutron diffusion equation in one-, two-, and three-dimensional hexagonal geometry. Either direct or adjoint solutions can be computed for k eff searches, buckling searches, external neutron sources, power flattening searches, or power normalization factor calculations with 1, 6, 24, 54, or 96 points per hex

  19. DR6 as a diagnostic and predictive biomarker in adult sarcoma.

    Directory of Open Access Journals (Sweden)

    Kun Yang

    Full Text Available The Death Receptor 6 (DR6 protein is elevated in the serum of ovarian cancer patients. We tested DR6 serum protein levels as a diagnostic/predictive biomarker in several epithelial tumors and sarcomas.DR6 gene expression profiles were screened in publically available arrays of solid tumors. A quantitative immunofluorescent western blot analysis was developed to test the serum of healthy controls and patients with sarcoma, uterine carcinosarcoma, bladder, liver, and pancreatic carcinomas. Change in DR6 serum levels was used to assay the ability of DR6 to predict the response to therapy of sarcoma patients.DR6 mRNA is highly expressed in all tumor types assayed. Western blot analysis of serum DR6 protein demonstrated high reproducibility (r = 0.97. Compared to healthy donor controls, DR6 serum levels were not elevated in patients with uterine carcinosarcoma, bladder, liver, or pancreatic cancers. Serum DR6 protein levels from adult sarcoma patients were significantly elevated (p<0.001. This was most evident for patients with synovial sarcoma. Change in serum DR6 levels during therapy correlated with clinical benefit from therapy (sensitivity 75%, and positive predictive value 87%.DR6 may be a clinically useful diagnostic and predictive serum biomarker for some adult sarcoma subtypes.Diagnosis of sarcoma can be difficult and can lead to improper management of these cancers. DR6 serum protein may be a tool to aid in the diagnosis of some sarcomatous tumors to improve treatment planning. For patients with advanced disease, rising DR6 levels predict non-response to therapy and may expedite therapeutic decision making and reduce reliance on radiologic imaging.

  20. Reversal of methylation silencing of Apo2L/TRAIL receptor 1 (DR4) expression overcomes resistance of SK-MEL-3 and SK-MEL-28 melanoma cells to interferons (IFNs) or Apo2L/TRAIL.

    Science.gov (United States)

    Bae, S I; Cheriyath, V; Jacobs, B S; Reu, F J; Borden, E C

    2008-01-17

    Human melanoma cell lines, SK-MEL-3 and SK-MEL-28, despite induction of the proapoptotic cytokine, Apo2L/TRAIL, did not undergo apoptosis in response to interferons (IFN-alpha2b or IFN-beta). Postulating that genes important for apoptosis induction by IFNs might be silenced by methylation, the DNA demethylating agent 5-aza-2'-deoxycytidine (5-AZAdC) was assessed. DR4 (TRAIL-R1) was identified as one of the genes reactivated by 5-AZAdC with a >3-fold increase in 8 of 10 melanoma cell lines. Pretreatment with 5-AZAdC sensitized SK-MEL-3 and SK-MEL-28 cells to apoptosis induced by IFN-alpha2b and IFN-beta; methylation-specific PCR and bisulfite sequencing confirmed demethylation of 5'CpG islands of DR4 and flow cytometry showed an increase in DR4 protein on the cell surface. In cells with reactivated DR4, neutralizing mAB to TRAIL reduced apoptosis in response to IFN-beta or Apo2L/TRAIL. To further confirm the role of DR4, it was expressed by retroviral vector in SK-MEL-3 and SK-MEL-28 cells with reversal of resistance to IFN-beta and Apo2L/TRAIL. Thus, reexpressing DR4 by 5-AZAdC or retroviral transfection in melanoma cell in which promoter methylation had suppressed its expression, potentiated apoptosis by IFN-alpha2b, IFN-beta and Apo2L/TRAIL. Reactivation of silenced proapoptotic genes by inhibitors of DNA methylation may enhance clinical response to IFNs or Apo2L/TRAIL.

  1. Gaia DR2 documentation Chapter 7: Variability

    Science.gov (United States)

    Eyer, L.; Guy, L.; Distefano, E.; Clementini, G.; Mowlavi, N.; Rimoldini, L.; Roelens, M.; Audard, M.; Holl, B.; Lanzafame, A.; Lebzelter, T.; Lecoeur-Taïbi, I.; Molnár, L.; Ripepi, V.; Sarro, L.; Jevardat de Fombelle, G.; Nienartowicz, K.; De Ridder, J.; Juhász, Á.; Molinaro, R.; Plachy, E.; Regibo, S.

    2018-04-01

    This chapter of the Gaia DR2 documentation describes the models and methods used on the 22 months of data to produce the Gaia variable star results for Gaia DR2. The variability processing and analysis was based mostly on the calibrated G and integrated BP and RP photometry. The variability analysis approach to the Gaia data has been described in Eyer et al. (2017), and the Gaia DR2 results are presented in Holl et al. (2018). Detailed methods on specific topics will be published in a number of separate articles. Variability behaviour in the colour magnitude diagram is presented in Gaia Collaboration et al. (2018c).

  2. Irradiated graphite studies prior to decommissioning of G1, G2 and G3 reactors

    International Nuclear Information System (INIS)

    Bonal, J.P.; Vistoli, J.Ph.; Combes, C.

    2005-01-01

    G1 (46 MW th ), G2 (250 MW th ) and G3 (250 MW th ) are the first French plutonium production reactors owned by CEA (Commissariat a l'Energie Atomique). They started to be operated in 1956 (G1), 1959 (G2) and 1960 (G3); their final shutdown occurred in 1968, 1980 and 1984 respectively. Each reactor used about 1200 tons of graphite as moderator, moreover in G2 and G3, a 95 tons graphite wall is used to shield the rear side concrete from neutron irradiation. G1 is an air cooled reactor operated at a graphite temperature ranging from 30 C to 230 C; G2 and G3 are CO 2 cooled reactors and during operation the graphite temperature is higher (140 C to 400 C). These reactors are now partly decommissioned, but the graphite stacks are still inside the reactors. The graphite core radioactivity has decreased enough so that a full decommissioning stage may be considered. Conceming this decommissioning, the studies reported here are: (i) stored energy in graphite, (ii) graphite radioactivity measurements, (iii) leaching of radionuclide ( 14 C, 36 Cl, 63 Ni, 60 Co, 3 H) from graphite, (iv) chlorine diffusion through graphite. (authors)

  3. Transcervical Inoculation with Chlamydia trachomatis Induces Infertility in HLA-DR4 Transgenic and Wild-Type Mice.

    Science.gov (United States)

    Pal, Sukumar; Tifrea, Delia F; Zhong, Guangming; de la Maza, Luis M

    2018-01-01

    Chlamydia trachomatis is the leading cause of infection-induced infertility in women. Attempts to control this epidemic with screening programs and antibiotic therapy have failed. Currently, a vaccine to prevent C. trachomatis infections is not available. In order to develop an animal model for evaluating vaccine antigens that can be applied to humans, we used C. trachomatis serovar D (strain UW-3/Cx) to induce infertility in mice whose major histocompatibility complex class II antigen was replaced with the human leukocyte antigen DR4 (HLA-DR4). Transcervical inoculation of medroxyprogesterone-treated HLA-DR4 transgenic mice with 5 × 10 5 C. trachomatis D inclusion forming units (IFU) induced a significant reduction in fertility, with a mean number of embryos/mouse of 4.4 ± 1.3 compared to 7.8 ± 0.5 for the uninfected control mice ( P < 0.05). A similar fertility reduction was elicited in the wild-type (WT) C57BL/6 mice (4.3 ± 1.4 embryos/mouse) compared to the levels of the WT controls (9.1 ± 0.4 embryos/mouse) ( P < 0.05). Following infection, WT mice mounted more robust humoral and cellular immune responses than HLA-DR4 mice. As determined by vaginal shedding, HLA-DR4 mice were more susceptible to a transcervical C. trachomatis D infection than WT mice. To assess if HLA-DR4 transgenic and WT mice could be protected by vaccination, 10 4 IFU of C. trachomatis D was delivered intranasally, and mice were challenged transcervically 6 weeks later with 5 × 10 5 IFU of C. trachomatis D. As determined by severity and length of vaginal shedding, WT C57BL/6 and HLA-DR4 mice were significantly protected by vaccination. The advantages and limitations of the HLA-DR4 transgenic mouse model for evaluating human C. trachomatis vaccine antigens are discussed. Copyright © 2017 American Society for Microbiology.

  4. Obituary Dr A. W. Kloos (1880—1952)

    NARCIS (Netherlands)

    Ooststroom, van S.J.

    1952-01-01

    At the end of the previous number of “Blumea” could just be inserted the death notice of one of the honorary collaborators of the Rijksherbarium, Dr Ir A. W. Kloos, who passed away in his home at Dordrecht on June 3rd, 1952. A more detailed obituary may follow here. Abraham Willem Kloos was born at

  5. Dr. Albert Carr--Science Educator 1930-2000

    Science.gov (United States)

    Lopez, Leslie

    2013-01-01

    The very first issue of "Educational Perspectives" was published in October of 1962. Dr. Albert Carr wrote one of the inaugural essays on the topic of current developments in science education, and he went on to write several other articles for the journal. This article shares why Dr. Albert Carr's colleagues remember him for his…

  6. A Tribute to Dr. Willy Lens

    Directory of Open Access Journals (Sweden)

    Maarten Vansteenkiste

    2016-07-01

    Full Text Available Dr. Willy Lens, born on December 10th, 1943, passed away on August 29th, 2014. With his passing, the motivation community has lost a seminal member, a mentor, and a friend. Dr. Lens – a Fellow of the Association for Psychological Science and Founding Fellow of the American Educational Research Association – made fundamental contributions to the study of motivation both through his own work and through his caring and thoughtful mentorship of a large community of scholars. With this tribute, we want to honor Dr. Willy Lens’ significance to psychology and education as well as his positive influence, both personally and professionally, on the lives of dozens of scholars. With his contagious enthusiasm and caring mentorship, Willy was an example for our academic community and with this tribute we express our gratitude for the privilege to have collaborated with him.

  7. Drømmebilleder

    DEFF Research Database (Denmark)

    Fausing, Bent

    2014-01-01

    Bogen beskriver i en række intense analyser forbindelsen mellem ydre og indre billeder: altså mellem de moderne mediers billedverden og drømmens og erindringens indre billeder. I fokus for undersøgelsen er desuden kønnet, altså hvordan billeder viser, omformer eller skjuler kønnet, 'det andet', s...

  8. Technical update on pressure suppression type containments in use in U.S. light water reactor nuclear power plants

    International Nuclear Information System (INIS)

    1978-07-01

    In 1972, Dr. S. H. Hanauer (Technical Advisor to the NRC's Executive Director for Operations) wrote a memorandum that raised several questions on the viability of pressure suppression containment concepts. The concerns raised by Dr. Hanauer have recently become the subject of considerable discussion by several members of the U.S. Congress and public. The report provides a response to these expressed concerns and a status summary for various technical matters that relate to the safety of pressure suppression type containments for light water cooled reactor plants

  9. The 4th surveillance testing for Kori unit 3 reactor vessel materials

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Kee Ok; Kim, Byoung Chul; Lee, Sam Lai; Choi, Kwun Jae; Gong, Un Sik; Chang, Jong Hwa; Joo, Yong Sun; Ahn, Sang Bok; Hong, Joon Hwa [Korea Atomic Energy Research Institute, Taejeon (Korea)

    2000-10-01

    Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 4th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Kori unit 3 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules U, V, X and W are 4.983E+18, 1.641E+19, 3.158E+19, and 4.469E+19n/cm{sup 2}, respectively. The bias factor, the ratio of calculation/measurement, was 0.840 for the 1st through 4th testing and the calculational uncertainty, 12% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.362E+19n/cm{sup 2} based on the end of 12th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 3.481E+19, 4.209E+19, 5.144E+19 and 5.974E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Kori unit 3 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 48 refs., 35 figs., 41 tabs. (Author)

  10. Comparison of 2D and 3D Neutron Transport Analyses on Yonggwang Unit 3 Reactor

    International Nuclear Information System (INIS)

    Maeng, Aoung Jae; Kim, Byoung Chul; Lim, Mi Joung; Kim, Kyung Sik; Jeon, Young Kyou; Yoo, Choon Sung

    2012-01-01

    10 CFR Part 50 Appendix H requires periodical surveillance program in the reactor vessel (RV) belt line region of light water nuclear power plant to check vessel integrity resulting from the exposure to neutron irradiation and thermal environment. Exact exposure analysis of the neutron fluence based on right modeling and simulations is the most important in the evaluation. Traditional 2 dimensional (D) and 1D synthesis methodologies have been widely applied to evaluate the fast neutron (E > 1.0 MeV) fluence exposure to RV. However, 2D and 1D methodologies have not provided accurate fast neutron fluence evaluation at elevations far above or below the active core region. RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries) program for 3D geometries calculation was therefore developed both by Westinghouse Electronic Company, USA and Korea Reactor Integrity Surveillance Technology (KRIST) for the analysis of In-Vessel Surveillance Test and Ex-Vessel Neutron Dosimetry (EVND). Especially EVND which is installed at active core height between biological shielding material and concrete also evaluates axial neutron fluence by placing three dosimetries each at Top, Middle and Bottom part of the angle representing maximum neutron fluence. The EVND programs have been applied to the Korea Nuclear Plants. The objective of this study is therefore to compare the 3D and the 2D Neutron Transport Calculations and Analyses on the Yonggwang unit 3 Reactor as an example

  11. Profile Interview: Dr. Patrick Dongosolo Kamalo – Consultant ...

    African Journals Online (AJOL)

    Dr. Yohane Gadama (YG), an MMJ intern, interviews Dr. Patrick Dongosolo Kamalo (PDK) on his work as Malawi's only local practicing neurosurgeon, the launch of Blantyre Institute of Neurological Sciences (BINS) and the beginning of Neurosurgery training in Malawi ...

  12. The induction of autoimmune hepatitis in the human leucocyte antigen-DR4 non-obese diabetic mice autoimmune hepatitis mouse model.

    Science.gov (United States)

    Yuksel, M; Xiao, X; Tai, N; Vijay, G M; Gülden, E; Beland, K; Lapierre, P; Alvarez, F; Hu, Z; Colle, I; Ma, Y; Wen, L

    2016-11-01

    Autoimmune hepatitis (AIH) is a chronic liver disease characterized by progressive inflammation, female preponderance and seropositivity for autoantibodies such as anti-smooth muscle actin and/or anti-nuclear, anti-liver kidney microsomal type 1 (anti-LKM1) and anti-liver cytosol type 1 (anti-LC1) in more than 80% of cases. AIH is linked strongly to several major histocompatibility complex (MHC) alleles, including human leucocyte antigen (HLA)-DR3, -DR7 and -DR13. HLA-DR4 has the second strongest association with adult AIH, after HLA-DR3. We investigated the role of HLA-DR4 in the development of AIH by immunization of HLA-DR4 (DR4) transgenic non-obese diabetic (NOD) mice with DNA coding for human CYP2D6/FTCD fusion autoantigen. Immunization of DR4 mice leads to sustained mild liver injury, as assessed biochemically by elevated alanine aminotransferase, histologically by interface hepatitis, plasma cell infiltration and mild fibrosis and immunologically by the development of anti-LKM1/anti-LC1 antibodies. In addition, livers from DR4 mice had fewer regulatory T cells (T regs ), which had decreased programmed death (PD)-1 expression. Splenic T regs from these mice also showed impaired inhibitory capacity. Furthermore, DR4 expression enhanced the activation status of CD8 + T cells, macrophages and dendritic cells in naive DR4 mice compared to naive wild-type (WT) NOD mice. Our results demonstrate that HLA-DR4 is a susceptibility factor for the development of AIH. Impaired suppressive function of T regs and reduced PD-1 expression may result in spontaneous activation of key immune cell subsets, such as antigen-presenting cells and CD8 + T effectors, facilitating the induction of AIH and persistent liver damage. © 2016 British Society for Immunology.

  13. The induction of autoimmune hepatitis in the human leucocyte antigen‐DR4 non‐obese diabetic mice autoimmune hepatitis mouse model

    Science.gov (United States)

    Yuksel, M.; Xiao, X.; Tai, N.; Vijay, G. M.; Gülden, E.; Beland, K.; Lapierre, P.; Alvarez, F.; Hu, Z.; Colle, I.; Ma, Y.

    2016-01-01

    Summary Autoimmune hepatitis (AIH) is a chronic liver disease characterized by progressive inflammation, female preponderance and seropositivity for autoantibodies such as anti‐smooth muscle actin and/or anti‐nuclear, anti‐liver kidney microsomal type 1 (anti‐LKM1) and anti‐liver cytosol type 1 (anti‐LC1) in more than 80% of cases. AIH is linked strongly to several major histocompatibility complex (MHC) alleles, including human leucocyte antigen (HLA)‐DR3, ‐DR7 and ‐DR13. HLA‐DR4 has the second strongest association with adult AIH, after HLA‐DR3. We investigated the role of HLA‐DR4 in the development of AIH by immunization of HLA‐DR4 (DR4) transgenic non‐obese diabetic (NOD) mice with DNA coding for human CYP2D6/FTCD fusion autoantigen. Immunization of DR4 mice leads to sustained mild liver injury, as assessed biochemically by elevated alanine aminotransferase, histologically by interface hepatitis, plasma cell infiltration and mild fibrosis and immunologically by the development of anti‐LKM1/anti‐LC1 antibodies. In addition, livers from DR4 mice had fewer regulatory T cells (Tregs), which had decreased programmed death (PD)‐1 expression. Splenic Tregs from these mice also showed impaired inhibitory capacity. Furthermore, DR4 expression enhanced the activation status of CD8+ T cells, macrophages and dendritic cells in naive DR4 mice compared to naive wild‐type (WT) NOD mice. Our results demonstrate that HLA‐DR4 is a susceptibility factor for the development of AIH. Impaired suppressive function of Tregs and reduced PD‐1 expression may result in spontaneous activation of key immune cell subsets, such as antigen‐presenting cells and CD8+ T effectors, facilitating the induction of AIH and persistent liver damage. PMID:27414259

  14. Sources of variability for the single-comparator method in a heavy-water reactor

    International Nuclear Information System (INIS)

    Damsgaard, E.; Heydorn, K.

    1978-11-01

    The well thermalized flux in the heavy-water-moderated DR 3 reactor at Risoe prompted us to investigate to what extent a single comparator could be used for multi-element determination instead of multiple comparators. The reliability of the single-comparator method is limited by the thermal-to-epithermal ratio, and experiments were designed to determine the variations in this ratio throughout a reactor operating period (4 weeks including a shut-down period of 4-5 days). The bi-isotopic method using zirconium as monitor was chosen, because 94 Zr and 96 Zr exhibit a large difference in their Isub(o)/Σsub(th) values, and would permit determination of the flux ratio with a precision sufficient to determine variations. One of the irradiation facilities comprises a rotating magazine with 3 channels, each of which can hold five aluminium cans. In this rig, five cans, each holding a polyvial with 1 ml of aqueous zirconium solution were irradiated simultaneously in one channel. Irradiations were carried out in the first and the third week of 4 periods. In another facility consisting of a pneumatic tube system, two samples were simultaneously irradiated on top of each other in a polyethylene rabbit. Experiments were carried out once a week for 4 periods. All samples were counted on a Ge(Li)-detector for 95 Zr, 97 sup(m)Nb and 97 Nb. The thermal-to-epithermal flux ratio was calculated from the induced activity, the nuclear data for the two zirconium isotopes and the detector efficiency. By analysis of variance the total variation of the flux ratio was separated into a random variation between reactor periods, and systematic differences between the positions, as well as the weeks in the operating period. If the variations are in statistical control, the error resulting from use of the single-comparator method in multi-element determination can be estimated for any combination of irradiation position and day in the operating period. With the measure flux ratio variations in DR

  15. Mishra, Dr A C

    Indian Academy of Sciences (India)

    Elected: 2009 Section: Medicine. Mishra, Dr A C . Ph.D. (Pune), FNA. Date of birth: 1 July 1950. Specialization: Human Viral Infection & Zoonotic Diseases, Public Health Address: Director, Interactive Research School of Health Affairs, Bharati Vidyapeeth University, ...

  16. Thiagarajan, Dr Pazhamaneri Subramaniam

    Indian Academy of Sciences (India)

    Elected: 1995 Section: Mathematical Sciences. Thiagarajan, Dr Pazhamaneri Subramaniam Ph.D. (Rice), FNASc. Date of birth: 9 November 1948. Specialization: Distributed Probabilistic Systems, Hybrid Systems and Computational Systems Biology Address: Laboratory of System Pharmacology, Harvard Medical School, ...

  17. Safety in the ARIES-III D-3He tokamak reactor design

    International Nuclear Information System (INIS)

    Herring, J.S.; Dolan, T.J.

    1992-01-01

    This paper reports on the ARIES-III reactor study, an extensive examination of the viability of a D- 3 He-fueled commercial tokamak powder reactor. Because neutrons are produced only through side reactions (D+D- 3 HE+N; and D+D-T+p followed by D+T- 4 He+n), the reactor has the significant advantages of reduced activation of the first wall and shield, low afterheat and Class A or C low level waste disposal. Since no tritium is required for operation, no lithium-containing breeding blanket is necessary. A ferritic steel shield behind the first wall protects the magnets from gamma and neutron heating and from radiation damage. The authors explored the potential for isotopically tailoring the 4 mm tungsten layer on the divertor in order to reduce the offsite doses should a tungsten aerosol be released from the reactor after an accident. The authors also modeled a loss-of-cooling accident (LOCA) in which the organic coolant was burning in order to estimate the amount of radionuclides released from the first wall. Because the maximum temperature is low, degree C, release fractions are small. The authors analyzed the disposition of the 20 g/day of tritium that is produced by D-D reactions and removed by the vacuum pumps

  18. The Flamanville 3 EPR reactor; Le reacteur EPR Flamanville 3

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2007-07-01

    On April 10. 2007, the french government authorized EDF to create on the site of Flamanville ( La Manche) a nuclear base installation containing a pressurized water EPR type reactor. This nuclear reactor, conceived by AREVA NP and EDF, is the first copy of a generation susceptible to replace later, at least partly, the French nuclear reactors at present in operation.Within the framework of its mission of technical support of the Authority of Nuclear Safety ( A.S.N.), the I.R.S.N. widely contributed successively: to define the general objectives of safety assigned to this new generation of pressurized water nuclear reactors; to analyze the options of safety proposed by EDF for the EPR project; To deepen, upstream to the authorization of creation, the evaluation of the step of safety and the measures of conception retained by EDF that have to allow to respect the objectives of safety which were notified to it. (N.C.)

  19. Salunke, Dr Dinakar Mashnu

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 2001 Section: General Biology. Salunke, Dr Dinakar Mashnu Ph.D. (IISc), FNASc, FNA, FTWAS. Date of birth: 1 July 1955. Specialization: Structural Biology, Macromolecular Crystallography and Immunology Address: Director, International Centre for Genetic Engineering, & Biotechnology, Aruna Asaf ...

  20. Watve, Dr Milind Gajanan

    Indian Academy of Sciences (India)

    Date of birth: 12 December 1957. Specialization: Wildlife Ecology & Animal Cognition, Evolutionary Biology, Computational Biology and Microbial Diversity Address: Professor, Biology, Indian Institute of Science Education & Research, Dr Homi Bhabha Road, Pashan, Pune 411 008, Maharashtra Contact: Office: (020) 2590 ...

  1. Shivanna, Dr Kundaranahalli Ramalingaiah

    Indian Academy of Sciences (India)

    Elected: 1985 Section: Plant Sciences. Shivanna, Dr Kundaranahalli Ramalingaiah Ph.D. (Delhi), FNA, FNAAS, FNASc. Date of birth: 30 June 1940. Specialization: Pollen Biology, Reproductive Ecology and Conservation Biology Address: Odekar Farms, Nandihalli, via Thovinakere, Tumkur 572 138, Karnataka Contact:

  2. Reversed field pinch reactor study 3

    International Nuclear Information System (INIS)

    Hollis, A.A.; Mitchell, J.T.D.

    1977-12-01

    This report, the third of a series on the Reversed Field Pinch Reactor, describes a preliminary concept of the engineering design and layout of this pulsed toroidal reactor, which uses the stable plasma behaviour first observed in ZETA. The basic parameters of the 600 MW(e) reactor are taken from a companion study by Hancox and Spears. The plasma volume is 1.75m minor radius and 16m major radius surrounded by a 1.8m blanket-shield region - with the blanket divided into 14 removable segments for servicing. The magnetic confinement system consists of 28 toroidal field coils situated just outside the blanket and inside the poloidal and vertical field coils and all coils have normal copper conductors. The requirement to incorporate a conducting shell at the front of the blanket to provide a short-time plasma stability has a marked effect on the design. It sets the size of the blanket segment and the scale of the servicing operations, limits the breeding gain and complicates the blanket cooling and its integration with the heat engine. An extensive study will be required to confirm the overall reactor potential of the concept. (author)

  3. Safety evaluation for packaging for 1720-DR sodium-filled tank

    International Nuclear Information System (INIS)

    Mercado, M.S.

    1996-01-01

    Preparations are under way to sell the sodium stored in the 1720-DR tank in the 1720-DR building. This will require that the tank, as well as the 1720-DR facility, be moved to the 300 Area, so that the sodium may be melted and transferred into a railroad tanker car. Because the sodium is a hazardous material and is being shipped in a nonspecification packaging, a safety evaluation for packaging (SEP) is required. This SEP approves the sodium-filled tank for a single shipment from the 105-DR area to the 300 Area

  4. Does transitioning from computed radiography (CR) to direct radiography (DR) with portable imaging systems affect workflow efficiency?

    Science.gov (United States)

    Gali, Raja L.; Roth, Christopher G.; Smith, Elizabeth; Dave, Jaydev K.

    2018-03-01

    In digital radiography, computed radiography (CR) technology is based on latent image capture by storage phosphors whereas direct radiography (DR) technology is based either on indirect conversion using a scintillator or direct conversion using a photoconductor. DR-based portable imaging systems may enhance workflow efficiency. The purpose of this work was to investigate changes in workflow efficiency at a tertiary healthcare center after transitioning from CR to DR technology for imaging with portable x-ray units. An IRB exemption was obtained. Data for all inpatient-radiographs acquired with portable x-ray units from July-2014 till June-2015 (period 1) with CR technology (AMX4 or AMX4+ portable unit from GE Healthcare, NX workstation from Agfa Healthcare for digitization), from July-2015 till June-2016 (period 2) with DR technology (Carestream DRX-Revolution x-ray units and DRX-1C image receptors) and from July-2016 till January-2017 (period 3; same DR technology) were extracted using Centricity RIS-IC (GE Healthcare). Duration between the imaging-examination scheduled time and completed time (timesch-com) was calculated and compared using non-parametric tests (between the three time periods with corrections for multiple comparisons; three time periods were used to identify if there were any other potential temporal trends not related to transitioning from CR to DR). IBM's SPSS package was used for statistical analysis. Overall data was obtained from 33131, 32194, and 18015 cases in periods 1, 2 and 3, respectively. Independent-Samples Kruskal-Wallis test revealed a statistically significant difference in timesch-com across the three time periods (χ2(2, n= 83,340) = 2053, p < 0.001). The timesch-com was highest for period 1 i.e., radiographs acquired with CR technology (median: 64 minutes) and it decreased significantly for radiographs acquired with DR technology in periods 2 (median: 49 minutes; p < 0.001) and 3 (median∶ 44 minutes; p < 0.001). Overall

  5. Chandrashekar, Dr Tavarekere Kalliah

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 2000 Section: Chemistry. Chandrashekar, Dr Tavarekere Kalliah Ph.D. (IISc), FNASc, FNA, FTWAS Council Service: 2013-15. Date of birth: 1 January 1956. Specialization: Bio-inorganic Chemistry, Synthetic Inorganic Chemistry and Catalysis Address: Senior Professor, School of Chemical Sciences, ...

  6. Majumdar, Dr Subeer Suhash

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 2014 Section: Animal Sciences. Majumdar, Dr Subeer Suhash Ph.D. (nagpur), FNA, FNASc. Date of birth: 21 May 1961. Specialization: Animal Biotechnology, Transgenic Animals, Endocrinology Address: Director, National Institute of Animal Biotechnology, Gopan Pally, Hyderabad 500 046, A.P.

  7. Gupta, Dr Chhitar Mal

    Indian Academy of Sciences (India)

    Gupta, Dr Chhitar Mal Ph.D. (Agra), FNA, FNASc, FAMS, FTWAS Council Service: 1998-2000. Date of birth: 1 September 1944. Specialization: Membrane Biology, Bio-organic Chemistry and Molecular Biophysics Address: Distinguished Professor and Infosys Chair, Institute of Bioinformatics & Applied Biotechnology, Room ...

  8. Babu, Dr Cherukuri Raghavendra

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1990 Section: Plant Sciences. Babu, Dr Cherukuri Raghavendra D.Phil. (Calcutta). Date of birth: 30 June 1940. Specialization: Biosystematics, Ecology and Population Genetics Address: Professor Emeritus, CEMDE, School of Environmental Studies, University of Delhi, Delhi 110 007, U.T.. Contact:

  9. Anil, Dr Arga Chandrashekar

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2015 Section: Earth & Planetary Sciences. Anil, Dr Arga Chandrashekar Ph.D. (Karnatak). Date of birth: 23 January 1959. Specialization: Biological Oceanography, Marine Ecology, Marine Biology Address: Chief Scientist, National Institute of Oceanography, Dona Paula 403 004, ...

  10. Sharma, Dr Ram Swaroop

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1989 Section: Earth & Planetary Sciences. Sharma, Dr Ram Swaroop Ph.D. (Basel), FNA. Date of birth: 10 July 1937. Specialization: Metamorphic Petrology, Mineralogy and Precambrian Geology Address: 70/36, Pratapnagar, Sector 7, Sanganer (RHB), Jaipur 302 033, Rajasthan

  11. Dr Satish R. Shetye

    Indian Academy of Sciences (India)

    Elected: 1992 Section: Earth & Planetary Sciences. Shetye, Dr Satish Ramnath Ph.D. (Washington), FNA, FNASc. Council Service: 1998-2003. Date of birth: 25 October 1950. Specialization: Physical Oceanography Address: Vice Chancellor, Goa University, Taleigao Plateau 403 206, Goa Contact: Office: (0832) 651 9001

  12. Jena, Dr Prafulla Kumar

    Indian Academy of Sciences (India)

    Jena, Dr Prafulla Kumar Ph.D. (Utkal). Date of birth: 27 December 1931. Specialization: Extractive Metallurgy, Mineral Processing, Environmental Engineering and Materials Processing Address: Chairman, Institute of Advance Technology and Environmental Studies, 80A-831A Lewis Road, Bhubaneswar 751 002, Orissa

  13. Kulkarni, Dr Mohan Gopalkrishna

    Indian Academy of Sciences (India)

    Elected: 1996 Section: Engineering & Technology. Kulkarni, Dr Mohan Gopalkrishna Ph.D. (Mumbai), FNAE. Date of birth: 14 November 1950. Specialization: Polymer Science & Engineering, Intellectual Property Address: Emeritus Scientist, Unit for R&D of Information Products, Tapovan, NCL Campus, Pashan Road, Pune ...

  14. Apte, Dr Shree Kumar

    Indian Academy of Sciences (India)

    Elected: 2008 Section: General Biology. Apte, Dr Shree Kumar Ph.D. (Gujarat), FNA, FNASc, FNAAS. Date of birth: 18 October 1952. Specialization: Molecular Biology & Biotechnology, Physiology and Stress Biology of Bacteria & Plants Address: Emeritus Professor, Homi Bhabha National Institute, Anushakti Nagar, ...

  15. Teaching medicine with the help of "Dr. House".

    Science.gov (United States)

    Jerrentrup, Andreas; Mueller, Tobias; Glowalla, Ulrich; Herder, Meike; Henrichs, Nadine; Neubauer, Andreas; Schaefer, Juergen R

    2018-01-01

    TV series such as "House MD", "Grey´s Anatomy" or "Emergency Room" are well perceived by medical students. Seminars featuring medical TV series such as "House MD" might serve as door-opener to attract medical students to learn more about rare diseases. The TV series "House MD" is troublesome for the main character Dr. House is an excellent diagnostician but at the same time a rather misanthropic person. Therefore, lecturing medicine with the help of "House MD" requires constant evaluation. From 2008 to 2016 we are using the well-known TV series "House MD" continuously to attract medical students and teach them about rare diseases as well as diagnostic strategies. We collected from 213 students a detailed questionnaire assessing their learning experience. 76.6% of our students (n = 157) reported to watching medical dramas on a regular basis. The Dr. House seminar was compared to traditional seminars and our students reported an improved learning effect (69.9%), better concentration (89.7%), higher motivation to participate (88.7%), and more fun (86.7%) (all pHouse's behavior quite critically. Likert assessment on a 5-point scale identified strong disagreement with Dr. House´s interpersonal skills in dealing with his colleagues (median = 1) and patients (median = 1). At the same time, the students strongly agreed with his outstanding diagnostic (median = 5) and therapeutic capabilities (median = 4). Medical students visiting a Dr. House teaching seminar are highly motivated to learn more about rare diseases. They were positively influenced by TV series such as Dr. House to improve their diagnostic and clinical skills. At the same time, they are critical enough not to see Dr. House as a role model for their own personality. Well performed medical TV shows such as Dr. House can successfully be used in an educational setting to motivate medical students to come into seminars to learn more about rare diseases.

  16. Safety analysis of loss of flow transients in a typical research reactor by RELAP5/MOD3.3

    International Nuclear Information System (INIS)

    Di Maro, B.; Pierro, F.; Adorni, M.; Bousbia Salah, A.; D'Auria, F.

    2003-01-01

    The main aim of the following study is to assess the RELAP5/MOD3.3 code capability in simulating transient dynamic behaviour in nuclear research reactors. For this purpose typical loss of flow transient in a representative MTR (Metal Test Reactor) fuel type Research Reactor is considered. The transient herein considered is a sudden pump trip followed by the opening of a safety valve in order to allow passive decay heat removal by natural convection. During such transient the coolant flow decay, originally downward, leads to a flow reversal and the cooling process of the core passes from forced, mixed and finally to natural circulation. This fact makes it suitable for evaluating the new features of RELAP5 to simulate such specific operating conditions. The instantaneous reactor power is derived through the point kinetic calculation, both protected and unprotected cases are considered (with and without Scram). The results obtained from this analysis were also compared with previous results obtained by old version RELAP5/MOD2 code. (author)

  17. The World's Reactors no. 70 - Forsmark 3, BWR-75

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    A large pull-out wall chart is presented showing a coloured cut-away diagram of the Forsmark 3 station. It is accompanied by 2 small sketches one showing the layout of station buildings and the other the inside of the reactor vessel. Parameters are listed. (U.K.)

  18. Gas Reactor International Cooperative program. Pebble bed reactor plant: screening evaluation. Volume 3. Appendix A. Equipment list

    International Nuclear Information System (INIS)

    1979-11-01

    This report consists of three volumes which describe the design concepts and screening evaluation for a 3000 MW(t) Pebble Bed Reactor Multiplex Plant (PBR-MX). The Multiplex plant produces both electricity and transportable chemical energy via the thermochemical pipeline (TCP). The evaluation was limited to a direct cycle plant which has the steam generators and steam reformers in the primary circuit. Volume 1 reports the overall plant and reactor system and was prepared by the General Electric Company. Core scoping studies were performed which evaluated the effects of annular and cylindrical core configurations, radial blanket zones, burnup, and ball heavy metal loadings. The reactor system, including the PCRV, was investigated for both the annular and cylindrical core configurations. Volume 3 is an Appendix containing the equipment list for the plant and was also prepared by United Engineers and Constructors, Inc. It tabulates the major components of the plant and describes each in terms of quantity, type, orientation, etc., to provide a basis for cost estimation

  19. Brahmayya Sastry, Dr Podila

    Indian Academy of Sciences (India)

    Elected: 1978 Section: Medicine. Brahmayya Sastry, Dr Podila Ph.D. (McGill). Date of birth: 24 May 1913. Date of death: 28 May 1993. Specialization: Physiology, Neurophysiology and Placental Physiology Last known address: Sitaramanilayam, Plot No. 9, Doctors Co-Operative Housing Colony, Waltair, Visakhapatnam ...

  20. Valluri, Dr Sitaram Rao

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1971 Section: Engineering & Technology. Valluri, Dr Sitaram Rao Ph.D. (Caltech). Date of birth: 25 June 1924. Specialization: Metal Fatigue Address: 'Prashanthi', 659, 100 Feet Road, Indiranagar, Bengaluru 560 038, Karnataka Contact: Residence: (080) 2525 8294. YouTube ...

  1. Shastry, Dr B Sriram

    Indian Academy of Sciences (India)

    Shastry, Dr B Sriram Ph.D. (Mumbai), FNA, FNASc, FTWAS. Date of birth: 26 November 1950. Specialization: Strongly-Correlated Fermi Systems, Quantum Integrable Systems Address: Distinguished Professor, Department of Physics, University of California, Santa Cruz, CA 95064, USA Contact: Office: (+1-831) 459 5849

  2. Gangal, Dr Sharad Vishwanath

    Indian Academy of Sciences (India)

    Gangal, Dr Sharad Vishwanath Ph.D. (Mumbai), FNASc. Date of birth: 2 May 1937. Specialization: Allergy, Immunology and Biochemistry Address: Lakshmi Niwas, Opp. Santoshi Mata Temple (B Cabin), Sane Guruji Path, Naupada, Thane 400 602, Maharashtra Contact: Residence: (022) 2537 6961. Mobile: 93249 24307

  3. Paranjpe, Dr Pramod Anand

    Indian Academy of Sciences (India)

    Elected: 1975 Section: Engineering & Technology. Paranjpe, Dr Pramod Anand D.Sc. Tech. (ETH Zurich). Date of birth: 1 April 1934. Specialization: Turbomachinery and Jet Propulsion Systems Address: 'Bahaar', 5, Hindustan Estate, Road No. 13, Kalyaninagar, Pune 411 006, Maharashtra Contact: Residence: (020) 2668 ...

  4. Thakur, Dr Vikram Chandra

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1991 Section: Earth & Planetary Sciences. Thakur, Dr Vikram Chandra Ph.D. (London). Date of birth: 15 January 1940. Specialization: Structural Geology, Tectonics of Himalayan Geology and Active Tectonics Address: 9/12 (Lane 9), Ashirwad Eclave, Dehra Dun 248 001, ...

  5. Gangal, Dr Sudha Gajanan

    Indian Academy of Sciences (India)

    Gangal, Dr Sudha Gajanan Ph.D. (Mumbai), FNA Council Service: 1995-97. Date of birth: 25 August 1934. Specialization: Cancer & Basic Immunology, Cell Biology and Genetic Diseases Address: 4, Mahavishnu Apartments, Dahanukar Colony A, Kothrud, Pune 411 029, Maharashtra Contact: Residence: (020) 2538 4382, ...

  6. Mishra, Dr Rakesh K

    Indian Academy of Sciences (India)

    Mishra, Dr Rakesh K Ph.D. (Allahabad), FNASc, FNA. Date of birth: 14 April 1961. Specialization: Genomics, Chromatin, Epigenetics Address: Director, Centre for Cellular & Molecular Biology, Uppal Road, Hyderabad 500 007, A.P.. Contact: Office: (040) 2719 2600. Residence: (040) 2720 6400. Mobile: 94419 02188

  7. Parnaik, Dr Veena Krishnaji

    Indian Academy of Sciences (India)

    Elected: 2008 Section: Animal Sciences. Parnaik, Dr Veena Krishnaji Ph.D. (Ohio State), FNA. Date of birth: 22 August 1953. Specialization: Cell Biology, Molecular Biology, Lamins and Nuclear Organisation Address: INSA Senior Scientist, Centre for Cellular & Molecular Biology, Uppal Road, Hyderabad 500 007, A.P.

  8. Dr. Shi Hanzhang's Experience in Treating Andropathy

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    @@ Dr. Shi Hanzhang (施汉章) of Dongzhimen Hospital affiliated to Beijing University of Traditional Chinese Medicine is experienced in both teaching and clinical practice, especially in treating andropathy, such as sexual disorder, infertility, and hyperplasia of the prostate. The author has the honour to follow him for study and really learned a lot from him. A brief introduction to Dr. Shi's way of thinking in treatment is as follows.

  9. Volume celebrating the 60th birthday of Professor Dr. Franz Fie; Professor Dr. Franz Fiedler zum 60. Geburtstag

    Energy Technology Data Exchange (ETDEWEB)

    Beheng, K.D. [ed.

    1998-01-01

    This report was compiled in honor of Professor Dr. Franz Fiedler on the occasion of his 60th birthday on 7 January 1998. Its contributions deal with mesoscale modelling, the propagation of air pollutants, measurements of precipitation using radar, and prediction models. (orig./KW) [Deutsch] Dieser Bericht wurde aus Anlass des 60. Geburtstags von Herrn Prof. Dr. Franz Fiedler am 7. Januar 1998 zusammengestellt. Die Beitraege behandeln mesoskalige Modellierung, Ausbreitung von Luftschadstoffen, Niederschlagsmessung mit Radar und Vorhersagemodelle. (orig.)

  10. Development of telerobotic systems for reactor decommissioning, (3)

    International Nuclear Information System (INIS)

    Usui, Hozumi; Fujii, Yoshio; Shinohara, Yoshikuni

    1991-01-01

    This paper describes the telerobotic system for reactor decommissioning in the scope of engineering demonstration of dismantling radioactive reactor internals of an experimental boiling water power reactor JPDR. The total system consists of a telerobotic manipulator system equipped with a multi-functional amphibious slave manipulator with a load capacity of 25 daN, a chain-driven transport system, and a computer-assisted monitoring and control system. Preceding to the application of the telerobotic system to actual dismantling operation, a mockup test was performed of dismantling the simulated reactor internals of actual-size by the method of underwater plasma arc cutting in order to study the performance of the telerobotic system in a realistic environment. The system was then successfully applied to dismantling the actual reactor internals according to the JPDR decommissioning program. (author)

  11. For Dr. Nancy Snyderman's Parents, Staying Close to Family Is Key

    Science.gov (United States)

    ... to move closer to their daughter and her family, as part of the next chapter in their lives. Photo courtesy of Dr. Nancy Snyderman As Chief Medical Editor for NBC News and host of the popular MSNBC show, Dr. Nancy , Dr. ...

  12. DR and CR: Recent advances in technology

    International Nuclear Information System (INIS)

    Schaefer-Prokop, C.M.; De Boo, D.W.; Uffmann, M.; Prokop, M.

    2009-01-01

    After some initial reluctance, nowadays transition from conventional analogue-to-digital radiographic technique is realized in the vast majority of institutions. The eventual triumph of digital over conventional technique is related to its undoubted advantages with respect to image quality and improved image handling in the context of a picture archiving and communication system. CR represents the older system, which matured over decades and experienced some important recent improvements with respect to dose efficiency and work-flow efficiency that strengthened its position. It represents a very versatile, economically attractive system that is equally suited for integrated systems as well as for cassette-based imaging at the bedside. DR systems offer superb image quality and realistic options for dose reduction based on their high dose efficiency. While for a long time only integrated systems were on the market suited for a large patient throughput, also mobile DR systems became recently available. While for the next years, it is likely that DR and CR systems will coexist, the long term perspective of CR will depend on further innovations with respect to dose efficiency and signal-to-noise characteristics while for DR economical aspects and broader availability of mobile systems will play a role.

  13. The high-temperature reactor's attractiveness lies in passive safety

    International Nuclear Information System (INIS)

    Anon.

    1987-01-01

    In the recent years the use of nuclear energy has turned from a technical and scientific issue to a political one. The high-temperature reactor (HTR) however, has always been advertised as particularly safe. The present situation and future developments of HTR-technology were the two issues that VDI-News brought up on the 27th October on an HTR-conference in an interview with the 'spiritual father' of the HTR, Prof. Dr. Rudolf Schulten of the Juelich Nuclear Research Centre. (orig.) [de

  14. Bal, Dr Dattatreya Vaman

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 1943 Section: Animal Sciences. Bal, Dr Dattatreya Vaman Ph.D. (Liverpool). Date of birth: 25 August 1905. Date of death: 1 April 1999. Specialization: Marine Zoology, Oceanography. Fisheries and Aquaculture Last known address: 104, Swaroop Complex, Karve Road, Pune 411 ...

  15. Bhawalkar, Dr Dilip Devidas

    Indian Academy of Sciences (India)

    Fellow Profile. Elected: 1986 Section: Physics. Bhawalkar, Dr Dilip Devidas Ph.D. (Southampton), FNA, FNASc. Date of birth: 16 October 1940. Specialization: Lasers and laser Instrumentation Address: 26, Paramanu Nagar, Indore 452 013, M.P.. Contact: Office: (0731) 232 2707. Residence: (0731) 232 0031. Mobile: 93032 ...

  16. Agrewala, Dr Javed Naim

    Indian Academy of Sciences (India)

    Agrewala, Dr Javed Naim Ph.D. (Agra), FNA, FNASc. Date of birth: 14 May 1961. Specialization: Immunology, Vaccine, Drug Discovery Address: Chief Scientist, Immunology Laboratory, Institute of Microbial Technology, Sector 39A, Chandigarh 160 036, U.T.. Contact: Office: (0172) 666 5261. Residence: (0172) 666 5514

  17. Barua, Dr Asok Kumar

    Indian Academy of Sciences (India)

    Elected: 1987 Section: Physics. Barua, Dr Asok Kumar Ph.D. (Calcutta). Date of birth: 1 July 1936. Specialization: Solid State Materials, Thin Film Technology and Thin Film Solar Cells Address: Honorary Emeritus Professor, Indian Institute of Engineering Science & Technology, Shibpur, Howrah 711 103, W.B.. Contact:

  18. Gurjar, Dr Mukund Keshao

    Indian Academy of Sciences (India)

    Gurjar, Dr Mukund Keshao Ph.D. (Nagpur and London), FNASc. Date of birth: 28 August 1952. Specialization: Carbohydrate Chemistry and Synthetic Organic Chemistry Address: Director, R&D, Emcure Pharmaceuticals Limited, P2, ITBT Park Phase II, Hinjwadi, Pune 411 057, Maharashtra Contact: Office: (020) 3982 1350, ...

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

    Energy Technology Data Exchange (ETDEWEB)

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

    2007-11-01

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

  20. The Effect of Different Perturbations on the Stability Analysis of Light Water Reactors

    International Nuclear Information System (INIS)

    Dykin, Victor

    2010-09-01

    Neutron noise analysis techniques are studied and developed, with primary use of determining the stability of Boiling Water Reactors (BWRs). In particular, the role of a specific perturbation prevailing in Light Water Reactors, the propagating density perturbation, in the stability of BWRs and on the noise field of LWRs in general, is investigated by considering three topics. In the first topics, we investigate how the neutronic response of the reactor, usually described as a second order system driven by a white noise driving force, is affected by a non-white driving force. This latter arises from the reactivity effect of the propagating density perturbations. The investigation is performed by using spectral and correlation analysis. Propagating perturbations with different velocities are analyzed. We investigate how the accuracy of the determination of the so-called decay ratio (DR) of the system, based on the assumption of white noise driving force, deteriorates with deviations from the white noise character of the driving force. In the second topics, the space dependence of the neutron noise, induced by propagating density perturbations, represented through the perturbation of the absorption, is determined and discussed. A full analytical solution was obtained by the use of the Green's function technique. The solution was analyzed for different frequencies and different system sizes. An interesting new interference effect between the point-kinetic and space-dependent components of the induced noise was discovered and interpreted in physical terms. In the last topics, a non-linear stability analysis of a BWR is performed, using so called Reduced Order Model (ROM) techniques. A ROM is usually constructed by reducing the full set of 3D space-time dependent neutron-kinetics, thermal-hydraulics and heat transfer equations to time-dependent ones, by considering space dependence in a lumped parameter model (one or two discrete channels). The main novelty of our work

  1. Generation of functional HLA-DR*1101 tetramers receptive for loading with pathogen or tumour derived synthetic peptides

    Directory of Open Access Journals (Sweden)

    Protti Maria

    2005-12-01

    Full Text Available Abstract Background MHC class I-peptide tetramers are currently utilised to characterize CD8+ T cell responses at single cell level. The generation and use of MHC class II tetramers to study antigen-specific CD4+ T cells appears less straightforward. Most MHC class II tetramers are produced with a homogeneously built-in peptide, reducing greatly their flexibility of use. We attempted the generation of "empty" functional HLA-DR*1101 tetramers, receptive for loading with synthetic peptides by incubation. No such reagent is in fact available for this HLA-DR allele, one of the most frequent in the Caucasian population. Results We compared soluble MHC class II-immunoglobulin fusion proteins (HLA-DR*1101-Ig with soluble MHC class II protein fused with an optimised Bir site for enzymatic biotynilation (HLA-DR*1101-Bir, both produced in insect cells. The molecules were multimerised by binding fluorochrome-protein A or fluorochrome-streptavidin, respectively. We find that HLA-DR*1101-Bir molecules are superior to the HLA-DR*1101-Ig ones both in biochemical and functional terms. HLA-DR*1101-Bir molecules can be pulsed with at least three different promiscuous peptide epitopes, derived from Tetanus Toxoid, influenza HA and the tumour associated antigen MAGE-3 respectively, to stain specific CD4+ T cells. Both staining temperature and activation state of CD4+ T cells are critical for the binding of peptide-pulsed HLA-DR*1101-Bir to the cognate TCR. Conclusion It is therefore possible to generate a soluble recombinant HLA-DR*1101 backbone that is receptive for loading with different peptides to stain specific CD4+ T cells. As shown for other HLA-DR alleles, we confirm that not all the strategies to produce soluble HLA-DR*1101 multimers are equivalent.

  2. Station Blackout Analysis for a 3-Loop Westinghouse PWR Reactor Using Trace

    International Nuclear Information System (INIS)

    El-Sahlamy, N.M.

    2017-01-01

    One of the main concerns in the area of severe accidents in nuclear reactors is that of station blackout (SBO). The loss of offsite electrical power concurrent with the unavailability of the onsite emergency alternating current (AC) power system can result in loss of decay heat removal capability, leading to a potential core damage which may lead to undesirable consequences to the public and the environment. To cope with an SBO, nuclear reactors are provided with protection systems that automatically shut down the reactor, and with safety systems to remove the core residual heat. This paper provides a best estimate assessment of the SBO scenario in a 3-loop Westinghouse PWR reactor. The evaluation is performed using TRACE, a best estimate computer code for thermal-hydraulic calculations. Two sets of scenarios for SBO analyses are discussed in the current work. The first scenario is the short term SBO where it is assumed that in addition to the loss of AC power, there is no DC power; i.e., no batteries are available. In the second scenario, a long term SBO is considered. For this scenario, DC batteries are available for four hours. The aim of the current SBO analyses for the 3-loop pressurized water reactor presented in this paper is to focus on the effect of the availability of a DC power source to delay the time to core uncovers and heatup

  3. The qualification of U3O8 as research reactor fuel

    International Nuclear Information System (INIS)

    Krull, W.

    1983-01-01

    This report summarizes the today knowledge of the qualification status of U 3 O 8 as low enriched ( 3 O 8 is so far qualified to start testing of ten (10) fuel elements with an U-density of 3.1 g U/cc in the FRG-2 research reactor. (orig.) [de

  4. Development of TRAIL Resistance by Radiation-Induced Hypermethylation of DR4 CpG Island in Recurrent Laryngeal Squamous Cell Carcinoma

    International Nuclear Information System (INIS)

    Lee, Jong Cheol; Lee, Won Hyeok; Min, Young Joo; Cha, Hee Jeong; Han, Myung Woul; Chang, Hyo Won; Kim, Sun-A; Choi, Seung-Ho; Kim, Seong Who; Kim, Sang Yoon

    2014-01-01

    Purpose: There are limited therapeutic options for patients with recurrent head and neck cancer after radiation therapy failure. To assess the use of tumor necrosis factor–related apoptosis-inducing ligand (TRAIL) as a salvage chemotherapeutic agent for recurrent cancer after radiation failure, we investigated the effect of clinically relevant cumulative irradiation on TRAIL-induced apoptosis. Methods and Materials: Using a previously established HN3 cell line from a laryngeal carcinoma patient, we generated a chronically irradiated HN3R isogenic cell line. Viability and apoptosis in HN3 and HN3R cells treated with TRAIL were analyzed with MTS and PI/annexin V-FITC assays. Western blotting and flow cytometry were used to determine the underlying mechanism of TRAIL resistance. DR4 expression was semiquantitatively scored in a tissue microarray with 107 laryngeal cancer specimens. Methylation-specific polymerase chain reaction and bisulfite sequencing for DR4 were performed for genomic DNA isolated from each cell line. Results: HN3R cells were more resistant than HN3 cells to TRAIL-induced apoptosis because of significantly reduced levels of the DR4 receptor. The DR4 staining score in 37 salvage surgical specimens after radiation failure was lower in 70 surgical specimens without radiation treatment (3.03 ± 2.75 vs 5.46 ± 3.30, respectively; P<.001). HN3R cells had a methylated DR4 CpG island that was partially demethylated by the DNA demethylating agent 5-aza-2′-deoxycytidine. Conclusion: Epigenetic silencing of the TRAIL receptor by hypermethylation of a DR4 CpG island might be an underlying mechanism for TRAIL resistance in recurrent laryngeal carcinoma treated with radiation

  5. Operation experience with the 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Islam, M.S.; Haque, M.M.; Salam, M.A.; Rahman, M.M.; Khandokar, M.R.I.; Sardar, M.A.; Saha, P.K.; Haque, A.; Malek Sonar, M.A.; Uddin, M.M.; Hossain, S.M.S.; Zulquarnain, M.A.

    2004-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities and manpower training. The reactor has been operated successfully since it's commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power under forced-convection mode remained suspended for about 4 years. During that time, the reactor was operated at a power level of 250 kW so as to carry out experiments that require lower neutron flux. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50 g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. A total of 873 irradiation requests (IRs) have been catered for different reactor uses. Out of these, 114 IRs were for radioisotope (RI) production and 759 IRs for different experiments. The total amount of RI produced stands at about 2100 GBq. The total amount of burn-up-fuel is about 6158 MWh. Efforts are on to undertake an ADP project so as to convert the analog console and I and C system of the reactor into digital one. The paper summarizes the reactor operation experiences focusing on troubleshooting, rectification, modification, RI production, various R and D

  6. Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/B-VII.0

    International Nuclear Information System (INIS)

    Khan, Jahirul Haque

    2013-01-01

    The objective of this study is to explain the main nuclear safety parameters of 3 MW TRIGA Mark-II Research Reactor at AERE, Savar, Dhaka, Bangladesh from the viewpoint of reactor safety and also reactor operator. The most important nuclear reactor physics safety parameters are power distribution, power peaking factors, shutdown margin, control rod worth, excess reactivity and fuel temperature reactivity coefficient. These parameters are calculated using the chain of the computer codes the SRAC-PIJ for cell calculation based on neutron transport theory and the SRAC-CITATION for core calculation based on neutron diffusion equation. To achieve this objective the TRIGA model is developed by the 3-D diffusion code SRAC-CITATION based on the group constants that come from the collision probability transport code SRAC-PIJ. In this study the evaluated nuclear data libraries JENDL-3.3 and ENDF/B-VII.0 are used. The calculated most important reactor physics parameters are compared to the safety analysis report (SAR) values as well as earlier published MCNP results (numerically benchmark). It was found that the calculated results show a good agreement between the said libraries. Besides, in most cases the calculated results reveal a reasonable agreement with the SAR values (by General Atomic) as well as the MCNP results. In addition, this analysis can be used as the inputs for thermal-hydraulic calculations of the TRIGA fresh core in the steady state and pulse mode operation. Because of power peaking factors, power distributions and temperature reactivity coefficients are the most important reactor safety parameters for normal operation and transient safety analysis in research as well as in power reactors. They form the basis for technical specifications and limitations for reactor operation such as loading pattern limitations for pulse operation (in TRIGA). Therefore, this analysis will be very important to develop the nuclear safety parameters data of 3 MW TRIGA Mark

  7. Overall properties of the Gaia DR1 reference frame

    Science.gov (United States)

    Liu, N.; Zhu, Z.; Liu, J.-C.; Ding, C.-Y.

    2017-03-01

    Aims: The first Gaia data release (Gaia DR1) provides 2191 ICRF2 sources with their positions in the auxiliary quasar solution and five astrometric parameters - positions, parallaxes, and proper motions - for stars in common between the Tycho-2 catalogue and Gaia in the joint Tycho-Gaia astrometric solution (TGAS). We aim to analyze the overall properties of Gaia DR1 reference frame. Methods: We compare quasar positions of the auxiliary quasar solution with ICRF2 sources using different samples and evaluate the influence on the Gaia DR1 reference frame owing to the Galactic aberration effect over the J2000.0-J2015.0 period. Then we estimate the global rotation between TGAS with Tycho-2 proper motion systems to investigate the property of the Gaia DR1 reference frame. Finally, the Galactic kinematics analysis using the K-M giant proper motions is performed to understand the property of Gaia DR1 reference frame. Results: The positional comparison between the auxiliary quasar solution and ICRF2 shows negligible orientation and validates the declination bias of -0.1mas in Gaia quasar positions with respect to ICRF2. Galactic aberration effect is thought to cause an offset 0.01mas of the Z axis direction of Gaia DR1 reference frame. The global rotation between TGAS and Tycho-2 proper motion systems, obtained by different samples, shows a much smaller value than the claimed value 0.24mas yr-1. For the Galactic kinematics analysis of the TGAS K-M giants, we find possible non-zero Galactic rotation components beyond the classical Oort constants: the rigid part ωYG = -0.38±0.15mas yr-1 and the differential part ω^primeYG = -0.29±0.19mas yr-1 around the YG axis of Galactic coordinates, which indicates possible residual rotation in Gaia DR1 reference frame or problems in the current Galactic kinematical model. Conclusions: The Gaia DR1 reference frame is well aligned to ICRF2, and the possible influence of the Galactic aberration effect should be taken into consideration

  8. Gas-cooled reactor thermal-hydraulics using CAST3M and CRONOS2 codes

    International Nuclear Information System (INIS)

    Studer, E.; Coulon, N.; Stietel, A.; Damian, F.; Golfier, H.; Raepsaet, X.

    2003-01-01

    The CEA R and D program on advanced Gas Cooled Reactors (GCR) relies on different concepts: modular High Temperature Reactor (HTR), its evolution dedicated to hydrogen production (Very High Temperature Reactor) and Gas Cooled Fast Reactors (GCFR). Some key safety questions are related to decay heat removal during potential accident. This is strongly connected to passive natural convection (including gas injection of Helium, CO 2 , Nitrogen or Argon) or forced convection using active safety systems (gas blowers, heat exchangers). To support this effort, thermal-hydraulics computer codes will be necessary tools to design, enhance the performance and ensure a high safety level of the different reactors. Accurate and efficient modeling of heat transfer by conduction, convection or thermal radiation as well as energy storage are necessary requirements to obtain a high level of confidence in the thermal-hydraulic simulations. To achieve that goal a thorough validation process has to ve conducted. CEA's CAST3M code dedicated to GCR thermal-hydraulics has been validated against different test cases: academic interaction between natural convection and thermal radiation, small scale in-house THERCE experiments and large scale High Temperature Test Reactor benchmarks such as HTTR-VC benchmark. Coupling with neutronics is also an important modeling aspect for the determination of neutronic parameters such as neutronic coefficient (Doppler, moderator,...), critical position of control rods...CEA's CAST3M and CRONOS2 computer codes allow this coupling and a first example of coupled thermal-hydraulics/neutronics calculations has been performed. Comparison with experimental data will be the next step with High Temperature Test Reactor experimental results at nominal power

  9. Nageswara Rao, Dr Gullapalli

    Indian Academy of Sciences (India)

    Nageswara Rao, Dr Gullapalli M.D. (Opthal.) (AIIMS), FAMS, FACS, FRCS, FNASc. Date of birth: 1 September 1945. Specialization: Cornea, Community Eye Health and Eye Care Policy & Planning Address: Distinguished Chair of Eye Health, LV Prasad Eye Institute, LV Prasad Marg, Banjara Hills, Hyderabad 500 034, A.P.

  10. Ghosh, Dr Pushpito Kumar

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2010 Section: Chemistry. Ghosh, Dr Pushpito Kumar Ph.D. (Princeton). Date of birth: 29 May 1954. Specialization: Processes Research, Water Purification, Renewable Energy, R&D Management Address: A-604, Punit Park, Plot No. 182/C, Sector 17, Merol, Navi Mumbai 400 706, ...

  11. Nandicoori, Dr Vinay Kumar

    Indian Academy of Sciences (India)

    Home; Fellowship. Fellow Profile. Elected: 2018 Section: General Biology. Nandicoori, Dr Vinay Kumar Ph.D. (IISc), FNASc. Date of birth: 1 March 1969. Specialization: Molecular & Cellular Biology, Cell Signalling, Cell Biology Address: National Institute of Immunology, Aruna Asaf Ali Marg, New Delhi 110 067, U.T.; Contact ...

  12. Panda, Dr Subrat Kumar

    Indian Academy of Sciences (India)

    Panda, Dr Subrat Kumar M.B.B.S. (Utkal), M.D. (Path.) (AIIMS), FNA. Date of birth: 18 November 1954. Specialization: Liver Pathology, Viral Hepatitis and Molecular Biology/Virology Address: Professor, Department of Pathology, All India Institute of Medical Sciences, Ansari Nagar, New Delhi 110 029, U.T.. Contact:

  13. Pressure loss tests for DR-BEP of fullsize 17 x 17 PWR fuel assembly

    International Nuclear Information System (INIS)

    Chung, Moon Ki; Chun, Se Young; Chang, Seok Kyu; Won, Soon Youn; Cho, Young Rho; Kim, Bok Deuk; Min, Kyoung Ho

    1993-01-01

    This report describes the conditions, procedure and results in the pressure loss tests carried out for a double grid type debris resistance bottom end piece (DR-BEP) designed by KAERI. In this test, the pressure loss coefficients of the full size 17 x 17 PWR simulated fuel assembly with DR-BET and with standard-BEP were measured respectively, and the pressure loss coefficients of DR-BEP were compared with the coefficients of STD-BET. The test conditions fall within the ranges of loop pressure from 5.2 to 45 bar, loop temperature from 27 to 221 deg C and Reynolds number in fuel bundle from 2.17 x 10 4 to 3.85 x 10 5 . (Author) 5 refs., 18 figs., 5 tabs

  14. 3-DB, 3-D Multigroup Diffusion, X-Y-Z, R-Theta-Z, Triangular-Z Geometry, Fast Reactor Burnup

    International Nuclear Information System (INIS)

    Hardie, R.W.; Little, W.W. Jr.; Mroz, W.

    1974-01-01

    1 - Description of problem or function: 3DB is a three-dimensional (x-y-z, r-theta-z, triangular-z) multigroup diffusion code for use in detailed fast-reactor criticality and burnup analysis. The code can be used to - (a) compute k eff and perform criticality searches on time absorption, reactor composition, and reactor dimensions by means of either a flux or an adjoint model, (b) compute material burnup using a flexible material shuffling scheme, and (c) compute flux distributions for an arbitrary extraneous source. 2 - Method of solution: Eigenvalues are computed by standard source- iteration techniques. Group re-balancing and successive over-relaxation with line inversion are used to accelerate convergence. Adjoint solutions are obtained by inverting the input data and redefining the source terms. Material burnup is by reactor zone. The burnup rate is determined by the zone and energy-averaged cross sections which are recomputed after each time-step. The isotopic chains, which can contain any number of isotopes are formed by the user. The code does not contain built- in or internal chains. 3 - Restrictions on the complexity of the problem: Since variable dimensioning is employed, no simple bounds can be stated

  15. A robot-automated work site for repair of the Chinon A3 reactor

    International Nuclear Information System (INIS)

    Raynal, A.

    1987-01-01

    In 1982, following degradation due to corrosion of low-carbon steel by carbon dioxide gas, the utility undertook to repair some of the support structures at Chinon A3. This involved consolidation and reinforcing thermocouples and gas monitor pipeworks supports. A welding process was selected and the use of robots became indispensable because of the large number of components to be replaced (200 per outage). Two robots, supplied with tool heads and replacement components from outside the reactor were used. The robots and their servers were coordinated by a central computer and monitored by a closed circuit television system. Each repair operation was performed after ''training'' on a full-scale mockup of the top of the reactor reconstructed from telemetry of the real reactor dimensions. Since becoming operational in June 1986, the robots have accumulated over 20 000 hours of operation and seventy parts have been welded to the reactor. A 3D CAD system has been adapted to simulate the robots and analyse long trajectories in order to reduce robot learning time [fr

  16. [Dr. Atanasije Puljo: pioneer of Serbian dentistry].

    Science.gov (United States)

    Jovananović, Svetlana; Milovanović, Srdjan; Zagradjanin, Danica; Milovanović, Nebojša; Puzović, Dragana

    2012-01-01

    This paper describes the life and work of Dr. Atanasije Puljo (1878-1944). He was a volunteer in the Balkan wars, an active participant in the First World War; he was the first who noted the importance of team-work of a dentist and a surgeon in the care of jaw and facial injuries. He established primacy in this field, as he came up with this brilliant idea three years before other colleagues. His method of treatment of the upper jaw neglected fractures, called the Balkan method, was recognized worldwide. Dr. Puljo is the pioneer of dental radiology in Serbia, founder of the Odontology Clinic of the Medical Faculty and main supporter of the establishment of the School of Dentistry. Merits of Dr. Atanasije Puljo, medical practitioner with a broad knowledge in different fields, remain within the academic institution that was founded by this pioneer of dentistry in Serbia.

  17. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99). Elle est

  18. EL3 reactor description and safety analysis report; Pile EL3, rapport descriptif et de surete

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1969-02-01

    The EL-3 reactor is an experimental pile. Heterogenous type reactor, water moderated and cooled it uses slightly enriched uranium oxide as fuel (4.5 percent) distributed in vertical cells that constitute the core (the maximum number of cells is 99). It is conceived to function at a maximal thermal power of 20 MW. It supplies a maximum thermal neutron flux of 10{sup 14} neutrons/cm{sup 2}/sec. It has several experimental devices. The EL-3 reactor is surrounded by auxiliary circuits of fluids, in a sealed containment, slightly depressed. The primary heavy water coolant circuit is completely included in this containment. Its cooling is made by the intermediary of a light water secondary circuit by atmospheric refrigerants. The ventilation circuits of the sealed containment and the reactor block do not release air outside, under nornal functioning, by a particularly studied chimney only after filtering and eventually dilution. The eventual contamination of the light water or air by active products is permanently monitored to allow the reactor shutdown and avoid the release in atmosphere of dangerous products. The EL-3 reactor, laying down in may 1955, has diverged in july 1957, made its first ascending in power in december 1957 and reached its complete power in april 1958. The positioning of actual fuel (snow crystal) was made during summer 1964. Reactor with an experimental aim, it is used for theoretical and technological studies by material irradiation in the experimental channels and the core cells, with possibilities to constitute independent loops (relative to the cooling fluids). Thirty vertical channels are devoted to the fabrication of artificial radioelements. [French] La pile EL-3 est une pile experimentale. Du type heterogene, moderee et refroidie a l'eau lourde elle utilise comme combustible de l'oxygene d'uranium faiblement enrichi (4,5 p.cent) reparti en cellules verticales qui constituent le coeur (le nombre maximal de cellules est de, 99

  19. Uranium-fuel thermal reactor benchmark testing of CENDL-3

    International Nuclear Information System (INIS)

    Liu Ping

    2001-01-01

    CENDL-3, the new version of China Evaluated Nuclear Data Library are being processed, and distributed for thermal reactor benchmark analysis recently. The processing was carried out using the NJOY nuclear data processing system. The calculations and analyses of uranium-fuel thermal assemblies TRX-1,2, BAPL-1,2,3, ZEEP-1,2,3 were done with lattice code WIMSD5A. The results were compared with the experimental results, the results of the '1986'WIMS library and the results based on ENDF/B-VI. (author)

  20. Investigations related to a one-piece removal of the reactor block in the frame of the JRR-3 reconstruction program

    International Nuclear Information System (INIS)

    Onishi, N.; Kanenari, A.; Futamura, Y.; Sakurai, H.; Suzuki, S.; Nagase, T.; Iwatani, A.; Otsubo, F.

    1987-01-01

    In the Japan Atomic Energy Research Institute (JAERI), an outdated research reactor (Japan Research Reactor No.3; JRR-3) was removed to a storage facility between October 14th and November 7th, 1986. The removal of the 2250-ton reactor block (10 x 10 x 10 m) was performed as a part of a program to replace the JRR-3's core (10-MW thermal) with an upgraded research reactor core. The heavy water and fuel elements were taken out from the JRR-3 before removal work began. The reactor block was raised about 3.7 meters, using a 12-cubic meter steel frame and a center-hole jack system. The reactor block was then transported horizontally about 34 meters on steel rails, using four 100-ton jacks, to a storage facility. Finally, the reactor block was lowered 14 meters into the storage facility. After the reactor block was stored, a new 20-MW thermal, light-water moderated and cooled JRR-3 core will be built, with criticality targeted for 1989

  1. How Dr. Pierce Promoted Himself

    Data.gov (United States)

    Department of the Interior — This article is about Dr. Raymond V Pierce who owned St. Vincent Island before it became a refuge. The doctor painted advertisements for his famous “Woman’s Tonic”...

  2. Decommissioning of the BR3 pressurized-water reactor

    International Nuclear Information System (INIS)

    Massaut, V.

    1996-01-01

    The dismantling and the decommissioning of nuclear installations at the end of their life-cycle is a new challenge to the nuclear industry. Different techniques and procedures for the dismantling of a nuclear power plant on an existing installation, the BR-3 pressurized-water reactor, are described. The scientific programme, objectives, achievements in this research area at the Belgian Nuclear Research Centre SCK-CEN for 1995 are summarized

  3. Application of RELAP5-3D code for thermal analysis of the ADS reactor core

    International Nuclear Information System (INIS)

    Fernandes, Gustavo Henrique Nazareno

    2018-01-01

    Nuclear power is essential to supply global energy demand. Therefore, in order to use nuclear fuel more efficiently, more efficient nuclear reactors technologies researches have been intensified, such as hybrid systems, composed of particle accelerators coupled into nuclear reactors. In order to add knowledge to such studies, an innovative reactor design was considered where the RELAP5-3D thermal-hydraulic analysis code was used to perform a thermal analysis of the core, either in stationary operation or in situations transitory. The addition of new kind of coolants, such as, liquid salts, among them Flibe, lead, lead-bismuth, sodium, lithium-bismuth and lithium-lead was an important advance in this version of the code, making possible to do the thermal simulation of reactors that use these types of coolants. The reactor, object of study in this work, is an innovative reactor, due to its ability to operate in association with an Accelerator Driven System (ADS), considered a predecessor system of the next generation of nuclear reactors (GEN IV). The reactor selected was the MYRRHA (Multi-purpose Hybrid Research Reactor for High tech Applications) due to the availability of data to perform the simulation. In the modeling of the reactor with the code RELAP5-3D, the core was simulated using nodules with 1, 7, 15 and 51 thermohydraulic channels and eutectic lead-bismuth (LBE) as coolant. The parameters, such as, pressure, mass flow and coolant and heat structure temperature were analyzed. In addition, the thermal behavior of the core was evaluated by varying the type of coolant (sodium) in substitution for the LBE of the original design using the model with 7 thermohydraulic channels. The results of the steady-state calculations were compared with data from the literature and the proposed models were verified certifying the ability of the RELAP5-3D code to simulate this innovative reactor. After this step, it was analysed cases of transients with loss of coolant flow

  4. Doppler transcranien au cours de la drépanocytose chez l'enfant Malagasy

    Science.gov (United States)

    Herinirina, Nicolas Fanantenana; Rajaonarison, Lova Hasina Ny Ony Narindra; Herijoelison, Andry Roussel; Rakoto, Olivat Aimée Alson; Ahmad, Ahmad

    2016-01-01

    Introduction Le doppler transcrânien est un outil efficace permettant de dépister les enfants drépanocytaires à risque d'AVC. Méthodes Nous avons réalisé une étude descriptive transversale sur des enfants Malagasy âgés entre 24 mois et 15 ans (groupe 1: 57 drépanocytaires, groupe 2: 43 témoins) afin d’évaluer le profil vélocimétrique des artères cérébrales chez les drépanocytaires. Un examen Doppler transcrânien a été réalisé avec étude des flux sanguins cérébraux chez les enfants des deux groupes. Résultats Pour les sujets drépanocytaires, la vitesse moyenne (VM) de l'artère cérébrale moyenne était de 100,9 ± 26,8 cm/s, l'indice de pulsatilité (IP) de 0,73 ± 0,20, la différence entre les artères cérébrales moyennes droite et gauche (ACMr) de 19,8 ± 21,5 cm/s, le rapport des vitesses de l'artère cérébrale antérieure/artère cérébrale moyenne (ACA/ACM) de 0,7 ± 0,2. Pour les enfants non drépanocytaires, VM: 80,6 ± 19,3 cm/s, IP: 0,79 ± 0,14, ACMr: 17 ± 20,1 cm/s, ACA/ACM: 0,8 ± 0,2. La vélocité des enfants drépanocytaires était supérieure au groupe contrôle. Les vitesses ont été corrélées avec le taux d'hémoglobine et l’âge et non pas avec le sexe et le volume globulaire moyen. Conclusion Les vitesses circulatoires cérébrales sont élevées chez les drépanocytaires que les enfants non drépanocytaires et sont influencées par le taux d'hémoglobine et l’âge. PMID:27516829

  5. Proceedings of 2. Yugoslav symposium on reactor physics, Part 3, Herceg Novi (Yugoslavia), 27-29 Sep 1966

    International Nuclear Information System (INIS)

    1966-01-01

    This Volume 3 of the Proceedings of 2. Yugoslav symposium on reactor physics includes three papers describing the following: model for spatial synthesis of automated control system of the GCR type reactor; model for analysis of hydrodynamic processes at the BHWR type reactors; mathematical model for safety analysis of heavy water power reactor

  6. Photographer: Digital Telepresence: Dr Murial Ross's Virtual Reality Application for Neuroscience

    Science.gov (United States)

    1995-01-01

    Photographer: Digital Telepresence: Dr Murial Ross's Virtual Reality Application for Neuroscience Research Biocomputation. To study human disorders of balance and space motion sickness. Shown here is a 3D reconstruction of a nerve ending in inner ear, nature's wiring of balance organs.

  7. Should pediatric patients wait for HLA-DR-matched renal transplants?

    Science.gov (United States)

    Gritsch, H A; Veale, J L; Leichtman, A B; Guidinger, M K; Magee, J C; McDonald, R A; Harmon, W E; Delmonico, F L; Ettenger, R B; Cecka, J M

    2008-10-01

    Graft survival rates from deceased donors aged 35 years or less among all primary pediatric kidney transplant recipients in the United States between 1996 and 2004 were retrospectively examined to determine the effect of HLA-DR mismatches on graft survival. Zero HLA-DR-mismatched kidneys had statistically comparable 5-year graft survival (71%), to 1-DR-mismatched kidneys (69%) and 2-DR-mismatched kidneys (71%). When compared to donors less than 35 years of age, the relative rate of allograft failure was 1.32 (p = 0.0326) for donor age greater than or equal to age 35. There was no statistical increase in the odds of developing a panel-reactive antibody (PRA) greater than 30% at the time of second waitlisting, based upon the degree of HLA-A, -B or -DR mismatch of the first transplant, nor was there a 'dose effect' when more HLA antigens were mismatched between the donor and recipient. Therefore, pediatric transplant programs should utilize the recently implemented Organ Procurement and Transplantation Network's (OPTN)allocation policy, which prioritizes pediatric recipients to receive kidneys from deceased donors less than 35 years of age, and should not turn down such kidney offers to wait for a better HLA-DR-matched kidney.

  8. Dr. David Sawyer, Mickey Mouse and Dr. David Brown attend a ceremony at Ronald McNair Middle School

    Science.gov (United States)

    1999-01-01

    Dr. David Sawyer (left), Superintendent of the Brevard County School District, Mickey Mouse, and Dr. David Brown, a NASA astronaut, attend a tribute to NASA astronaut Ronald McNair held in the gymnasium of Ronald McNair Magnet School in Cocoa, Fla. During the tribute, Walt Disney World presented a portrait of McNair to the school, which had previously been renamed for the fallen astronaut. McNair was one of a crew of seven who lost their lives during an accident following launch of the Space Shuttle Challenger in January 1986.

  9. Sirsat, Dr Satyavati Motiram

    Indian Academy of Sciences (India)

    Sirsat, Dr Satyavati Motiram Ph.D. (Mumbai). Date of birth: 7 October 1925. Date of death: 10 July 2010. Specialization: Medical Research (Cancer) & Ultrastructural Pathology and Hospice Care of the Dying Last known address: Bhagirathi Sadan, 17th Road, Khar, Mumbai 400 052. YouTube · Twitter · Facebook · Blog ...

  10. Dr. Mostafa Moin, Minister of Science, Research and Technology, Islamic Republic of Iran

    CERN Multimedia

    Patrice Loïez

    2001-01-01

    L. to. r.:Dr Henrik Foeth, Team Leader, CMS experiment; Dr Daniel Denegri, Physics Coordinator, CMS experiment; Prof. Tejinder Virdee, Deputy Spokesman, CMS experiment; Prof. Luciano Maiani, CERN Director-General (signing); Mr Jean-Marie Dufour, Head of the Legal Service, Mr Ghodratollah Habibpour Gharakol (back); Dr Abdolali Sharghi, Advisor to the Minister and Director General, Office of International Scientific Cooperation, Ministry of Science, Research and Technology; Dr Mostafa Moin, Minister of Science, Research and Technology, Islamic Republic of Iran (signing); Dr Reza Mansouri, Director, International Scientific Meetings Office, Ministry of Science, Research and Technology; H. E. Dr Ali Khorram, Extraordinary and plenipotentiary Ambassador to the United Nations in Geneva and Dr Hans F. Hoffmann, CERN Director for Technology Transfer & for Scientific Computing. _

  11. Abd-Allah, Dr. Adel-Gamil

    African Journals Online (AJOL)

    Abd-Allah, Dr. Adel-Gamil. Vol 12, No 4 (2000) - Articles CORRELATION BETWEEN UTERINE ARTERY FLOW VELOCITY WAVEFORMS AND ENDOMETRIAL HISTOPATHOLOGY IN WOMEN WITH PERIMENOPAUSAL AND POSTMENOPAUSAL BLEEDING. Details. ISSN: 1110-5607. AJOL African Journals Online.

  12. Reactor core of FBR type reactor

    International Nuclear Information System (INIS)

    Hayashi, Hideyuki; Ichimiya, Masakazu.

    1994-01-01

    A reactor core is a homogeneous reactor core divided into two regions of an inner reactor core region at the center and an outer reactor core region surrounding the outside of the inner reactor core region. In this case, the inner reactor core region has a lower plutonium enrichment degree and less amount of neutron leakage in the radial direction, and the outer reactor core region has higher plutonium enrichment degree and greater amount of neutron leakage in the radial direction. Moderator materials containing hydrogen are added only to the inner reactor core fuels in the inner reactor core region. Pins loaded with the fuels with addition of the moderator materials are inserted at a ratio of from 3 to 10% of the total number of the fuel pins. The moderator materials containing hydrogen comprise zirconium hydride, titanium hydride, or calcium hydride. With such a constitution, fluctuation of the power distribution in the radial direction along with burning is suppressed. In addition, an absolute value of the Doppler coefficient can be increased, and a temperature coefficient of coolants can be reduced. (I.N.)

  13. Hybrid Reactor Simulation and 3-D Information Display of BWR Out-of-Phase Oscillation

    International Nuclear Information System (INIS)

    Edwards, Robert; Huang, Zhengyu

    2001-01-01

    The real-time hybrid reactor simulation (HRS) capability of the Penn State TRIGA reactor has been expanded for boiling water reactor (BWR) out-of-phase behavior. During BWR out-of-phase oscillation half of the core can significantly oscillate out of phase with the other half, while the average power reported by the neutronic instrumentation may show a much lower amplitude for the oscillations. A description of the new HRS is given; three computers are employed to handle all the computations required, including real-time data processing and graph generation. BWR out-of-phase oscillation was successfully simulated. By adjusting the reactivity feedback gains from boiling channels to the TRIGA reactor and to the first harmonic mode power simulation, limit cycle can be generated with both reactor power and the simulated first harmonic power. A 3-D display of spatial power distributions of fundamental mode, first harmonic, and total powers over the reactor cross section is shown

  14. Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

    International Nuclear Information System (INIS)

    Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira

    2015-01-01

    Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

  15. Simulation of channel blockage for the IEA-R1 research reactor using RELAP/MOD 3

    Energy Technology Data Exchange (ETDEWEB)

    Oliveira, Eduardo C.F. de; Castrillo, Lazara Silveira, E-mail: ecfoliveira@hotmail.com, E-mail: lazara.castrillo@upe.br [Universidade de Pernambuco (UPE), Recife, PE (Brazil). Escola Politecnica de Pernambuco

    2015-07-01

    Research reactors have great importance in the area of nuclear technology, such as radioisotope production, research in nuclear physics, development of new technologies and staff training for reactor operation. The IEA-R1 is a Brazilian research reactor type pool, located at the IPEN (Instituto de Pesquisas Energeticas e Nucleares). In this work is simulated with computer code RELAP5 / MOD 3.3.2 gamma, the effect caused by partial and complete blockage of a channel in MTR fuel element of the IEA-R1 core, in order to analyzed the thermal hydraulic parameters on adjacent channels. (author)

  16. Superantigen and HLA-DR ligation induce phospholipase-C gamma 1 activation in class II+ T cells

    DEFF Research Database (Denmark)

    Kanner, S B; Odum, Niels; Grosmaire, L

    1992-01-01

    Bacterial enterotoxin superantigens bind directly to HLA class II molecules (HLA-DR) expressed on both APC and activated human T cells, and simultaneously bind to certain V beta chains of the TCR. In this report, we compared early T cell signaling events in human alloantigen-stimulated T cells when...... activated by HLA-DR ligation through antibody cross-linking or by direct enterotoxin superantigen binding. Both types of stimuli induced tyrosine phosphorylation of phosphatidylinositol-specific phospholipase C gamma 1 (PLC gamma 1) and an increase in intracellular calcium concentration; however......, superantigen-induced signaling was stronger than class II ligation alone. Antibody-mediated ligation of HLA-DR with CD3 resulted in augmented PLC gamma 1 activation and increased calcium mobilization, consistent with a mechanism of superantigen activity through a combination of class II and CD3/Ti signals...

  17. Advances in Reactor physics, mathematics and computation. Volume 3

    Energy Technology Data Exchange (ETDEWEB)

    1987-01-01

    These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, volume 3, are divided into sessions bearing on: - poster sessions on benchmark and codes: 35 conferences - review of status of assembly spectrum codes: 9 conferences - Numerical methods in fluid mechanics and thermal hydraulics: 16 conferences - stochastic transport and methods: 7 conferences.

  18. Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1; Simulacion de un reactor FBR con geometria hexagonal-Z usando el codigo PARCS 3.1

    Energy Technology Data Exchange (ETDEWEB)

    Reyes F, M. C.; Del Valle G, E. [IPN, Escuela Superior de Fisica y Matematicas, Av. Instituto Politecnico Nacional s/n, U.P. Adolfo Lopez Mateos, Edificio 9, Col. San Pedro Zacatenco, 07738 Mexico D. F. (Mexico); Filio L, C., E-mail: rf.melisa@gmail.com [Comision Nacional de Seguridad Nuclear y Salvaguardias, Dr. Jose Ma. Barragan No. 779, Col. Narvarte, 03020 Mexico D. F. (Mexico)

    2013-10-15

    The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S{sub 2} and P{sub 1}. Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

  19. GenoType HelicoDR test in the determination of antimicrobial resistance of Helicobacter pylori in Korea.

    Science.gov (United States)

    Lee, Jung Won; Kim, Nayoung; Nam, Ryoung Hee; Park, Ji Hyun; Choi, Yoon Jin; Kim, Jung Mogg; Kim, Joo Sung; Jung, Hyun Chae

    2014-09-01

    Antimicrobial resistance of Helicobacter pylori is most important factor in eradication success. GenoType HelicoDR test has been developed for rapid detection of antimicrobial resistance. The present study evaluated the clinical usefulness of GenoType HelicoDR test in Korea. To detect 23S rRNA for clarithromycin resistance and gyrA mutations for fluoroquinolone resistance, both DNA sequencing after minimal inhibitory test (MIC) and GenoType HelicoDR test were performed in H. pylori isolates from the gastric mucosa of 101 patients. The eradication results of clarithromycin and moxifloxacin-containing triple therapy were evaluated by the 23S rRNA and gyrA mutations. For 42 isolates with A2143G mutation by GenoType HelicoDR, 83.3% (35/42) of concordance rate was estimated with DNA sequencing method and 85.7% (36/42) for MIC test. For 43 isolates with N87K mutation by GenoType HelicoDR, 71.1% (31/43) of concordance rate was estimated with DNA sequencing and 88.4% (38/43) for MIC test. The sensitivity and specificity of GenoType HelicoDR test in determination of 23S rRNA mutation were 94.9% and 87.1%, and those of gyrA 98.2% and 80.0%. The sensitivity and specificity of GenoType HelicoDR test in determination of clarithromycin resistance based on MIC test were 55.0% and 80.0%, for fluoroquinolone 74.4% and 70.0%. GenoType HelicoDR test is useful to determine mutations responsible for clarithromycin or fluoroquinolone-containing eradication failure but has a limitation for the clinical applicability in determination of resistance.

  20. Preparations for the shipment of RA-3 reactor irradiated fuel

    International Nuclear Information System (INIS)

    Goldschmidt, Adrian; Novara, Oscar; Lafuente, Jose

    2002-01-01

    During the last quarter of 2000, in the Radioactive Waste Management Area of the Argentine National Commission of Atomic Energy (CNEA), located at Ezeiza Atomic Center (CAE), activities associated to the shipment of 207 MTR spent fuels containing high enrichment uranium were carried out within the Foreign Research Reactor/Domestic Research Reactor Receipt Program launched by the US Department of Energy (DOE). The MTR spent fuel shipped to Savannah River Site (SRS) was fabricated in Argentina with 90% enriched uranium of US origin and it was utilized in the operation of the research and radioisotope production reactor RA-3 from 1968 until 1987. After a cooling period at the reactor, the spent fuel was transferred to the Central Storage Facility (CSF) located in the waste management area of CAE for interim storage. The spent fuel (SF) inventory consisted of 166 standard assemblies (SA) and 41 control assemblies (CA). Basically, the activities performed were the fuel conditioning operations inside the storage facility (remote transference of the assemblies to the operation pool, fuel cropping, fuel re-identification, loading in transport baskets, etc.) conducted by CNEA. The loading of the filled baskets in the transport casks (NAC-LWT) by means of intermediate transfer systems and loaded casks final preparations were conducted by NAC personnel (DOE's contractor) with the support of CNEA personnel. (author)

  1. Researcher Profile: An Interview With Dr. Rebecca J. Travnichek

    Directory of Open Access Journals (Sweden)

    Rebecca J. Travnichek

    2011-04-01

    Full Text Available

    Dr. Rebecca Travnichek is a Family Financial Education Specialist with University of Missouri Extension. Dr. Travnichek currently serves as the Annual Conference Program Chair. She is also very active in the Association for Financial Counseling and Planning Education, where she serves on the Board of Directors. Dr. Travnichek has participated in leadership development programs at the state and national levels. She was involved in the initial proposal development of the Financial Security for All Community of Practice with eXtension and continues to be involved through several roles. She is active in the National Extension Association of Family and Consumer Sciences at the national and state levels, serving in multiple leadership roles. For the past three years, Dr. Travnichek has also served as the Editor of the Journal of the National Extension Association of Family and Consumer Sciences. She represents the type of person who makes the Financial Therapy Association a dynamic organization linking practitioners and academicians.

  2. The research contributions of Dr. Paul Van Deusen

    Science.gov (United States)

    Thomas B. Lynch; Francis A. Roesch; John Paul McTague; Jeffrey H. Gove; Gregory A. Reams; Aaron R. Weiskittel

    2015-01-01

    Dr. Paul Van Deusen’s recent passing concluded a rich 30+-year research career dedicated to development and implementation of quantitative methods for forestry and natural resources. Since the early part of his career as a biometrician with the USDA Forest Service Southern Research Station in the 1980s-1990s and continuing with his later employment at NCASI, Dr. Van...

  3. Principles of plastic surgery portrayed by the professional life of Dr John Peter Mettauer.

    Science.gov (United States)

    Avashia, Yash J; Thaller, Seth R

    2011-11-01

    Regarded as "America's first plastic surgeon," Dr John Peter Mettauer's professional life displays 3 fundamental keystones of plastic surgery: education, innovation, and practice. To fully appreciate the history of our plastic surgery, one must look beyond a purely factual recount of noteworthy actions performed decades ago. Fundamental principles that governed achievements of our predecessors remain applicable even today. Dr Mettauer thrived as a medical student under the influence of distinguished professors in medicine at the University of Pennsylvania. Later, he continued to propagate their basic tenets when he established his medical institute in 1837. Throughout his life, Dr Mettauer combined ingenuity with scientific inquiry to devise numerous unprecedented surgical techniques and instruments. He was a prolific writer and exquisitely documented his work in medical journals for the benefit of both contemporary and future surgeons. One of Dr Mettauer's momentous achievements in plastic surgery that displays his remarkable capabilities was his contributions to management of both simple and complicated cases of cleft palate. He was the first to describe relaxing lateral incisions for treating complete cleft palates and, incidentally, was the first to successfully treat this in America. He invariably replicated similar success in establishing techniques for treating a wide range of anatomic deformities. Cumulatively, Dr Mettauer's lifelong commitment and diligence have truly laid a foundation for the eventual progress and success in the field of plastic surgery.

  4. Design and implementation of the control system for the new console of TRIGA-3-Salazar Reactor

    International Nuclear Information System (INIS)

    Gonzalez M, J.L.

    1994-01-01

    TRIGA-3-Salazar Reactor was set in operation in 1968 and the aging of its components has cause the increasing in the maintenance. In the presence of this, it becomes necessary to replace the reactor console using new technologies, considering the incorporation of a personal computer. The aim of this work is the design and construction of the equipment interfaces as well as the digital computer program for the automation and control of the TRIGA-3-Salazar Reactor by means of a personal computer. (Author)

  5. On the major DYN3D developments for fast reactor design and transient analysis

    International Nuclear Information System (INIS)

    Merk, B.; Kliem, S.

    2013-01-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  6. On the major DYN3D developments for fast reactor design and transient analysis

    Energy Technology Data Exchange (ETDEWEB)

    Merk, B.; Kliem, S. [Helmholtz-Zentrum Dresden-Rossendorf e.V., Dresden (Germany). Reactor Safety Div.

    2013-07-01

    Due to the French project ASTRID, the European CP-ESFR project, and the MYRRHA/FASTEF project, the research work on fast reactors has got a new push in Europe. Additionally to this European projects a strong project is growing in Russia based on the lead cooled fast reactor design BREST. Following this trend, the Institute of Resource Ecology at the Helmholtz-Zentrum Dresden-Rossendorf has decided to start several projects dedicated to fast reactor technology, among them the extension of the well validated LWR core simulator DYN3D. The new developments, first validation results, and the next strategic steps for the adaption of the code for the improved simulation of fast reactor cores are presented. (orig.)

  7. Show: Dr. H, the life and death of pancakes

    CERN Multimedia

    2012-01-01

    Dr. H, the life and death of pancakes, a comic theatrical creation, written and performed by Heiko Buchholz.   Monday 2 April 2012 in German Tuesday 3 April 2012 in English Wednesday 4 April 2012 in French 8:30 p.m. at the Globe of Science and Innovation. This production takes a comic look at scientific methods, as applied to a common object: the pancake. More specifically, Dr H. regales his audience with statistics, experiments and scientific data surrounding this egg-and-milk-based culinary delight. And although these zany sketches are nothing short of absurd, the audience is drawn in more often than you might expect… and taken on quite an unexpected journey into the behavioural disorders, personality quirks and psychoanalysis of the base pancake. This show playfully mocks scientific logic and discourse, forcing the audience to reflect on their gullibility in the face of science and its impenetrable jargon. It purports to be neither explanation nor illustration of scientific fact,...

  8. Calculation of low-energy reactor neutrino spectra reactor for reactor neutrino experiments

    Energy Technology Data Exchange (ETDEWEB)

    Riyana, Eka Sapta; Suda, Shoya; Ishibashi, Kenji; Matsuura, Hideaki [Dept. of Applied Quantum Physics and Nuclear Engineering, Kyushu University, Kyushu (Japan); Katakura, Junichi [Dept. of Nuclear System Safety Engineering, Nagaoka University of Technology, Nagaoka (Japan)

    2016-06-15

    Nuclear reactors produce a great number of antielectron neutrinos mainly from beta-decay chains of fission products. Such neutrinos have energies mostly in MeV range. We are interested in neutrinos in a region of keV, since they may take part in special weak interactions. We calculate reactor antineutrino spectra especially in the low energy region. In this work we present neutrino spectrum from a typical pressurized water reactor (PWR) reactor core. To calculate neutrino spectra, we need information about all generated nuclides that emit neutrinos. They are mainly fission fragments, reaction products and trans-uranium nuclides that undergo negative beta decay. Information in relation to trans-uranium nuclide compositions and its evolution in time (burn-up process) were provided by a reactor code MVP-BURN. We used typical PWR parameter input for MVP-BURN code and assumed the reactor to be operated continuously for 1 year (12 months) in a steady thermal power (3.4 GWth). The PWR has three fuel compositions of 2.0, 3.5 and 4.1 wt% {sup 235}U contents. For preliminary calculation we adopted a standard burn-up chain model provided by MVP-BURN. The chain model treated 21 heavy nuclides and 50 fission products. The MVB-BURN code utilized JENDL 3.3 as nuclear data library. We confirm that the antielectron neutrino flux in the low energy region increases with burn-up of nuclear fuel. The antielectron-neutrino spectrum in low energy region is influenced by beta emitter nuclides with low Q value in beta decay (e.g. {sup 241}Pu) which is influenced by burp-up level: Low energy antielectron-neutrino spectra or emission rates increase when beta emitters with low Q value in beta decay accumulate. Our result shows the flux of low energy reactor neutrinos increases with burn-up of nuclear fuel.

  9. [Dr. Valdimir Jakovljević--his contribution to the art of surgery].

    Science.gov (United States)

    Ilić, M

    1992-01-01

    In this article we present biographical data of Dr Vladimir Jakovljević, a surgeon (1893-1960), and his contribution to the technical approach to cephalic duodenopancreatectomy: the first pancreatico-jejunostomy, and first reported in world's literature triple different anastomosis of the jejunum with part of the stomach (after a 2/3 resection of the organ), choledochus and a part of the head of the pancreas, done by Vladimir Jakovljević in 1934, and published in "Medicinski pregled" (Medical Review) in 1935. A basic surgical teaching of Dr Jakovljević school of surgery is an aspiration toward the "physiological surgery", a technical viability for performing the most difficult operation on the biliary tract, a strong surgical imagination and full information about contemporary knowledge on surgery.

  10. RA reactor exploitation, task 3.08/01; Zadatak 3.08/01 - Eksploatacija reaktora RA

    Energy Technology Data Exchange (ETDEWEB)

    Zecevic, V [Institute of Nuclear Sciences Boris Kidric, Reaktor RA, Vinca, Beograd (Serbia and Montenegro)

    1963-12-15

    During 1963 the RA reactor was operated for 1852 hours at mean power of 5.7 MW (total power production was 10716 MWh). Reactor was used for irradiation according to the demand of 356 users, and 15 experiments. The reason for decreased operation in comparison with the previous year was repair of all the reactor equipment and decontamination of the heavy water system. This report contains detailed data about reactor power, reactivity changes and fuel burnup. Mean monthly usage of the reactor experimental channels as well as samples which were irradiated are part of this report.

  11. China's Investment Leade Dr, Alyce Su

    Institute of Scientific and Technical Information of China (English)

    2010-01-01

    @@ I. Professional Background Dr. Alyce Su specializes in investment managemeng, managing portfolios consisted of investment opportunities originated from China's growth and internationalization, both'outbound and inbound.

  12. Operating reactors licensing actions summary. Vol. 3, No. 6

    International Nuclear Information System (INIS)

    1983-07-01

    The operating reactors licensing actions summary is designed to provide the management of the Nuclear Regulatory Commission (NRC) with an overview of licensing actions dealing with operating power and nonpower reactors. These reports utilize data collected from the Division of Licensing in the Office of Nuclear Reactor Regulation and are prepared by the Office of Management and Program Analysis. This summary report is published primarily for internal NRC use in managing the operating reactors licensing actions program. Its content will change based on NRC management informational requirements

  13. Study of seismic responses of Candu-3 reactor building using isolator bearings

    International Nuclear Information System (INIS)

    Biswas, J.K.

    1992-01-01

    Seismic isolator bearings are known to increase reliability, reduce cost and increase the potential sitings for nuclear power plants located in regions of high seismicity. High seismic activities in Canada occur mainly in the western coast, the Grand Banks and regions of Quebec along the St. Lawrence river. In Canada, nuclear power plants are located in Ontario, Quebec and New Brunswick where the seismicity levels are low to moderate. Consequently, seismic isolator bearings have not been used in the existing nuclear power plants in Canada. The present paper examines the effect of using seismic isolator bearings in the design for the new CANDU3 which would be suitable for regions having high seismicity. The CANDU3 Nuclear Power Plant is rated at 450 MW of net output power and is a smaller version of its predecessor CANDU6 successfully operating in Canada and abroad. The design of CANDU3 is being developed by AECL CANDU. Advanced technologies for design, construction and plant operation have been utilized. During the conceptual development of the CANDU3 design, various design options including the use of isolator bearings were considered. The present paper presents an overview of seismic isolation technology and summarizes the analytical work for predicting the seismic behavior of the CANDU3 reactor building. A lumped-parameter dynamic model for the reactor building is used for the analysis. The characteristics of the bearings are utilized in the analysis work. The time-history modal analysis has been used to compute the seismic responses. Seismic responses of the reactor building with and without isolator bearings are compared. The isolator bearings are found to reduce the accelerations of the reactor building. As a result, a lower level of seismic qualification for components and systems would be required. The use of these bearings however increases rigid body seismic displacements of the structure requiring special considerations in the layout and interfaces for

  14. TU Electric reactor physics model verification: Power reactor benchmark

    International Nuclear Information System (INIS)

    Willingham, C.E.; Killgore, M.R.

    1988-01-01

    Power reactor benchmark calculations using the advanced code package CASMO-3/SIMULATE-3 have been performed for six cycles of Prairie Island Unit 1. The reload fuel designs for the selected cycles included gadolinia as a burnable absorber, natural uranium axial blankets and increased water-to-fuel ratio. The calculated results for both startup reactor physics tests (boron endpoints, control rod worths, and isothermal temperature coefficients) and full power depletion results were compared to measured plant data. These comparisons show that the TU Electric reactor physics models accurately predict important measured parameters for power reactors

  15. Reactor Dosimetry Applications Using RAPTOR-M3G:. a New Parallel 3-D Radiation Transport Code

    Science.gov (United States)

    Longoni, Gianluca; Anderson, Stanwood L.

    2009-08-01

    The numerical solution of the Linearized Boltzmann Equation (LBE) via the Discrete Ordinates method (SN) requires extensive computational resources for large 3-D neutron and gamma transport applications due to the concurrent discretization of the angular, spatial, and energy domains. This paper will discuss the development RAPTOR-M3G (RApid Parallel Transport Of Radiation - Multiple 3D Geometries), a new 3-D parallel radiation transport code, and its application to the calculation of ex-vessel neutron dosimetry responses in the cavity of a commercial 2-loop Pressurized Water Reactor (PWR). RAPTOR-M3G is based domain decomposition algorithms, where the spatial and angular domains are allocated and processed on multi-processor computer architectures. As compared to traditional single-processor applications, this approach reduces the computational load as well as the memory requirement per processor, yielding an efficient solution methodology for large 3-D problems. Measured neutron dosimetry responses in the reactor cavity air gap will be compared to the RAPTOR-M3G predictions. This paper is organized as follows: Section 1 discusses the RAPTOR-M3G methodology; Section 2 describes the 2-loop PWR model and the numerical results obtained. Section 3 addresses the parallel performance of the code, and Section 4 concludes this paper with final remarks and future work.

  16. Treating Cataracts: Dr. Rachel Bishop's Top Tips for Your Eyes

    Science.gov (United States)

    ... please turn JavaScript on. Feature: Treating Cataracts Dr. Rachel Bishop's Top Tips for Your Eyes Past Issues / ... exams, a healthy lifestyle, and eye protection. Dr. Rachel Bishop, chief of consult services at the National ...

  17. Research on intelligent monitor for 3D power distribution of reactor core

    International Nuclear Information System (INIS)

    Xia, Hong; Li, Bin; Liu, Jianxin

    2014-01-01

    Highlights: • Core power distribution of ex-core measurement system has been reconstructed. • Building up an artificial intelligence model for 3-D core power distribution. • Error of the experiments has been reduced to 0.76%. • Methods for improving the accuracy of the model have been obtained. - Abstract: A real-time monitor for 3D reactor power distribution is critical for nuclear safety and high efficiency of NPP’s operation as well as for optimizing the control system, especially when the nuclear power plant (NPP) works at a certain power level or it works in load following operation. This paper was based on analyzing the monitor for 3D reactor power distribution technologies used in modern NPPs. Furthermore, considering the latest research outcomes, the paper proposed a method based on using an ex-core neutron detector system and a neural network to set up a real time monitor system for reactor’s 3D power distribution supervision. The results of the experiments performed on a reactor simulation machine illustrated that the new monitor system worked very well for a certain burn-up range during the fuel cycle. In addition, this new model could reduce the errors associated with the fitting of the distribution effectively, and several optimization methods were also obtained to improve the accuracy of the simulation model

  18. Remaining Sites Verification Package for 132-DR-1, 1608-DR Effluent Pumping Station. Attachment to Waste Site Reclassification Form 2005-035

    International Nuclear Information System (INIS)

    Carlson, R.A.

    2005-01-01

    Radiological characterization, decommissioning and demolition of the 132-DR-1 site, 1608-DR Effluent Pumping Station was performed in 1987. The current site conditions achieve the remedial action objectives and the corresponding remedial action goals established in the Remaining Sites ROD. Residual concentrations support future land uses that can be represented by a rural-residential scenario and pose no threat to groundwater or the Columbia River based on RESRAD modeling

  19. Sproglige drømmerier

    DEFF Research Database (Denmark)

    Farø, Ken Joensen

    2015-01-01

    blev tidligere brugt i Danmarks Radio som pausesignal, afspillet på en spilledåse. Ak ja, det var dengang. Gå ind på nettet og lyt til den, hvis du ikke kender melodien. Det er national kulturarv. Mange bevingede ord indeholder en form af ”drøm(me)”, fx Martin Luther Kings ”I have a Dream”. Eller...

  20. Effect of 3-D moderator flow configurations on the reactivity of CANDU nuclear reactors

    International Nuclear Information System (INIS)

    Zadeh, Foad Mehdi; Etienne, Stephane; Chambon, Richard; Marleau, Guy; Teyssedou, Alberto

    2017-01-01

    Highlights: • 3-D CFD simulations of CANDU-6 moderator flows are presented. • A thermal-hydraulic code using thermal physical fluid properties is used. • The numerical approach and convergence is validated against available data. • Flow configurations are correlated using Richardson’s number. • The interaction between moderator temperatures with reactivity is determined. - Abstract: The reactivity of nuclear reactors can be affected by thermal conditions prevailing within the moderator. In CANDU reactors, the moderator and the coolant are mechanically separated but not necessarily thermally isolated. Hence, any variation of moderator flow properties may change the reactivity. Until now, nuclear reactor calculations have been performed by assuming uniform moderator flow temperature distribution. However, CFD simulations have predicted large time dependent flow fluctuations taking place inside the calandria, which can bring about local temperature variations that can exceed 50 °C. This paper presents robust CANDU 3-D CFD moderator simulations coupled to neutronic calculations. The proposed methodology makes it possible to study not only different moderator flow configurations but also their effects on the reactor reactivity coefficient.

  1. Dr. Praveen Chaudhari named director of Brookhaven National Laboratory

    CERN Multimedia

    2003-01-01

    "Brookhaven Science Associates announced today the selection of Dr. Praveen Chaudhari as Director of the U.S. Department of Energy's Brookhaven National Laboratory. Dr. Chaudhari, who will begin his new duties on April 1, joins Brookhaven Lab after 36 years of distinguished service at IBM as a scientist and senior manager of research" (1 page).

  2. G2 and G3 reactors design; Description des reacteurs G2 et G3

    Energy Technology Data Exchange (ETDEWEB)

    Herreng,; Ertaud,; Pasquet, [Societe Alsacienne de Constructions Mecaniques (France)

    1958-07-01

    'FRANCE ATOME' Manufacturers Party has been entrusted with the G2 and G3 reactors engineering by the french A.E.C., for the first-five-year french project. Although these reactors are essentially plutonium generators, everyone has been linked with a power station which is supposed to supply with 40 MW, 'Electricite de France' has taken the liability upon itself. The reactor core includes most of G1 reactor parts (central gap excluded): horizontal channels, graphite parallelepipedic bricks stacking, steel thermal shield. The cooling is provided with CO{sub 2} under a 15 atmospheres pressure. This pressure is kept steady in a press-stressed concrete packing-case which is a cylinder horizontally shaped. Steel strips tightened encircle the concrete cylinder; itself protected by sole-plates. The cylinder bottom has brought about unusual problems which have been solved by the choice of an hemispheric shape. Packing-case tightness is provided by a 30 mm iron-plate connected with the inner wall of concrete. One of the reactor's special characteristics is the possibility of loading and unloading while operating. On loading side, barrel locks, each weighting 50 tons, allow new cans, at a pressure of 15 atmospheres, to pass. The cans process almost in a steady way through the channel, and finally drop down through bent spouts, then through spiral toboggans into a new lock. The cooling CO{sub 2} flow is provided with 3 turbo-bellows, these are actuated by average pressure-steam, obtained from exchangers. Every reactor supplies 4 exchangers which have been very difficult to build and to set up. The secondary cycle is standard and contains 3 stages (pressure 10,3: 2 and 0,5 kg/cm{sup 2}). Steam can be condensed in the event of a group turbo-generator stopping, with no modifion for the normal operating conditions of the reactor. Auxiliary circuits have to assure the continuous purifying of cooling CO{sub 2}, its storage and drain. 49 boron carbide rods are used to control the

  3. Murty, Dr Thutupalli Gopala Krishna

    Indian Academy of Sciences (India)

    Elected: 2002 Section: Engineering & Technology. Murty, Dr Thutupalli Gopala Krishna Ph.D. (Adelaide). Date of birth: 11 February 1944. Specialization: Optical Engineering, Thin Film Technology, Electro-Optical Instrumentation and Atmospheric Science Technologies Address: 848, 8th B Main, 17th Cross, ISRO Layout, ...

  4. Profile of Nasopharyngeal Carcinoma in Dr. Cipto Mangunkusumo National Hospital, 2010

    Directory of Open Access Journals (Sweden)

    Vito F. Jayalie

    2017-01-01

    Full Text Available Nasopharyngeal carcinoma (NPC is the most common head and neck malignancy in Indonesia. NPCpresents numerous challenges from non-specific signs and symptoms until lack of awareness from generalpractitioners (GP, which lead to late or missed diagnosis. Early diagnosis and prevention are proposedas the best solutions for this problem. In order to do that, we need a complete and well-managed patients’data. This study aims to reveal the demographic, clinical and histopathologic characteristics of NPC inIndonesia. A cross-sectional study was conducted by collecting medical records of all NPC patients in 2010from Otorhinolaryngology Department of Dr. Cipto Mangunkusumo National Hospital. The extracted datawere then analyzed to describe the problem of NPC in Indonesia. Out of 167 patients, 68.3% of the patientsare male and most of them are Sundanese and Javanese. Palpable lump in the neck is the most commoncomplaint in presentation (58.1%, followed by nasal congestion (49.1%. Salted fish consumption was themost prevalent risk factor (29.9%. Based on the histopathologic findings, 75.4% of the cases were classifiedas WHO-3 and around half of the patients (51% were in stage IV upon diagnosis. Studying demographic andclinical characteristics of NPC patients is the first step to overcome problems caused by NPC in Indonesia. Keywords: head and neck cancer, nasopharyngeal carcinoma, epidemiology  Profil Karsinoma Nasofaring di RSUPN Dr. Cipto Mangunkusumo, 2010 Abstrak Karsinoma nasofaring (KNF merupakan keganasan kepala leher yang paling sering di Indonesia.Tanda dan gejala KNF tidak spesifik dan dokter umum kurang waspada sehingga diagnosis terlambat ataugagal. Untuk mengatasi hal tersebut, diperlukan upaya pencegahan dan deteksi dini yang didasari profil KNF.Studi ini bertujuan untuk mengetahui gambaran demografi, gejala klinis dan karakteristik histopatologi pasienKNF di RSUPN Dr. Cipto Mangunkusumo. Penelitian menggunakan desain potong lintang dengan

  5. 3. International conference on catalysis in membrane reactors

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1998-09-01

    The 3. International Conference on Catalysis in Membrane Reactors, Copenhagen, Denmark, is a continuation of the previous conferences held in Villeurbanne 1994 and Moscow 1996 and will deal with the rapid developments taking place within membranes with emphasis on membrane catalysis. The approx. 80 contributions in form of plenary lectures and posters discuss hydrogen production, methane reforming into syngas, selectivity and specificity of various membranes etc. The conference is organised by the Danish Catalytic Society under the Danish Society for Chemical Engineering. (EG)

  6. Thermal-hydraulic modelling of the SAFARI-1 research reactor using RELAP/SCDAPSIM/MOD3.4

    International Nuclear Information System (INIS)

    Sekhri, Abdelkrim; Graham, Andy; D'Arcy, Alan; Oliver, Melissa

    2008-01-01

    The SAFARI-1 reactor is a tank-in-pool MTR type research reactor operated at a nominal core power of 20 MW. It operates exclusively in the single phase liquid water regime with nominal water and fuel temperatures not exceeding 100 deg. C. RELAP/SCDAPSIM/MOD3.4 is a Best Estimate Code for light water reactors as well as for low pressure transients, as part of the code validation was done against low pressure facilities and research reactor experimental data. The code was used to simulate SAFARI-1 in normal and abnormal operation and validated against the experimental data in the plant and was used extensively in the upgrading of the Safety Analysis Report (SAR) of the reactor. The focus of the following study is the safety analysis of the SAFARI-1 research reactor and describes the thermal hydraulic modelling and analysis approach. Particular emphasis is placed on the modelling detail, the application of the no-boiling rule and predicting the Onset of Nucleate Boiling and Departure from Nucleate Boiling under Loss of Flow conditions. Such an event leads the reactor to switch to a natural convection regime which is an adequate mode to maintain the clad and fuel temperature within the safety margin. It is shown that the RELAP/SCDAPSIM/MOD3.4 model can provide accurate predictions as long as the clad temperature remains below the onset of nucleate boiling temperature and the DNB ratio is greater than 2. The results are very encouraging and the model is shown to be appropriate for the analysis of SAFARI-1 research reactor. (authors)

  7. HLA class II variation in the Gila River Indian Community of Arizona: alleles, haplotypes, and a high frequency epitope at the HLA-DR locus.

    Science.gov (United States)

    Williams, R C; McAuley, J E

    1992-01-01

    A genetic distribution for the HLA class II loci is described for 349 "full-blooded" Pima and Tohono O'odham Indians (Pimans) in the Gila River Indian Community. A high frequency epitope in the *DRw52 family was defined by reactions with 31 alloantisera, which we have designated *DR3X6. It segregates as a codominant allele at HLA-DR with alleles *DR2, *DR4, and *DRw8, and has the highest frequency yet reported for an HLA-DR specificity, 0.735. It forms a common haplotype with *DRw52 and *DQw3 that is a valuable marker for genetic admixture and anthropological studies. Phenotype and allele frequencies, and haplotype frequencies for two and three loci, are presented. Variation at these loci is highly restricted, the mean heterozygosity for HLA-DR and HLA-DQ being 0.361. The Pimans represent a contemporary model for the Paleo-Indians who first entered North America 20,000 to 40,000 years ago.

  8. A structural study of the interaction between the Dr haemagglutinin DraE and derivatives of chloramphenicol

    International Nuclear Information System (INIS)

    Pettigrew, David M.; Roversi, Pietro; Davies, Stephen G.; Russell, Angela J.; Lea, Susan M.

    2009-01-01

    The structures of two Dr adhesin (DraE) complexes with chloramphenicol derivatives, namely chloramphenicol succinate and bromamphenicol, have been solved. The structures reveal important functional groups for small-molecule binding and imply possible modifications to the molecule that would permit a more wide-ranging interaction without the toxic side effects associated with chloramphenicol. Dr adhesins are expressed on the surface of uropathogenic and diffusely adherent strains of Escherichia coli. The major adhesin subunit (DraE/AfaE) of these organelles mediates attachment of the bacterium to the surface of the host cell and possibly intracellular invasion through its recognition of the complement regulator decay-accelerating factor (DAF) and/or members of the carcinoembryonic antigen (CEA) family. The adhesin subunit of the Dr haemagglutinin, a Dr-family member, additionally binds type IV collagen and is inhibited in all its receptor interactions by the antibiotic chloramphenicol (CLM). In this study, previous structural work is built upon by reporting the X-ray structures of DraE bound to two chloramphenicol derivatives: chloramphenicol succinate (CLS) and bromamphenicol (BRM). The CLS structure demonstrates that acylation of the 3-hydroxyl group of CLM with succinyl does not significantly perturb the mode of binding, while the BRM structure implies that the binding pocket is able to accommodate bulkier substituents on the N-acyl group. It is concluded that modifications of the 3@@hydroxyl group would generate a potent Dr haemagglutinin inhibitor that would not cause the toxic side effects that are associated with the normal bacteriostatic activity of CLM

  9. Application of Raptor-M3G to reactor dosimetry problems on massively parallel architectures - 026

    International Nuclear Information System (INIS)

    Longoni, G.

    2010-01-01

    The solution of complex 3-D radiation transport problems requires significant resources both in terms of computation time and memory availability. Therefore, parallel algorithms and multi-processor architectures are required to solve efficiently large 3-D radiation transport problems. This paper presents the application of RAPTOR-M3G (Rapid Parallel Transport Of Radiation - Multiple 3D Geometries) to reactor dosimetry problems. RAPTOR-M3G is a newly developed parallel computer code designed to solve the discrete ordinates (SN) equations on multi-processor computer architectures. This paper presents the results for a reactor dosimetry problem using a 3-D model of a commercial 2-loop pressurized water reactor (PWR). The accuracy and performance of RAPTOR-M3G will be analyzed and the numerical results obtained from the calculation will be compared directly to measurements of the neutron field in the reactor cavity air gap. The parallel performance of RAPTOR-M3G on massively parallel architectures, where the number of computing nodes is in the order of hundreds, will be analyzed up to four hundred processors. The performance results will be presented based on two supercomputing architectures: the POPLE supercomputer operated by the Pittsburgh Supercomputing Center and the Westinghouse computer cluster. The Westinghouse computer cluster is equipped with a standard Ethernet network connection and an InfiniBand R interconnects capable of a bandwidth in excess of 20 GBit/sec. Therefore, the impact of the network architecture on RAPTOR-M3G performance will be analyzed as well. (authors)

  10. Faktor-Faktor Yang Mempengaruhi Kejadian Insomnia di Poliklinik Saraf RS DR. M. Djamil Padang

    Directory of Open Access Journals (Sweden)

    Lydia Susanti

    2015-09-01

    Full Text Available Abstrak Faktor risiko seperti usia lanjut, jenis kelamin wanita, penyakit penyerta (depresi dan penyakit lain, status sosial ekonomi rendah menyebabkan insomnia. Penelitian mengenai prevalensi dan faktor-faktor yang mempengaruhi kejadian insomnia di Poliklinik Saraf RS DR. M. Djamil Padang belum pernah dilakukan. Tujuan penelitian ini adalah menentukan faktor-faktor yang mempengaruhi terjadinya insomnia di poliklinik saraf RS DR. M. Djamil Padang. Penelitian ini merupakan penelitian cross sectional. Jumlah sampel dihitung menggunakan rumus yang dikembangkan oleh Snedecor & Cochran dan didapatkan jumlah sampel 100 orang. Pengambilan sampel dilakukan secara acakdimana pasien yang memenuhi kriteria inklusi langsung menjadi sampel penelitian. Pengambilan data menggunakan kuesioner dan beberapa skala, Insomnia Severity Index, dan Beck depression inventory scale. Data dikumpulkan dari t 1 Juli sampai 31 Agustus 2013. Data ditampilkan dalam bentuk tabel distribusi frekuensi dan dilakukan analisis bivariatdan multivariat.  Kejadian Insomnia dialami oleh 38% (38 orang pasien yang berkunjung ke poliklinik saraf RS DR. M.Djamil Padang dengan jenis kelamin terbanyak pada wanita 24(45,3% dan pada kelompok umur  61-70 tahun (3,3%. Insomnia berhubungan dengan depresi (p= 0,00 dan tidak berhubungan dengan umur (p=0,472, jenis kelamin (p=0,111, status ekonomi (p=0,075, riwayat insomnia di keluarga (p=0,197. Depresi (p=0,00; OR=9,20 dan nyeri  kronik (p=0,031; OR=4.253 merupakan faktor yang dominan berhubungan dengan kejadian Insomnia. Kata Kunci: insomnia, tidur, insomnia severity index, beck depression inventory scaleAbstract A number of risk factors such as advanced age, female gender, co-morbidities (such as depression and other diseases, low socioeconomic status causes insomnia. Research on the frequency of insomnia in DR. M. Djamil hospital Padang has never been done. The objective of this study was to determine the factors that influence the incidence

  11. The design of a fuel element for the RA-3 reactor (Ezeiza Atomic Center)

    International Nuclear Information System (INIS)

    Agueda, Horacio C.; Estevez, Esteban; Gerding, Jose R.; Markiewicz, Mario E.

    2003-01-01

    Some features of the mechanical design of the low enrichment fuel element for the RA-3 reactor are described, with emphasis in those aspects of the original design that have been modified considering the experience acquired in the design of other fuel elements. The proposed modification is based fundamentally on the replacement of all welded joints by screwed joints, which facilitates the manufacture of the fuel element, avoiding the distortions produced by the welds used at present and contributing to the fulfillment of the foreseen tolerances. A basic characteristic of this design is a careful manufacture of the fuel element's structural components in order to assure an assembling of the fuel element that fulfills the tolerances intrinsically required. The fuel is designed for the RA-3 reactor and uses U 3 O 8 or U 3 Si 2 as carrying phase of the fissile material with an enrichment of 19.70% of 235 U. The design verification was performed by analytical and numerical methods, and is supported by testing of materials in laboratory, hydrodynamics tests and performance evaluations of the fuel elements in the RA-3 reactor. (author)

  12. Technical report on implementation of reactor internal 3D modeling and visual database system

    International Nuclear Information System (INIS)

    Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun

    1996-06-01

    In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation's integrated computer aided engineering system, such as Mitsubishi's NUWINGS (Japan), AECL's CANDID (Canada) and Duke Power's PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new

  13. Technical report on implementation of reactor internal 3D modeling and visual database system

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yeun Seung; Eom, Young Sam; Lee, Suk Hee; Ryu, Seung Hyun [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

    1996-06-01

    In this report was described a prototype of reactor internal 3D modeling and VDB system for NSSS design quality improvement. For improving NSSS design quality several cases of the nuclear developed nation`s integrated computer aided engineering system, such as Mitsubishi`s NUWINGS (Japan), AECL`s CANDID (Canada) and Duke Power`s PASCE (USA) were studied. On the basis of these studies the strategy for NSSS design improvement system was extracted and detail work scope was implemented as follows : 3D modelling of the reactor internals were implemented by using the parametric solid modeler, a prototype system of design document computerization and database was suggested, and walk-through simulation integrated with 3D modeling and VDB was accomplished. Major effects of NSSS design quality improvement system by using 3D modeling and VDB are the plant design optimization by simulation, improving the reliability through the single design database system and engineering cost reduction by improving productivity and efficiency. For applying the VDB to full scope of NSSS system design, 3D modelings of reactor coolant system and nuclear fuel assembly and fuel rod were attached as appendix. 2 tabs., 31 figs., 7 refs. (Author) .new.

  14. Licensed reactor nuclear safety criteria applicable to DOE reactors

    International Nuclear Information System (INIS)

    1991-04-01

    The Department of Energy (DOE) Order DOE 5480.6, Safety of Department of Energy-Owned Nuclear Reactors, establishes reactor safety requirements to assure that reactors are sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that adequately protects health and safety and is in accordance with uniform standards, guides, and codes which are consistent with those applied to comparable licensed reactors. This document identifies nuclear safety criteria applied to NRC [Nuclear Regulatory Commission] licensed reactors. The titles of the chapters and sections of USNRC Regulatory Guide 1.70, Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants, Rev. 3, are used as the format for compiling the NRC criteria applied to the various areas of nuclear safety addressed in a safety analysis report for a nuclear reactor. In each section the criteria are compiled in four groups: (1) Code of Federal Regulations, (2) US NRC Regulatory Guides, SRP Branch Technical Positions and Appendices, (3) Codes and Standards, and (4) Supplemental Information. The degree of application of these criteria to a DOE-owned reactor, consistent with their application to comparable licensed reactors, must be determined by the DOE and DOE contractor

  15. Design of a new wet storage rack for spent fuels from IEA-R1 reactor

    International Nuclear Information System (INIS)

    Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter

    2015-01-01

    The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

  16. Design of a new wet storage rack for spent fuels from IEA-R1 reactor

    Energy Technology Data Exchange (ETDEWEB)

    Rodrigues, Antonio C.I.; Madi Filho, Tufic; Siqueira, Paulo T.D.; Ricci Filho, Walter, E-mail: acirodri@ipen.br, E-mail: tmfilho@ipen.br, E-mail: ptsiquei@ipen.br, E-mail: wricci@ipen.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2015-07-01

    The IEA-R1 research reactor operates in a regimen of 64h weekly, at the power of 4.5 MW. In these conditions, the racks of the spent fuel elements have less than half of its initial capacity. Thus, maintaining these operating conditions, the storage will have capacity for about six years. Since the estimated useful life of the IEA-R1 is about another 20 years, it will be necessary to increase the storage capacity of spent fuel. Dr. Henrik Grahn, expert of the International Atomic Energy Agency on wet storage, visiting the IEA-R1 Reactor (September/2012) made some recommendations: among them, the design and installation of racks made with borated stainless steel and internally coated with an aluminum film, so that corrosion of the fuel elements would not occur. After an extensive literature review of material options given for this type of application we got to Boral® manufactured by 3M due to numerous advantages. This paper presents studies on the analysis of criticality using the computer code MCNP 5, demonstrating the possibility of doubling the storage capacity of current racks to attend the demand of the IEA-R1 reactor while attending the safety requirements the International Atomic Energy Agency. (author)

  17. DR AVRAM JOZEF VINAVER (1862-1915) - PIONEER OF RADIOLOGY IN SERBIA.

    Science.gov (United States)

    Babić, Rade Radomir; Stanković Babić, Gordana

    2015-01-01

    Dr Abraham Joseph Vinaver (1862-1915), a Jew from Poland, was a pioneer of radiology in Serbia. He graduated from the Faculty of Medicine in Warsaw (1887), but lived and worked in abac (the Kingdom of Serbia) since 1890. Dr Abraham Joseph Vinarev - Career Development. He procured the first X-ray machine and developed radiological service in Sabac five years after the discovery of X-rays. These were the beginnings of radiology in Serbia. He introduced the application of artesian wells. Dr Abraham Joseph Vinarev - a Participant at the First Congress of Serbian Physicians and Naturalists, Belgrade 1904. "The diagnostic importance of X-rays in lung disease, especially in initial tuberculosis" and "Five Years of Treatment by X-Ray Machines" were the first works in the field of radiology in Serbia by this author. Dr Abraham Joseph Vinaver - Reserve Medical Officer in the Serbian Army. During the Balkan Wars, he was a volunteer with the rank of major engaged in military corps and he participated in the First World War as well. He died of malaria in 1915 in Gevgelija. "Dr Avram Vinaver"- Stanislav Vinarev. His dedication to work during the typhus epidemics was put into verses of a poem by his son Stanislav Vinarev. Dr Avram Vinaver Joseph was a noble man with a great heart, who selflessly sacrificed himself for the Serbian people and Serbia. He gave his contribution to the development of health services in Serbia, both in peacetime and wartime conditions. Dr Abraham Joseph Vinaver laid the foundations for today's radiology in Serbia.

  18. RELAP5-3D Code for Supercritical-Pressure Light-Water-Cooled Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Riemke, Richard Allan; Davis, Cliff Bybee; Schultz, Richard Raphael

    2003-04-01

    The RELAP5-3D computer program has been improved for analysis of supercritical-pressure, light-water-cooled reactors. Several code modifications were implemented to correct code execution failures. Changes were made to the steam table generation, steam table interpolation, metastable states, interfacial heat transfer coefficients, and transport properties (viscosity and thermal conductivity). The code modifications now allow the code to run slow transients above the critical pressure as well as blowdown transients (modified Edwards pipe and modified existing pressurized water reactor model) that pass near the critical point.

  19. Development of a 3-D flow analysis computer program for integral reactor

    International Nuclear Information System (INIS)

    Youn, H. Y.; Lee, K. H.; Kim, H. K.; Whang, Y. D.; Kim, H. C.

    2003-01-01

    A 3-D computational fluid dynamics program TASS-3D is being developed for the flow analysis of primary coolant system consists of complex geometries such as SMART. A pre/post processor also is being developed to reduce the pre/post processing works such as a computational grid generation, set-up the analysis conditions and analysis of the calculated results. TASS-3D solver employs a non-orthogonal coordinate system and FVM based on the non-staggered grid system. The program includes the various models to simulate the physical phenomena expected to be occurred in the integral reactor and will be coupled with core dynamics code, core T/H code and the secondary system code modules. Currently, the application of TASS-3D is limited to the single phase of liquid, but the code will be further developed including 2-phase phenomena expected for the normal operation and the various transients of the integrator reactor in the next stage

  20. Nuclear reactor safety

    International Nuclear Information System (INIS)

    Buhl, A.R.

    1979-01-01

    Dr. Buhl feels that nuclear-energy issues are too complex to be understood as single topics, and can only be understood in relationship to broader issues. In fact, goals and risks associated with all energy options must be seen as interrelated with other broad issues, and it should be understood that there are presently no clearcut criteria to ensure that the best decisions are made. The technical community is responsible for helping the public to understand the basic incompatibility of hard and soft technologies and that there is no risk-free energy source. Four principles are outlined for assessing the risks of various energy technologies: (1) take a holistic view; (2) compare the risk with the unit energy output; (3) compare the risk with those of everyday activities; and (4) identify unusual risks associated with a particular option. Dr. Buhl refers to the study conducted by Dr. Inhaber of Canada who used this approach and concluded that nuclear power and natural gas have the lowest overall risk

  1. Research reactors in Argentina

    International Nuclear Information System (INIS)

    Carlos Ruben Calabrese

    1999-01-01

    Argentine Nuclear Development started in early fifties. In 1957, it was decided to built the first a research reactor. RA-1 reactor (120 kw, today licensed to work at 40 kW) started operation in January 1958. Originally RA-1 was an Argonaut (American design) reactor. In early sixties, the RA-1 core was changed. Fuel rods (20% enrichment) was introduced instead the old Argonaut core design. For that reason, a critical facility named RA-0 was built. After that, the RA-3 project started, to build a multipurpose 5 MW nuclear reactor MTR pool type, to produce radioisotopes and research. For that reason and to define the characteristics of the RA-3 core, another critical facility was built, RA-2. Initially RA-3 was a 90 % enriched fuel reactor, and started operation in 1967. When Atucha I NPP project started, a German design Power Reactor, a small homogeneous reactor was donated by the German Government to Argentina (1969). This was RA-4 reactor (20% enrichment, 1W). In 1982, RA-6 pool reactor achieved criticality. This is a 500 kW reactor with 90% enriched MTR fuel elements. In 1990, RA-3 started to operate fueled by 20% enriched fuel. In 1997, the RA-8 (multipurpose critical facility located at Pilcaniyeu) started to operate. RA-3 reactor is the most important CNEA reactor for Argentine Research Reactors development. It is the first in a succession of Argentine MTR reactors built by CNEA (and INVAP SE ) in Argentina and other countries: RA-6 (500 kW, Bariloche-Argentina), RP-10 (10MW, Peru), NUR (500 kW, Algeria), MPR (22 MW, Egypt). The experience of Argentinian industry permits to compete with foreign developed countries as supplier of research reactors. Today, CNEA has six research reactors whose activities have a range from education and promotion of nuclear activity, to radioisotope production. For more than forty years, Argentine Research Reactors are working. The experience of Argentine is important, and argentine firms are able to compete in the design and

  2. Interview with Smithsonian NASM Spacesuit Curator Dr. Cathleen Lewis

    Science.gov (United States)

    Lewis, Cathleen; Wright, Rebecca

    2012-01-01

    Dr. Cathleen Lewis was interviewed by Rebecca Wright during the presentation of an "Interview with Smithsonian NASM Spacesuit Curator Dr. Cathleen Lewis" on May 14, 2012. Topics included the care, size, and history of the spacesuit collection at the Smithsonian and the recent move to the state-of-the-art permanent storage facility at the Udvar-Hazy facility in Virginia.

  3. The future of nursing: how important is discipline-specific knowledge? A conversation with Jacqueline Fawcett. Interview by Dr. Janie Butts and Dr. Karen Rich.

    Science.gov (United States)

    Fawcett, Jacqueline

    2012-04-01

    Nurses have long attempted to secure a unique identity for the profession. Many scholars are now promoting an interdisciplinary framework for nursing practice. Fawcett is convinced that interdisciplinary practice poses a danger for nursing to lose its identity and that interdisciplinary practice cannot be successful if members of each discipline do not understand the conceptual models, practice, and research of their own discipline. Dr. Janie Butts and Dr. Karen Rich interviewed Dr. Jacqueline Fawcett about her views related to discipline-specific knowledge and nursing's future. The authors conclude that Fawcett's scientific foundation gives nursing the solidarity and power necessary to determine the unique internal goods of its practice.

  4. Hydrogen production using Rhodopseudomonas palustris WP 3-5 with hydrogen fermentation reactor effluent

    International Nuclear Information System (INIS)

    Chi-Mei Lee; Kuo-Tsang Hung

    2006-01-01

    The possibility of utilizing the dark hydrogen fermentation stage effluents for photo hydrogen production using purple non-sulfur bacteria should be elucidated. In the previous experiments, Rhodopseudomonas palustris WP3-5 was proven to efficiently produce hydrogen from the effluent of hydrogen fermentation reactors. The highest hydrogen production rate was obtained at a HRT value of 48 h when feeding a 5 fold effluent dilution from anaerobic hydrogen fermentation. Besides, hydrogen production occurred only when the NH 4 + concentration was below 17 mg-NH 4 + /l. Therefore, for successful fermentation effluent utilization, the most important things were to decrease the optimal HRT, increase the optimal substrate concentration and increase the tolerable ammonia concentration. In this study, a lab-scale serial photo-bioreactor was constructed. The reactor overall hydrogen production efficiency with synthetic wastewater exhibiting an organic acid profile identical to that of anaerobic hydrogen fermentation reactor effluent and with effluent from two anaerobic hydrogen fermentation reactors was evaluated. (authors)

  5. Research reactor core conversion guidebook. V. 3: Analytical verification (Appendices G and H)

    International Nuclear Information System (INIS)

    1992-04-01

    Volume 3 consists of Appendix G which contains detailed results of a safety-related benchmark problem for an idealized reactor and Appendix H which contains detailed comparisons of calculated and measured data for actual cores with moderately enriched uranium and low enriched uranium fuels. The results of the benchmark calculations in Appendix G are summarized in Chapter 7 of Volume 1 and the results of the comparisons between calculations and measurements are summarized in Chapter 8 of Volume 1. Both the approaches described in these appendices are very useful in ensuring that the calculational methods employed in the preparation of a Safety Report are accurate. As a first step, it is recommended that reactor operators/physicists use their own methods and codes to first calculate the benchmark problem, and then compare the results of calculations with measurements in their own reactor or in one of the reactors for which measured data is available in Appendix H. (author). Refs, figs and tabs

  6. The ARIES-III D-3He tokamak reactor

    International Nuclear Information System (INIS)

    Bathke, C.G.; Werley, K.A.; Miller, R.L.; Krakowski, R.A.; Santarius, J.F.

    1992-01-01

    The multi-institutional ARIES study has generated a conceptual design of another tokamak fusion reactor in a series that varies the assumed advances in technology and physics. The ARIES-III design uses a D- 3 He fuel cycle and requires advances in technology and physics for economical attractiveness. The optimal design was characterized through systems analyses for eventual conceptual engineering design. In this paper, results from the systems analysis are summarized, and a comparison with the high-field, D-T fueled ARIES-I is included

  7. Annealing of the BR3 reactor pressure vessel

    International Nuclear Information System (INIS)

    Fabry, A.; Motte, F.; Stiennon, G.; Debrue, J.; Gubel, P.; Van de Velde, J.; Minsart, G.; Van Asbroeck, P.

    1985-01-01

    The pressure vessel of the Belgian BR-3 plant, a small (11 MWe) PWR presently used for fuel testing programs and operated since 1962, was annealed during March, 1984. The anneal was performed under wet conditions for 168 hours at 650 0 F with core removal and within plant design margins justification for the anneal, summary of plant characteristics, description of materials sampling, summary of reactor physics and dosimetry, development of embrittlement trend curves, hypothesized pressurized and overcooling thermal shock accidents, and conclusions are provided in detail

  8. RB Research nuclear reactor RB reactor, Annual report for 2000

    International Nuclear Information System (INIS)

    Milosevic, M.

    2000-12-01

    Report on RB reactor operation during 2000 contains 3 parts. Part one contains a brief description of reactor operation and reactor components, relevant dosimetry data and radiation protection issues, personnel and financial data. Part two is devoted to maintenance of the reactor components, namely, fuel, heavy water, reactor vessel, heavy water circulation system, absorption rods and heavy water level-meters, maintenance of electronic, mechanical, electrical and auxiliary equipment. Part three contains data concerned with reactor operation and utilization with a comprehensive list of publications resulting from experiments done at the RB reactor. It contains data about reactor operation during previous 14 years, i.e. from 1986 - 2000

  9. 3D Nondestructive Visualization and Evaluation of TRISO Particles Distribution in HTGR Fuel Pebbles Using Cone-Beam Computed Tomography

    Directory of Open Access Journals (Sweden)

    Gongyi Yu

    2017-01-01

    Full Text Available A nonuniform distribution of tristructural isotropic (TRISO particles within a high-temperature gas-cooled reactor (HTGR pebble may lead to excessive thermal gradients and nonuniform thermal expansion during operation. If the particles are closely clustered, local hotspots may form, leading to excessive stresses on particle layers and an increased probability of particle failure. Although X-ray digital radiography (DR is currently used to evaluate the TRISO distributions in pebbles, X-ray DR projection images are two-dimensional in nature, which would potentially miss some details for 3D evaluation. This paper proposes a method of 3D visualization and evaluation of the TRISO distribution in HTGR pebbles using cone-beam computed tomography (CBCT: first, a pebble is scanned on our high-resolution CBCT, and 2D cross-sectional images are reconstructed; secondly, all cross-sectional images are restructured to form the 3D model of the pebble; then, volume rendering is applied to segment and display the TRISO particles in 3D for visualization and distribution evaluation. For method validation, several pebbles were scanned and the 3D distributions of the TRISO particles within the pebbles were produced. Experiment results show that the proposed method provides more 3D than DR, which will facilitate pebble fabrication research and production quality control.

  10. MSeqDR: A Centralized Knowledge Repository and Bioinformatics Web Resource to Facilitate Genomic Investigations in Mitochondrial Disease.

    Science.gov (United States)

    Shen, Lishuang; Diroma, Maria Angela; Gonzalez, Michael; Navarro-Gomez, Daniel; Leipzig, Jeremy; Lott, Marie T; van Oven, Mannis; Wallace, Douglas C; Muraresku, Colleen Clarke; Zolkipli-Cunningham, Zarazuela; Chinnery, Patrick F; Attimonelli, Marcella; Zuchner, Stephan; Falk, Marni J; Gai, Xiaowu

    2016-06-01

    MSeqDR is the Mitochondrial Disease Sequence Data Resource, a centralized and comprehensive genome and phenome bioinformatics resource built by the mitochondrial disease community to facilitate clinical diagnosis and research investigations of individual patient phenotypes, genomes, genes, and variants. A central Web portal (https://mseqdr.org) integrates community knowledge from expert-curated databases with genomic and phenotype data shared by clinicians and researchers. MSeqDR also functions as a centralized application server for Web-based tools to analyze data across both mitochondrial and nuclear DNA, including investigator-driven whole exome or genome dataset analyses through MSeqDR-Genesis. MSeqDR-GBrowse genome browser supports interactive genomic data exploration and visualization with custom tracks relevant to mtDNA variation and mitochondrial disease. MSeqDR-LSDB is a locus-specific database that currently manages 178 mitochondrial diseases, 1,363 genes associated with mitochondrial biology or disease, and 3,711 pathogenic variants in those genes. MSeqDR Disease Portal allows hierarchical tree-style disease exploration to evaluate their unique descriptions, phenotypes, and causative variants. Automated genomic data submission tools are provided that capture ClinVar compliant variant annotations. PhenoTips will be used for phenotypic data submission on deidentified patients using human phenotype ontology terminology. The development of a dynamic informed patient consent process to guide data access is underway to realize the full potential of these resources. © 2016 WILEY PERIODICALS, INC.

  11. Reactor science and technology: operation and control of reactors

    International Nuclear Information System (INIS)

    Qiu Junlong

    1994-01-01

    This article is a collection of short reports on reactor operation and research in China in 1991. The operation of and research activities linked with the Heavy Water Research Reactor, Swimming Pool Reactor and Miniature Neutron Source Reactor are briefly surveyed. A number of papers then follow on the developing strategies in Chinese fast breeder reactor technology including the conceptual design of an experimental fast reactor (FFR), theoretical studies of FFR thermo-hydraulics and a design for an immersed sodium flowmeter. Reactor physics studies cover a range of topics including several related to work on zero power reactors. The section on reactor safety analysis is concerned largely with the assessment of established, and the presentation of new, computer codes for use in PWR safety calculations. Experimental and theoretical studies of fuels and reactor materials for FBRs, PWRs, BWRs and fusion reactors are described. A final miscellaneous section covers Mo-Tc isotope production in the swimming pool reactor, convective heat transfer in tubes and diffusion of tritium through plastic/aluminium composite films and Li 2 SiO 3 . (UK)

  12. Master-3.0: multi-purpose analyzer for static and transient effects of reactors

    International Nuclear Information System (INIS)

    Cho, Byung Oh; Joo, Han Gyu; Cho, Jin Young; Song, Jae Seung; Zee, Sung Quun

    2002-03-01

    MASTER-3.0 (Multi-purpose Analyzer for Static and Transient Effects of Reactors) is a nuclear design code based on the multi-group diffusion theory to calculate the steady-state and transient pressurized water reactor core in a 3-dimensional Cartesian or hexagonal geometry. Its neutronics model solves the space-time dependent neutron diffusion equations with NIM (Nodal Integration Method), NEM (Nodal Expansion Method), AFEN (Analytic Function Expansion Nodal Method)/NEM Hybrid Method, NNEM (Non-linear Nodal Expansion Method) or NANM (Non-linear Analytic Nodal Method) for a Cartesian geometry and with NTPEN (Non-linear Triangle-based Polynomial Expansion Nodal Method), AFEN (Analytic Function Expansion Nodal)/NEM Hybrid Method or NLFM (Non-linear Local Fine-Mesh Method) for a hexagonal one. Coarse mesh rebalancing, Krylov Subspace method, energy group restriction/prolongation method and asymptotic extrapolation method are implemented to accelerate the convergence of iteration process. MASTER-3.0 performs microscopic depletion calculations using microscopic cross sections provided by CASMO-3 or HELIOS and also has the reconstruction capability of pin information by use of MSS-IAS (Method of Successive Smoothing with Improved Analytic Solution). For the thermal-hydraulic calculation, fuel temperature table or COBRA3-C/P or MATRA model can be used selectively. In addition, MASTER-3.0 is designed to cover various PWRs including SMART as well as WH- and CE-type reactors, providing all data required in their design procedures

  13. 3 D flow computations under a reactor vessel closure head

    International Nuclear Information System (INIS)

    Daubert, O.; Bonnin, O.; Hofmann, F.; Hecker, M.

    1995-12-01

    The flow under a vessel cover of a pressurised water reactor is investigated by using several computations and a physical model. The case presented here is turbulent, isothermal and incompressible. Computations are made with N3S code using a k-epsilon model. Comparisons between numerical and experimental results are on the whole satisfying. Some local improvements are expected either with more sophisticated turbulence models or with mesh refinements automatically computed by using the adaptive meshing technique which has been just implemented in N3S for 3D cases. (authors). 6 refs., 7 figs

  14. In memory Prof. Dr. L.H.K Bleeker | Gemser | HTS Teologiese ...

    African Journals Online (AJOL)

    HTS Teologiese Studies / Theological Studies. Journal Home · ABOUT THIS JOURNAL · Advanced Search · Current Issue · Archives · Journal Home > Vol 1, No 3 (1944) >. Log in or Register to get access to full text downloads. Username, Password, Remember me, or Register. In memory Prof. Dr. L.H.K Bleeker. B Gemser ...

  15. Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel

    International Nuclear Information System (INIS)

    Bodey, Isaac T.; Curtis, Franklin G.; Arimilli, Rao V.; Ekici, Kivanc; Freels, James D.

    2015-01-01

    The findings presented in this report are results of a five year effort led by the RRD Division of the ORNL, which is focused on research and development toward the conversion of the High Flux Isotope Reactor (HFIR) fuel from high-enriched uranium (HEU) to low-enriched uranium (LEU). This report focuses on the tasks accomplished by the University of Tennessee Knoxville (UTK) team from the Department of Mechanical, Aerospace, and Biomedical Engineering (MABE) that provided expert support in multiphysics modeling of complex problems associated with the LEU conversion of the HFIR reactor. The COMSOL software was used as the main computational modeling tool, whereas Solidworks was also used in support of computer-aided-design (CAD) modeling of the proposed LEU fuel design. The UTK research has been governed by a statement of work (SOW), which was updated annually to clearly define the specific tasks reported herein. Ph.D. student Isaac T. Bodey has focused on heat transfer and fluid flow modeling issues and has been aided by his major professor Dr. Rao V. Arimilli. Ph.D. student Franklin G. Curtis has been focusing on modeling the fluid-structure interaction (FSI) phenomena caused by the mechanical forces acting on the fuel plates, which in turn affect the fluid flow in between the fuel plates, and ultimately the heat transfer, is also affected by the FSI changes. Franklin Curtis has been aided by his major professor Dr. Kivanc Ekici. M.Sc. student Adam R. Travis has focused two major areas of research: (1) on accurate CAD modeling of the proposed LEU plate design, and (2) reduction of the model complexity and dimensionality through interdimensional coupling of the fluid flow and heat transfer for the HFIR plate geometry. Adam Travis is also aided by his major professor, Dr. Kivanc Ekici. We must note that the UTK team, and particularly the graduate students, have been in very close collaboration with Dr. James D. Freels (ORNL technical monitor and mentor) and have

  16. Research and Development of Multiphysics Models in Support of the Conversion of the High Flux Isotope Reactor to Low Enriched Uranium Fuel

    Energy Technology Data Exchange (ETDEWEB)

    Bodey, Isaac T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Curtis, Franklin G. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Arimilli, Rao V. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ekici, Kivanc [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Freels, James D. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

    2015-11-01

    The findings presented in this report are results of a five year effort led by the RRD Division of the ORNL, which is focused on research and development toward the conversion of the High Flux Isotope Reactor (HFIR) fuel from high-enriched uranium (HEU) to low-enriched uranium (LEU). This report focuses on the tasks accomplished by the University of Tennessee Knoxville (UTK) team from the Department of Mechanical, Aerospace, and Biomedical Engineering (MABE) that provided expert support in multiphysics modeling of complex problems associated with the LEU conversion of the HFIR reactor. The COMSOL software was used as the main computational modeling tool, whereas Solidworks was also used in support of computer-aided-design (CAD) modeling of the proposed LEU fuel design. The UTK research has been governed by a statement of work (SOW), which was updated annually to clearly define the specific tasks reported herein. Ph.D. student Isaac T. Bodey has focused on heat transfer and fluid flow modeling issues and has been aided by his major professor Dr. Rao V. Arimilli. Ph.D. student Franklin G. Curtis has been focusing on modeling the fluid-structure interaction (FSI) phenomena caused by the mechanical forces acting on the fuel plates, which in turn affect the fluid flow in between the fuel plates, and ultimately the heat transfer, is also affected by the FSI changes. Franklin Curtis has been aided by his major professor Dr. Kivanc Ekici. M.Sc. student Adam R. Travis has focused two major areas of research: (1) on accurate CAD modeling of the proposed LEU plate design, and (2) reduction of the model complexity and dimensionality through interdimensional coupling of the fluid flow and heat transfer for the HFIR plate geometry. Adam Travis is also aided by his major professor, Dr. Kivanc Ekici. We must note that the UTK team, and particularly the graduate students, have been in very close collaboration with Dr. James D. Freels (ORNL technical monitor and mentor) and have

  17. DR. MIKA MAJALE MEMORIAL LECTURE

    African Journals Online (AJOL)

    He had four children Irene Majale,. Prof. Mike Majale (Architect) Victoria Majale Ojiambo and Chris Majale. Dr. Majale died on 21st April 1978. As an orthopaedic Surgeon he worked at Kenyatta. National Hospital (KNH), Kabete Orthopaedic Unit and. Armed Forces Memorial Hospital. He did not do any private practice.

  18. Ali, Dr Moizuddin Abdul Salim

    Indian Academy of Sciences (India)

    ... Section: Animal Sciences. Ali, Dr Moizuddin Abdul Salim D.Sc. (Andhra), D.Sc. (h.c.), FNA. Date of birth: 12 November 1896. Date of death: 20 June 1987. Specialization: Ecology, Zoogeography, Nature Conservation, Ornithology Last known address: No. 46, Pali Hill, Bombay 400 050. YouTube; Twitter; Facebook; Blog ...

  19. Review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kobayashi, Tetsuya; Araki, Masaaki; Ohba, Toshinobu; Torii, Yoshiya [Japan Atomic Energy Agency, Tokai, Ibaraki (Japan); Takeuchi, Masaki [Nuclear Safety Commission (Japan)

    2012-03-15

    JRR-3(Japan Research Reactor No.3) with the thermal power of 20MW is a light water moderated and cooled, swimming pool type research reactor. JRR-3 has been operated without major troubles. This paper presents about review on the seismic safety of JRR-3 according to the revised regulatory code on seismic design for nuclear reactors. In addition, some topics concerning damages in JRR-3 due to the Great East Japan Earthquake are presented. (author)

  20. Separátory, sedimentační nádrže včetně funkce retenční nádrže Jeneweinova

    OpenAIRE

    Turic, Jakub

    2016-01-01

    Tato bakalářská práce se zabývá problematikou separátorů a sedimentačních nádrží, včetně funkce retenční nádrže Jeneweinova v Brně. Popisuje základní fyzikální a hydrodynamické vlastnosti vod a rozděluje její znečištění. Dále se zabývá popisem jednotlivých separačních a sedimentačních nádrží, jejich účel a využití. Zabývá se vznikem povodní a využití retenčních nádrží jako protipovodňové ochrany. Součástí práce je popis retenční nádrže Jeneweinova, její návrh, účel a funkce. The subject of...

  1. Nuclear Safety Research and Facilities Department. Annual report 1999

    International Nuclear Information System (INIS)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  2. Nuclear Safety Research and Facilities Department annual report 1997

    International Nuclear Information System (INIS)

    Majborn, B.; Aarkrog, A.; Brodersen, K.

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department's research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  3. Nuclear Safety Research and Facilities Department annual report 1998

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E.

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  4. GENESI-DR: Discovery, Access and on-Demand Processing in Federated Repositories

    Science.gov (United States)

    Cossu, Roberto; Pacini, Fabrizio; Parrini, Andrea; Santi, Eliana Li; Fusco, Luigi

    2010-05-01

    GENESI-DR (Ground European Network for Earth Science Interoperations - Digital Repositories) is a European Commission (EC)-funded project, kicked-off early 2008 lead by ESA; partners include Space Agencies (DLR, ASI, CNES), both space and no-space data providers such as ENEA (I), Infoterra (UK), K-SAT (N), NILU (N), JRC (EU) and industry as Elsag Datamat (I), CS (F) and TERRADUE (I). GENESI-DR intends to meet the challenge of facilitating "time to science" from different Earth Science disciplines in discovery, access and use (combining, integrating, processing, …) of historical and recent Earth-related data from space, airborne and in-situ sensors, which are archived in large distributed repositories. In fact, a common dedicated infrastructure such as the GENESI-DR one permits the Earth Science communities to derive objective information and to share knowledge in all environmental sensitive domains over a continuum of time and a variety of geographical scales so addressing urgent challenges such as Global Change. GENESI-DR federates data, information and knowledge for the management of our fragile planet in line with one of the major goals of the many international environmental programmes such as GMES, GEO/GEOSS. As of today, 12 different Digital Repositories hosting more than 60 heterogeneous dataset series are federated in GENESI-DR. Series include satellite data, in situ data, images acquired by airborne sensors, digital elevation models and model outputs. ESA has started providing access to: Category-1 data systematically available on Internet; level 3 data (e.g., GlobCover map, MERIS Global Vegetation Index); ASAR products available in ESA Virtual Archive and related to the Supersites initiatives. In all cases, existing data policies and security constraints are fully respected. GENESI-DR also gives access to Grid and Cloud computing resources allowing authorized users to run a number of different processing services on the available data. The GENESI-DR

  5. Raghavarao, Dr Karumanchi Srisaila Mallikarjuna S

    Indian Academy of Sciences (India)

    Elected: 2014 Section: Engineering & Technology. Raghavarao, Dr Karumanchi Srisaila Mallikarjuna S Ph.D. (Mumbai), FNAE, FNAAS. Specialization: Food Engineering, Biotechnology Address: Chief Scientist, Department of Food Engineering, Central Food Technological Research Institute, Mysore 570 020, Karnataka

  6. Neutron flux calculations for the Rossendorf research reactor in (hex)- and (hex,z)-geometry using SNAP-3D

    International Nuclear Information System (INIS)

    Koch, R.; Findeisen, A.

    1986-04-01

    The multigroup neutron diffusion theory code SNAP-3D has been used to perform time independent neutron flux and power calculations of the 10 MW Rossendorf research reactor of the type WWR-SM. The report describes these calculations, as well as the actual reactor configuration, some details of the code SNAP-3D, and two- and three-dimensional reactor models. For evaluating the calculations some flux values and control rod worths have been compared with those of measurements. (author)

  7. Dr. John Marburger visits DESY

    CERN Multimedia

    2003-01-01

    Dr. John Marburger, Director of the United States Office of Science and Technology Policy, visited the research center DESY in Hamburg. The American physicist wanted to inform himself about the status of the TESLA X-ray laser and the TESLA linear collider as well as the international collaboration at DESY (1/2 page).

  8. Summary of ORSphere critical and reactor physics measurements

    Directory of Open Access Journals (Sweden)

    Marshall Margaret A.

    2017-01-01

    Full Text Available In the early 1970s Dr. John T. Mihalczo (team leader, J.J. Lynn, and J.R. Taylor performed experiments at the Oak Ridge Critical Experiments Facility (ORCEF with highly enriched uranium (HEU metal (called Oak Ridge Alloy or ORALLOY to recreate GODIVA I results with greater accuracy than those performed at Los Alamos National Laboratory in the 1950s. The purpose of the Oak Ridge ORALLOY Sphere (ORSphere experiments was to estimate the unreflected and unmoderated critical mass of an idealized sphere of uranium metal corrected to a density, purity, and enrichment such that it could be compared with the GODIVA I experiments. This critical configuration has been evaluated. Preliminary results were presented at ND2013. Since then, the evaluation was finalized and judged to be an acceptable benchmark experiment for the International Criticality Safety Benchmark Experiment Project (ICSBEP. Additionally, reactor physics measurements were performed to determine surface button worths, central void worth, delayed neutron fraction, prompt neutron decay constant, fission density and neutron importance. These measurements have been evaluated and found to be acceptable experiments and are discussed in full detail in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. The purpose of this paper is to summarize all the evaluated critical and reactor physics measurements evaluations.

  9. Summary of ORSphere critical and reactor physics measurements

    Science.gov (United States)

    Marshall, Margaret A.; Bess, John D.

    2017-09-01

    In the early 1970s Dr. John T. Mihalczo (team leader), J.J. Lynn, and J.R. Taylor performed experiments at the Oak Ridge Critical Experiments Facility (ORCEF) with highly enriched uranium (HEU) metal (called Oak Ridge Alloy or ORALLOY) to recreate GODIVA I results with greater accuracy than those performed at Los Alamos National Laboratory in the 1950s. The purpose of the Oak Ridge ORALLOY Sphere (ORSphere) experiments was to estimate the unreflected and unmoderated critical mass of an idealized sphere of uranium metal corrected to a density, purity, and enrichment such that it could be compared with the GODIVA I experiments. This critical configuration has been evaluated. Preliminary results were presented at ND2013. Since then, the evaluation was finalized and judged to be an acceptable benchmark experiment for the International Criticality Safety Benchmark Experiment Project (ICSBEP). Additionally, reactor physics measurements were performed to determine surface button worths, central void worth, delayed neutron fraction, prompt neutron decay constant, fission density and neutron importance. These measurements have been evaluated and found to be acceptable experiments and are discussed in full detail in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. The purpose of this paper is to summarize all the evaluated critical and reactor physics measurements evaluations.

  10. Den europæiske drøm - om EU

    DEFF Research Database (Denmark)

    Østergaard, Uffe

    2007-01-01

    Anmeldelse af: Jeremy Rifkin: Den europæiske drøm (Informations Forlag, 2006). Oversat fra engelsk efter: "The European Dream: How Europe's Vision of the Future Is Quietly Eclipsing the American Dream" (2004)......Anmeldelse af: Jeremy Rifkin: Den europæiske drøm (Informations Forlag, 2006). Oversat fra engelsk efter: "The European Dream: How Europe's Vision of the Future Is Quietly Eclipsing the American Dream" (2004)...

  11. Dr. David Syz, State Secretary for Economic Affairs, Switzerland

    CERN Multimedia

    Maximilien Brice

    2003-01-01

    Dr. David Syz, State Secretary for Economic Affairs, Switzerland is seen here (seventh from right) visiting the assembly hall for the ATLAS experiment during his recent visit to CERN. To his right is Dr. Peter Jenni (blue shirt), spokesperson for the ATLAS Collaboration. The horizontal metal cylinder behind the group is one of the eight vacuum vessels for the superconducting coils of the ATLAS barrel toroid magnet system.

  12. Thermal fluid dynamics study of nuclear advanced reactors of high temperature using RELAP5-3D

    International Nuclear Information System (INIS)

    Scari, Maria Elizabeth

    2017-01-01

    Fourth Generation nuclear reactors (GEN-IV) are being designed with special features such as intrinsic safety, reduction of isotopic inventory and use of fuel in proliferation-resistant cycles. Therefore, the investigation and evaluation of operational and safety aspects of the GEN-IV reactors have been the subject of numerous studies by the international community and also in Brazil. In 2008, in Brazil, was created the National Institute of Science and Technology of Innovative Nuclear Reactors, focusing on studies of projects and systems of new generation reactors, which included GEN-IV reactors as well as advanced PWR (Pressurized Water Reactor) concepts. The Department of Nuclear Engineering of the Federal University of Minas Gerais (DEN-UFMG) is a partner of this Institute, having started studies on the GEN-IV reactors in the year 2007. Therefore, in order to add knowledge to these studies, in this work, three projects of advanced reactors were considered to verify the simulation capability of the thermo-hydraulic RELAP5-3D code for these systems, either in stationary operation or in transient situations. The addition of new working fluids such as ammonia, carbon dioxide, helium, hydrogen, various types of liquid salts, among them Flibe, lead, lithium-bismuth, lithium-lead, was a major breakthrough in this version of the code, allowing also the simulation of GEN-IV reactors. The modeling of the respective core of an HTTR (High Temperature Engineering Test Reactor), HTR-10 (High Temperature Test Module Reactor) and LS-VHTR (Liquid-Salt-Cooled Very-High-Temperature Reactor) were developed and verified in steady state comparing the values found through the calculations with reference data from other simulations, when it is possible. The first two reactors use helium gas as coolant and the LS-VHTR uses a mixture of 66% LiF and 34% of BeF 2 , the LiF-BeF 2 , also know as Flibe. All the studied reactors use enriched uranium as fuel, in form of TRISO (Tristructural

  13. Celebrating the Life and Legacy of Dr. John Hope Franklin

    Science.gov (United States)

    Harris, Robert L., Jr.; Levering-Lewis, David; French, John D.; Wharton, Clifton R., Jr.

    2009-01-01

    Dr. John Hope Franklin chronicled the experiences of African-Americans like no one before him, forcing America to recognize Black history as American history. His contributions were innumerable and his impact was abiding. In celebration of his life and legacy, the authors profile the celebrated scholar and activist, Dr. John Hope Franklin.

  14. 3D CFD for chemical transport profiles in a rotating disk CVD reactor

    Science.gov (United States)

    Han, Jong-Hyun; Yoon, Do-Young

    2010-06-01

    The RDCVD (Rotating Disk Chemical Vapor Deposition) technique is an appropriate method for uniform deposition of grains, such as compound semiconductior materials. The substrate temperature and rotation speed are the major factors, which determine the thickness uniformity of the deposited films. This paper investigates 3D CFD (3 Dimensional Computational Fluid Dynamics) simulation results of flow and heat transfer in a reactor of RDCVD using Fluent. In order to establish the reducibility of buoyancy effect on deposition quality, the chemical transport profile upon the disk heated is examined successfully in 3D domain for different rotating speeds. The resulting vortex flows due the simultaneous buoyance and centrifuge are discussed qualitatively in the 3D virtual system of a RDCVD reactor. 3D CFD is even more effective to describe the internal vortex flows due to the competitive inlet, buoyancy and centrifuge flows, which cannot be realized in the general 2D (2 Dimensional) CFD.[Figure not available: see fulltext.

  15. Development of a version of the reactor dynamics code DYN3D applicable for High Temperature Reactors; Entwicklung einer Version des Reaktordynamikcodes DYN3D fuer Hochtemperaturreaktoren. Abschlussbericht

    Energy Technology Data Exchange (ETDEWEB)

    Rohde, Ulrich; Apanasevich, Pavel; Baier, Silvio; Duerigen, Susan; Fridman, Emil; Grahn, Alexander; Kliem, Soeren; Merk, Bruno

    2012-07-15

    Based on the reactor dynamics code DYN3D for the simulation of transient processes in Light Water Reactors, a code version DYN3D-HTR for application to graphitemoderated, gas-cooled block-type high temperature reactors has been developed. This development comprises: - the methodical improvement of the 3D steady-state neutron flux calculation for the hexagonal geometry of the HTR fuel element blocks - the development of methods for the generation of homogenised cross section data taking into account the double heterogeneity of the fuel element block structure - the implementation of a 3D model for heat conduction and heat transport in the graphite matrix. The nodal method for neutron flux calculation based on SP3 transport approximation was extended to hexagonal fuel element geometry, where the hexagons are subdivided into triangles, thus the method had finally to be derived for triangular geometry. In triangular geometry, a subsequent subdivision of the hexagonal elements can be considered, and therefore, the effect of systematic mesh refinement can be studied. The algorithm was verified by comparison with Monte Carlo reference solutions, on the node-wise level, as well as also on the pin-wise level. New procedures were developed for the homogenization of the double-heterogeneous fuel element structures. One the one hand, the so-called Reactivity equivalent Physical Transformation (RPT), the two-step homogenization method based on 2D deterministic lattice calculations, was extended to cells with different temperatures of the materials. On the other hand, the progress in development of Monte Carlo methods for spectral calculations, in particular the development of the code SERPENT, opened a new, fully consistent 3D approach, where all details of the structures on fuel particle, fuel compact and fuel block level can be taken into account within one step. Moreover, a 3D heat conduction and heat transport model was integrated into DYN3D to be able to simulate radial

  16. Dr Jacob van der Land, marine biologist extraordinary

    OpenAIRE

    Bruggen, van, A.C.

    2001-01-01

    This contribution is an attempt to sketch the life and works of Dr Jacob van der Land, curator of worms and chief marine biologist of the National Museum of Natural History, on the occasion of his official retirement. Born in 1935, Jacob van der Land read biology at Leiden University (1958-1964), where he obtained his Ph.D. in 1970 on a treatise on the Priapulida under the supervision of Prof. Dr L.D. Brongersma. In 1964 he was appointed curator of worms in the museum. Later on he took over l...

  17. Experimental and kinetic modeling study of 3-methylheptane in a jet-stirred reactor

    KAUST Repository

    Karsenty, Florent

    2012-08-16

    Improving the combustion of conventional and alternative fuels in practical applications requires the fundamental understanding of large hydrocarbon combustion chemistry. The focus of the present study is on a high-molecular-weight branched alkane, namely, 3-methylheptane, oxidized in a jet-stirred reactor. This fuel, along with 2-methylheptane, 2,5-dimethylhexane, and n-octane, are candidate surrogate components for conventional diesel fuels derived from petroleum, synthetic Fischer-Tropsch diesel and jet fuels derived from coal, natural gas, and/or biomass, and renewable diesel and jet fuels derived from the thermochemical treatment of bioderived fats and oils. This study presents new experimental results along with a low- and high-temperature chemical kinetic model for the oxidation of 3-methylheptane. The proposed model is validated against these new experimental data from a jet-stirred reactor operated at 10 atm, over the temperature range of 530-1220 K, and for equivalence ratios of 0.5, 1, and 2. Significant effort is placed on the understanding of the effects of methyl substitution on important combustion properties, such as fuel reactivity and species formation. It was found that 3-methylheptane reacts more slowly than 2-methylheptane at both low and high temperatures in the jet-stirred reactor. © 2012 American Chemical Society.

  18. Development of a 3D-Multigroup program to simulate anomalous diffusion phenomena in the nuclear reactors

    International Nuclear Information System (INIS)

    Maleki Moghaddam, Nader; Afarideh, Hossein; Espinosa-Paredes, Gilberto

    2015-01-01

    Highlights: • The new version of neutron diffusion equation for simulating anomalous diffusion is presented. • Application of fractional calculus in the nuclear reactor is revealed. • A 3D-Multigroup program is developed based on the fractional operators. • The super-diffusion and sub-diffusion phenomena are modeled in the nuclear reactors core. - Abstract: The diffusion process is categorized in three parts, normal diffusion, super-diffusion and sub-diffusion. The classical neutron diffusion equation is used to model normal diffusion. A new scheme of derivatives is required to model anomalous diffusion phenomena. The fractional space derivatives are employed to model anomalous diffusion processes where a plume of particles spreads at an inconsistent rate with the classical Brownian motion model. In the fractional diffusion equation, the fractional Laplacians are used; therefore the statistical jump length of neutrons is unrestricted. It is clear that the fractional Laplacians are capable to model the anomalous phenomena in nuclear reactors. We have developed a NFDE-3D (neutron fractional diffusion equation) as a core calculation code to model normal and anomalous diffusion phenomena. The NFDE-3D is validated against the LMW-LWR reactor. The results demonstrate that reactors exhibit complex behavior versus order of the fractional derivatives which depends on the competition between neutron absorption and super-diffusion phenomenon

  19. The Honorable Dr Adolfo Urso, Vice Minister for Foreign Trade, "Viceministro delle Attivita' Produttive, Italia"

    CERN Multimedia

    Patrice Loïez

    2002-01-01

    Photo 01: The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy, visiting SM18 with (from l to r): Dr Roberto Saban, Technical Coordination and Planning, LHC machine; Prof. Luciano Maiani, CERN Director-General; Dr Mario Gerbino, Director General of the Ministry and Prof. Lucio Rossi, LHC Main Magnet and Superconductors (MMS) Group Leader. Photo 02: Prof. Luciano Maiani, CERN Director-General and The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy, in front of one of the LHC superconducting magnet in SM18. Photo 03 :In front of one of the LHC superconducting magnets - from left to right Dr Roberto Saban, Technical Coordination and Planning, LHC machine; The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy and Prof. Luciano Maiani, CERN Director-General. Photo 04: In the SM18 hall (from l. to r.) Prof. Luciano Maiani, CERN Director-General, The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy and Dr Mario Ge...

  20. Silencing the epigenetic silencer KDM4A for TRAIL and DR5 simultaneous induction and antitumor therapy.

    Science.gov (United States)

    Wang, Junjian; Wang, Haibin; Wang, Ling-Yu; Cai, Demin; Duan, Zhijian; Zhang, Yanhong; Chen, Peng; Zou, June X; Xu, Jianzhen; Chen, Xinbin; Kung, Hsing-Jien; Chen, Hong-Wu

    2016-11-01

    Recombinant TRAIL and agonistic antibodies to death receptors (DRs) have been in clinical trial but displayed limited anti-cancer efficacy. Lack of functional DR expression in tumors is a major limiting factor. We report here that chromatin regulator KDM4A/JMJD2A, not KDM4B, has a pivotal role in silencing tumor cell expression of both TRAIL and its receptor DR5. In TRAIL-sensitive and -resistant cancer cells of lung, breast and prostate, KDM4A small-molecule inhibitor compound-4 (C-4) or gene silencing strongly induces TRAIL and DR5 expression, and causes TRAIL-dependent apoptotic cell death. KDM4A inhibition also strongly sensitizes cells to TRAIL. C-4 alone potently inhibits tumor growth with marked induction of TRAIL and DR5 expression in the treated tumors and effectively sensitizes them to the newly developed TRAIL-inducer ONC201. Mechanistically, C-4 does not appear to act through the Akt-ERK-FOXO3a pathway. Instead, it switches histone modifying enzyme complexes at promoters of TRAIL and DR5 transcriptional activator CHOP gene by dissociating KDM4A and nuclear receptor corepressor (NCoR)-HDAC complex and inducing the recruitment of histone acetylase CBP. Thus, our results reveal KDM4A as a key epigenetic silencer of TRAIL and DR5 in tumors and establish inhibitors of KDM4A as a novel strategy for effectively sensitizing tumors to TRAIL pathway-based therapeutics.

  1. An overview of the safety pharmacology career of Dr. C.R. Hassler.

    Science.gov (United States)

    Hawk, M A; Pugsley, M K; Vinci, T; Wallery, J; Hassler, C R; Hamlin, R L

    2017-09-01

    Each year the Safety Pharmacology Society (SPS) recognizes an investigator who has had a marked impact upon the discipline. The 2016 recipient of the SPS Distinguished Service Award (DSA) was Dr. Craig R. Hassler. Dr. Hassler is one of the founding members of the SPS and has been actively engaged in physiological research for over 46years. Dr. Hassler delivered a talk entitled "My 43Years at Battelle Memorial Institute" to meeting attendees. In this article an overview is provided of the illustrious career of Dr. Hassler along with an account of the numerous animal models that were developed at Battelle under his guidance over the years. Copyright © 2017 Elsevier Inc. All rights reserved.

  2. Influence of HLA-D/DR antigen disparity in CTL generation in vitro

    International Nuclear Information System (INIS)

    Johnsen, H.E.; Madsen, M.; Mossin, J.; Kristensen, T.

    1983-01-01

    This report describes the influence of HLA-D/-DR antigen disparity upon the level of cytotoxicity in allogeneic in vitro cultures. Allogeneic cultures, between unrelated HLA-D/-DR full house donors, tested in CML gave three different levels of cytotoxicity, termed weak, intermediate and strong cytotoxicity. HLA-D/-DR compatibility predicts weak cytotoxicity and two HLA-B antigen incompatibility predicts strong cytotoxicity. On the contrary, HLA-A antigens have no major influence upon the strength of cytotoxicity. Accepting that the MLC/CML reaction is an in vitro parallel to the in vivo transplantation of allogeneic tissue, the observations are in accordance with the results of HLA-D/-DR matching for graft survival in human renal transplantation. (author)

  3. Study on effects of development of reactor constant in fast reactor analysis

    International Nuclear Information System (INIS)

    Chiba, Gou

    2002-12-01

    Evaluation was carried out about an effect of development of the new generation reactor constant system that substitutes for the JFS library in fast reactor analysis. Analyzed cores were ZPPR in JUPITER critical experiment and several power reactor cores that were designed in the feasibility study. In the JUPITER analysis, large effects, over 10%, were observed in sodium void reactivity and sample Doppler reactivity. The former resulted from several factors, while the latter was due to an accurate of a resonance interaction effect between Doppler sample and core fuel. In the previous study, the effect had been evaluated in power reactor cores. The effect included an effect of corrosion of weighting spectrum because JFS-3-J3.2, which had been made with the incorrect weighting spectrum, was used in the evaluation. In the present study, JFS-3-J3.2R, which had been made with the correct weighting spectrum, was used. It was confirmed that the effect of development of reactor constant in power reactor was not as large as that in critical assembly. (author)

  4. Simulation in 3 dimensions of a cycle 18 months for an BWR type reactor using the Nod3D program; Simulacion en 3 dimensiones de un ciclo de 18 meses para un reactor BWR usando el programa Nod3D

    Energy Technology Data Exchange (ETDEWEB)

    Hernandez, N.; Alonso, G. [ININ, A.P. 18-1027, 11801 Mexico D.F. (Mexico)]. E-mail: nhm@nuclear.inin.mx; Valle, E. del [IPN, ESFM, 07738 Mexico D.F. (Mexico)

    2004-07-01

    The development of own codes that you/they allow the simulation in 3 dimensions of the nucleus of a reactor and be of easy maintenance, without the consequent payment of expensive use licenses, it can be a factor that propitiates the technological independence. In the Department of Nuclear Engineering (DIN) of the Superior School of Physics and Mathematics (ESFM) of the National Polytechnic Institute (IPN) a denominated program Nod3D has been developed with the one that one can simulate the operation of a reactor BWR in 3 dimensions calculating the effective multiplication factor (kJJ3, as well as the distribution of the flow neutronic and of the axial and radial profiles of the power, inside a means of well-known characteristics solving the equations of diffusion of neutrons numerically in stationary state and geometry XYZ using the mathematical nodal method RTN0 (Raviart-Thomas-Nedelec of index zero). One of the limitations of the program Nod3D is that it doesn't allow to consider the burnt of the fuel in an independent way considering feedback, this makes it in an implicit way considering the effective sections in each step of burnt and these sections are obtained of the code Core Master LEND. However even given this limitation, the results obtained in the simulation of a cycle of typical operation of a reactor of the type BWR are similar to those reported by the code Core Master LENDS. The results of the keJ - that were obtained with the program Nod3D they were compared with the results of the code Core Master LEND, presenting a difference smaller than 0.2% (200 pcm), and in the case of the axial profile of power, the maxim differs it was of 2.5%. (Author)

  5. Gaia DR1 documentation Chapter 6: Variability

    Science.gov (United States)

    Eyer, L.; Rimoldini, L.; Guy, L.; Holl, B.; Clementini, G.; Cuypers, J.; Mowlavi, N.; Lecoeur-Taïbi, I.; De Ridder, J.; Charnas, J.; Nienartowicz, K.

    2017-12-01

    This chapter describes the photometric variability processing of the Gaia DR1 data. Coordination Unit 7 is responsible for the variability analysis of over a billion celestial sources. In particular the definition, design, development, validation and provision of a software package for the data processing of photometrically variable objects. Data Processing Centre Geneva (DPCG) responsibilities cover all issues related to the computational part of the CU7 analysis. These span: hardware provisioning, including selection, deployment and optimisation of suitable hardware, choosing and developing software architecture, defining data and scientific workflows as well as operational activities such as configuration management, data import, time series reconstruction, storage and processing handling, visualisation and data export. CU7/DPCG is also responsible for interaction with other DPCs and CUs, software and programming training for the CU7 members, scientific software quality control and management of software and data lifecycle. Details about the specific data treatment steps of the Gaia DR1 data products are found in Eyer et al. (2017) and are not repeated here. The variability content of the Gaia DR1 focusses on a subsample of Cepheids and RR Lyrae stars around the South ecliptic pole, showcasing the performance of the Gaia photometry with respect to variable objects.

  6. Nuclear Safety Research and Facilities Department. Annual report 1999

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E. [eds.

    2000-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department's research and development activities were organized in two research programmes: 'Radiation Protection and Reactor Safety' and 'Radioecology and Tracer Studies'. The nuclear facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au)

  7. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 5 tabs., 21 ills

  8. Nuclear Safety Research and Facilities Department annual report 1999

    DEFF Research Database (Denmark)

    Majborn, B.; Damkjær, A.; Jensen, Per Hedemann

    2000-01-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1999. The department´s research and development activities were organized in two research programmes: "Radiation Protection and Reactor Safety" and"Radioecology and Tracer Studies". The nuclear...... facilities operated by the department include the research reactor DR 3, the Isotope Laboratory, the Waste Management Plant, and the educational reactor DR 1. Lists of staff and publications are includedtogether with a summary of the staff´s participation in national and international committees....

  9. Department of Nuclear Safety Research and Nuclear Facilities annual report 1995

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Jacobsen, U.; Oelgaard, P.L. [eds.

    1996-03-01

    The report presents a summary of the work of the Department of Nuclear Safety Research and Nuclear Facilities in 1995. The department`s research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 5 tabs., 21 ills.

  10. Nuclear Safety Research and Facilities Department annual report 1997

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Aarkrog, A.; Brodersen, K. [and others

    1998-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1997. The department`s research and development activities were organized in four research programmes: Reactor Safety, Radiation protection, Radioecology, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the educational reactor DR1. Lists of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au) 11 tabs., 39 ills.; 74 refs.

  11. Nuclear Safety Research and Facilities Department annual report 1998

    Energy Technology Data Exchange (ETDEWEB)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Hedemann Jensen, P.; Nielsen, S.P.; Nonboel, E

    1999-04-01

    The report present a summary of the work of the Nuclear Safety Research and Facilities Department in 1998. The department`s research and development activities were organized in two research programmes: `Radiation Protection and Reactor Safety` and `Radioecology and Tracer Studies`. The nuclear facilities operated by the department include the research reactor DR3, the Isotope Laboratory, the Waste Treatment plant, and the educational reactor DR1. Lsits of staff and publications are included together with a summary of the staff`s participation in national and international committees. (au)

  12. Nuclear Safety Research and Facilities department annual report 1996

    International Nuclear Information System (INIS)

    Majborn, B.; Brodersen, K.; Damkjaer, A.; Floto, H.; Heydorn, K.; Oelgaard, P.L.

    1997-04-01

    The report presents a summary of the work of the Nuclear Safety Research and Facilities Department in 1996. The Department's research and development activities are organized in three research programmes: Radiation Protection, Reactor Safety, and Radioanalytical Chemistry. The nuclear facilities operated by the department include the Research Reactor DR3, the Isotope Laboratory, the Waste Treatment Plant, and the Educational Reactor DR1. Lists of staff and publications are included together with a summary of the staff's participation in national and international committees. (au) 2 tabs., 28 ills

  13. Fascaplysin sensitizes cells to TRAIL-induced apoptosis through upregulating DR5 expression

    Science.gov (United States)

    Wang, Feng; Chen, Haimin; Yan, Xiaojun; Zheng, Yanling

    2013-05-01

    This study investigated the molecular mechanism of anti-tumor effect of fascaplysin, a nitrogenous red pigment firstly isolated from a marine sponge. Microarray analysis show that the TNF and TNF receptor superfamily in human umbilical vein endothelial cells (HUVEC) and human hepatocarcinoma cells (BEL-7402) were significantly regulated by fascaplysin. Western Blot results reveal that fascaplysin increased the expression of cleaved caspase-9, active caspase-3, and decreased the level of procaspase-8 and Bid. Flow cytometry and cytotoxicity tests indicate that fascaplysin sensitized cells to tumor necrosis-related apoptosisinducing ligand-(TRAIL) induced apoptosis, which was markedly blocked by TRAIL R2/Fc chimera, a dominant negative form of TRAIL receptor DR5. Therefore, our results demonstrate that fascaplysin promotes apoptosis through the activation of TRAIL signaling pathway by upregulating DR5 expression.

  14. Granice podmorskih prostora jadranskih država

    Directory of Open Access Journals (Sweden)

    Marina Vokić Žužul

    2015-09-01

    Full Text Available U ovome radu analiziraju se sve dosada utvrđene granice jadranskog podmorja kao i one koje tak valja utvrditi, posebice u svjetlu novih istraživanja njegovih prirodnih bogatstava. Uz Hrvatsku i Italiju, koje dijele najveći dio morskog dna i podzemlja u Jadranu, pravo na epikontinentski pojas imaju i Crna Gora te Albanija. Dvije jadranske države s kratkim obalama – Bosna i Hercegovina te Slovenija, države su u nepovoljnome geografskom položaju koje ne mogu imati epikontinentski pojas kao prirodni produžetak svoga kopnenog područja. Podmorski prostori tih država završavaju stoga na vanjskoj granici njihovih teritorijalnih mora. Osim razmatranja tih granica i sporazumno utvrđenih granica epikontinentskih pojaseva, autorice se kritički osvrću i na jednostrane akte Slovenije o proglašenju njezinoga epikontinentskog pojasa iz 2005. godine kao potpuno pravno neutemeljene akte. U središtu pozornosti ovoga rada je razmatranje granice koja dijeli podmorske prostore Hrvatske i Italije kao buduće granice dviju država i nad morskim dnom. Ta bi granična crta, u skladu s Konvencijom UN-a o pravu mora, trebala postati – jedinstvena morska granica njihovih epikontinentskih i gospodarskih pojaseva (odnosno ekološke zone Italije i zaštićenoga ekološko-ribolovnog pojasa Republike Hrvatske. Takva višefunkcionalna jedinstvena granična crta u najboljem je interesu pravne sigurnosti u svim načinima korištenja mora, a u međunarodnoj sudskoj i arbitražnoj praksi posljednjih desetljeća u potpunosti je zamijenila povlačenje različitih crta razgraničenja za više pojaseva u istome morskom prostoru. S obzirom na rezultate nedavno provedenih istraživanja potencijalnih nalazišta nafte i plina u južnom Jadranu, u radu se upozorava i na potrebu što skorijeg povlačenja crte bočnog razgraničenja epikontinentskih pojaseva Hrvatske i Crne Gore. Autorice analiziraju moguće pravce te nove granice, uzimajući u obzir znatno odstupanje od

  15. How Dr Math reaches pupils with competitions and computer games by using MXit

    CSIR Research Space (South Africa)

    Butgereit, L

    2009-05-01

    Full Text Available In a world where school books, pencils and paper have to compete with cell phones, IPODs, and MP3 players for pupils' attention, Dr Math entices pupils to practice basic mathematics skills by providing games and competitions using Mxit over cell...

  16. Zingiber officinale, Piper retrofractum and Combination Induced Apoptosis and p53 Expression in Myeloma and WiDr Cell Lines

    Directory of Open Access Journals (Sweden)

    HENY EKOWATI

    2012-09-01

    Full Text Available In previous studies, Zingiber officinale, Piper retrofractum, and the combination showed cytotoxic activity, induced apoptosis, and p53 expression of HeLa, T47D, and MCF-7 cell lines. This study was conducted to investigate the cytotoxic and apoptotic activity of Zingiber officinale (ZO, Piper retrofractum (PR, and the combination as well as their effect to p53 expression on Myeloma and WiDr cells. The powder of ZO, PR, and ZO + PR combination (1:1 were macerated with 96% ethanol for 3 x 24 hours. MTT cytotoxic assay was performed on Myeloma and WiDr cell lines. Apoptotic cells were stained with ethidium bromide and acridine orange. Imunohistochemical expression of p53 was examined on Myeloma and WiDr cell lines. Doxorubicin was used as positive control in all assays. Results showed that ZO, PR, and ZO + PR combination had cytotoxic activity on Myeloma cells with IC50 of 28, 36, and 55 mg/ml respectively and WiDr cell lines with IC50 of 74, 158, and 64 mg/ml respectively, induced apoptotic activity, and increased p53 expression on Myeloma and WiDr cells. These results suggest that ZO, PR, and their combination induced Myeloma and WiDr cells in apoptosis through p53 expression.

  17. Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

    International Nuclear Information System (INIS)

    2015-01-01

    This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

  18. Pengaruh Nilai Pelanggan (Customer Value) Terhadap Loyalitas Pelanggan (Customer Loyalty) Padarumah Makan Zam-Zam Dr. Mansyur Medan

    OpenAIRE

    Pratama, Rizky Trisnadian

    2015-01-01

    The hectic of Restaurant Bussiness around activities Sites, particularly around University makes the level of competition among Restaurant increasingly stringent. This study will discuss one of the Restaurant that is Zam-Zam Dr. Mansyur Medan Restaurant. The object of this research is Customer of Zam-Zam Dr. Mansyur Medan Restaurant. The independent variable (X) is composed of Customer Value (X1) Emotional Value, (X2) Social Value, (X3) Performance and (X4) Price. The dependent variable (Y) i...

  19. Extension of the GeN-Foam neutronic solver to SP3 analysis and application to the CROCUS experimental reactor

    International Nuclear Information System (INIS)

    Fiorina, Carlo; Hursin, Mathieu; Pautz, Andreas

    2017-01-01

    Highlights: • Development and verification of an SP 3 solver based on OpenFOAM. • Integration into the GeN-Foam multi-physics platform. • Application of the new GeN-Foam SP 3 solver to the CROCUS reactor. - Abstract: The Laboratory for Reactor Physics and Systems Behaviour at the PSI and at the EPFL has been developing since 2013 a multi-physics platform for coupled reactor analysis named GeN-Foam. The developed tool includes a solver for the eigenvalue and transient solution of multi-group neutron diffusion equations. Although frequently used in reactor analysis, the diffusion theory shows some limitations for core configurations involving strong anisotropies, which is the case for the CROCUS research reactor at the EPFL. The use of an SP 3 approximation to neutron transport can often lead to visible improvements in a code predictive capabilities, especially for one-directional anisotropies, with acceptable added computational cost vs diffusion. Following some modelling issues for the CROCUS reactor, and in order to improve the GeN-Foam modelling capabilities, the GeN-Foam diffusion solver has been extended to allow for SP 3 analyses. The present paper describes such extension and a preliminary verification using a mini-core PWR benchmark. The newly developed solver is then applied to the analysis of the CROCUS experimental reactor and results are compared to Monte Carlo calculations, as well as to the results of the diffusion solver.

  20. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  1. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    Energy Technology Data Exchange (ETDEWEB)

    Chang, Y.I.

    1992-07-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

  2. A next-generation reactor concept: The Integral Fast Reactor (IFR)

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1992-01-01

    The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

  3. Tritium production, management and its impact on safety for a D-3He fusion reactor

    International Nuclear Information System (INIS)

    Sze, D.K.; Herring, S.; Sawan, M.

    1991-11-01

    About three percent of the fusion energy produced by a D- 3 He reactor is in the form of neutrons. Those neutrons are generated by D-D and D-T reactions, with the tritium produced by the D-D fusion. The neutrons will react with structural steel, deuterium, 3 He and shielding material to produce tritium. About half of the tritium generated by the D-D reaction will not burn in the plasma and will exit as a part of the plasma exhaust. Thus, there is enough tritium produced in a D- 3 He reactor and careful management will be required. The tritium produced in the shield and plasma can be managed with an acceptable effect on cost and safety. 3 refs., 2 figs., 3 tabs

  4. Tun Dr. Mahathir’s Leadership Communication: The Confucian Perspective

    Directory of Open Access Journals (Sweden)

    Cheah Joyce Lynn-Sze

    2017-01-01

    Full Text Available Previous studies have provided valuable insights into the impact of culture on the concept of leadership communication. However, only a few studies that focused on exploring and understanding the values of Confucianism and its impact on the Chinese culture, especially in Malaysia. Thus, this study is among the first study to examine the leadership communication from the perspective of Confucianism towards the leadership of Dr. Mahathir from the perspective of the Chinese community in Malaysia. This study aims to assess the role of Confucian values in Dr. Mahathir’s leadership communication. This study interviewed 15 Chinese leaders. The findings reveal that three main Confucian values are relevant to Dr. Mahathir’s leadership communication. The Confucian values are Zhi (wisdom, Xin (trust and Xiao (filial piety. This study provides a new perspective on leadership communication from the context of cultural diversity in Malaysia which emphasizes on Confucian values.

  5. Advanced reactors transition fiscal year 1995 multi-year program plan WBS 7.3

    International Nuclear Information System (INIS)

    Loika, E.F.

    1994-01-01

    This document describes in detail the work to be accomplished in FY-1995 and the out years for the Advanced Reactors Transition (WBS 7.3). This document describes specific milestones and funding profiles. Based upon the Fiscal Year 1995 Multi-Year Program Plan, DOE will provide authorization to perform the work outlined in the FY 1995 MYPP. Following direction given by the US Department of Energy (DOE) on December 15, 1993, Advanced Reactors Transition (ART), previously known as Advanced Reactors, will provide the planning and perform the necessary activities for placing the Fast Flux Test Facility (FFTF) in a radiologically and industrially safe shutdown condition. The DOE goal is to accomplish the shutdown in approximately five years. The Advanced Reactors Transition Multi-Year Program Plan, and the supporting documents; i.e., the FFTF Shutdown Program Plan and the FFTF Shutdown Project Resource Loaded Schedule (RLS), are defined for the life of the Program. During the transition period to achieve the Shutdown end-state, the facilities and systems will continue to be maintained in a safe and environmentally sound condition. Additionally, facilities that were associated with the Office of Nuclear Energy (NE) Programs, and are no longer required to support the Liquid Metal Reactor Program will be deactivated and transferred to an alternate sponsor or the Decontamination and Decommissioning (D and D) Program for final disposition, as appropriate

  6. Reactor Physics Programme

    Energy Technology Data Exchange (ETDEWEB)

    De Raedt, C

    2000-07-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

  7. Reactor Physics Programme

    International Nuclear Information System (INIS)

    De Raedt, C.

    2000-01-01

    The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

  8. Specialists' meeting on heat and mass transfer in the reactor cover gas, Harwell, England, 8-10 October 1985

    International Nuclear Information System (INIS)

    1986-07-01

    The specialists' meeting on ''Heat and Mass Transfer in the Reactor Cover Gas'' was held at Harwell, the United Kingdom, on 8-10 October 1985. It was attended by 24 participants from all IWGFR member-countries: France, the Federal Republic of Germany, India, Italy, Japan, the Union of Soviet Socialist Republics, the United Kingdom and the United States. The meeting was presided over by Dr K. Eickhoff of the United Kingdom. The following topical areas were reviewed and discussed during the meeting: 1. National review presentations on the status of activities on heat and mass transfer in the reactor cover gas - 2 papers; 2. Aerosol dynamics - 4 papers; 3. Aerosol trapping - 2 papers; 4. Heat and mass transfer through cover gas in annuli - 3 papers; 5. Radiative properties - 4 papers; 6. Modelling of cover gas - 4 papers. A separate abstract was prepared for each of these papers. On the basis of papers presented and discussed by participants, session summaries and conclusions were drafted on the above topical areas. These summaries, as well as general conclusions and recommendations of the meeting were reviewed and agreed upon by consensus at the end of the meeting

  9. DR2DI: a powerful computational tool for predicting novel drug-disease associations

    Science.gov (United States)

    Lu, Lu; Yu, Hua

    2018-05-01

    Finding the new related candidate diseases for known drugs provides an effective method for fast-speed and low-risk drug development. However, experimental identification of drug-disease associations is expensive and time-consuming. This motivates the need for developing in silico computational methods that can infer true drug-disease pairs with high confidence. In this study, we presented a novel and powerful computational tool, DR2DI, for accurately uncovering the potential associations between drugs and diseases using high-dimensional and heterogeneous omics data as information sources. Based on a unified and extended similarity kernel framework, DR2DI inferred the unknown relationships between drugs and diseases using Regularized Kernel Classifier. Importantly, DR2DI employed a semi-supervised and global learning algorithm which can be applied to uncover the diseases (drugs) associated with known and novel drugs (diseases). In silico global validation experiments showed that DR2DI significantly outperforms recent two approaches for predicting drug-disease associations. Detailed case studies further demonstrated that the therapeutic indications and side effects of drugs predicted by DR2DI could be validated by existing database records and literature, suggesting that DR2DI can be served as a useful bioinformatic tool for identifying the potential drug-disease associations and guiding drug repositioning. Our software and comparison codes are freely available at https://github.com/huayu1111/DR2DI.

  10. DR2DI: a powerful computational tool for predicting novel drug-disease associations

    Science.gov (United States)

    Lu, Lu; Yu, Hua

    2018-04-01

    Finding the new related candidate diseases for known drugs provides an effective method for fast-speed and low-risk drug development. However, experimental identification of drug-disease associations is expensive and time-consuming. This motivates the need for developing in silico computational methods that can infer true drug-disease pairs with high confidence. In this study, we presented a novel and powerful computational tool, DR2DI, for accurately uncovering the potential associations between drugs and diseases using high-dimensional and heterogeneous omics data as information sources. Based on a unified and extended similarity kernel framework, DR2DI inferred the unknown relationships between drugs and diseases using Regularized Kernel Classifier. Importantly, DR2DI employed a semi-supervised and global learning algorithm which can be applied to uncover the diseases (drugs) associated with known and novel drugs (diseases). In silico global validation experiments showed that DR2DI significantly outperforms recent two approaches for predicting drug-disease associations. Detailed case studies further demonstrated that the therapeutic indications and side effects of drugs predicted by DR2DI could be validated by existing database records and literature, suggesting that DR2DI can be served as a useful bioinformatic tool for identifying the potential drug-disease associations and guiding drug repositioning. Our software and comparison codes are freely available at https://github.com/huayu1111/DR2DI.

  11. Stop words for “Dr Math”

    CSIR Research Space (South Africa)

    Butgereit, L

    2011-05-01

    Full Text Available “Dr Math” is a facility where primary and secondary school pupils can use MXit on their cell phones to get help with their mathematics homework. Pupils use an abbreviated “MXit lingo” leaving out most vowels and substituting various numerals...

  12. Characteristics of UV-MicroO3 Reactor and Its Application to Microcystins Degradation during Surface Water Treatment

    Directory of Open Access Journals (Sweden)

    Guangcan Zhu

    2015-01-01

    Full Text Available The UV-ozone (UV-O3 process is not widely applied in wastewater and potable water treatment partly for the relatively high cost since complicated UV radiation and ozone generating systems are utilized. The UV-microozone (UV-microO3, a new advanced process that can solve the abovementioned problems, was introduced in this study. The effects of air flux, air pressure, and air humidity on generation and concentration of O3 in UV-microO3 reactor were investigated. The utilization of this UV-microO3 reactor in microcystins (MCs degradation was also carried out. Experimental results indicated that the optimum air flux in the reactor equipped with 37 mm diameter quartz tube was determined to be 18∼25 L/h for efficient O3 generation. The air pressure and humidity in UV-microO3 reactor should be low enough in order to get optimum O3 output. Moreover, microcystin-RR, YR, and LR (MC-RR, MC-YR, and MC-LR could be degraded effectively by UV-microO3 process. The degradation of different MCs was characterized by first-order reaction kinetics. The pseudofirst-order kinetic constants for MC-RR, MC-YR, and MC-LR degradation were 0.0093, 0.0215, and 0.0286 min−1, respectively. Glucose had no influence on MC degradation through UV-microO3. The UV-microO3 process is hence recommended as a suitable advanced treatment method for dissolved MCs degradation.

  13. Nuclear reactor (1960)

    International Nuclear Information System (INIS)

    Maillard, M.L.

    1960-01-01

    The first French plutonium-making reactors G1, G2 and G3 built at Marcoule research center are linked to a power plant. The G1 electrical output does not offset the energy needed for operating this reactor. On the contrary, reactors G2 and G3 will each generate a net power of 25 to 30 MW, which will go into the EDF grid. This power is relatively small, but the information obtained from operation is great and will be helpful for starting up the power reactor EDF1, EDF2 and EDF3. The paper describes how, previous to any starting-up operation, the tests performed, especially those concerned with the power plant and the pressure vessel, have helped to bring the commissioning date closer. (author) [fr

  14. Construction of Research Reactors for Gen 3 and Gen 4 Reactors Development

    International Nuclear Information System (INIS)

    Behar, Christophe

    2014-01-01

    Christophe Behar, Director of the Nuclear Energy Division at CEA, detailed the different kind of research reactors and the issues in term of investment, use, side application such as the medical isotopes production

  15. Portrait of Dr. Von Braun with Walt Disney, 1954.

    Science.gov (United States)

    1954-01-01

    Marshall Center Director Dr. Wernher Von Braun is pictured with Walt Disney during a visit to the Marshall Space Flight Center in 1954. In the 1950s, Dr. Von Braun while working in California on the Saturn project, also worked with Disney studios as a technical director in making three films about Space Exploration for television. Disney's tour of Marshall in 1965 was Von Braun's hope for a renewed public interest in the future of the Space Program at NASA.

  16. Simulation of a reactor FBR with hexagonal-Z geometry using the code PARCS 3.1

    International Nuclear Information System (INIS)

    Reyes F, M. C.; Del Valle G, E.; Filio L, C.

    2013-10-01

    The nuclear reactor core type FBR (Fast Breeder Reactor) was modeled in three dimensions of hexagonal-Z geometry using the code PARCS (Purdue Advanced Reactor Core Simulator) version 3.1 developed by Purdue University researchers. To carry out the modeling of the mentioned reactor was taken the corresponding information to one of the described benchmarks in the document NEACRP-L-330 (3-D Neutron Transport Benchmarks, 1991); fundamentally the corresponding to the geometric data and the cross sections. Being a quick reactor of breeding, known as the Knk-II, for which are considered 4 energy groups without dispersions up. The reactor core is formed by prismatic elements of hexagonal transversal cut where part of them only corresponds to nuclear fuel assemblies. This has four reflector rings and 6 identical control elements that together with the active part of the core is configured with 8 different types of elements.With the extracted information of the mentioned document the entrance file was prepared for PARCS 3.1 only considering a sixth part of the core due to the symmetry that presents their configuration. The NEACRP-L-330 shows a wide range of results reported by those who collaborated in its elaboration using different solution techniques that go from the Monte Carlo method to the approaches S 2 and P 1 . Of all the results were selected those obtained with the code HEXNOD, to which were carried out a comparison of the effective multiplication factor, being smaller differences to the 300 pcm, for three different scenarios: a) with the control bars extracted totally, b) with the semi-inserted control bars and c) with the control bars inserted completely and two different axial meshes, a thick mesh with 14 slices and another fine with 38, that which implies that the results can be considered very similar among if same. Radial maps and axial profiles are included, as much of the power as of the neutrons flow. (Author)

  17. Dr. Lindberg's Legacy : Charting A New Course | NIH MedlinePlus the Magazine

    Science.gov (United States)

    ... more. Don also created the National Center for Biotechnology Information (NCBI). NCBI has been a focal point ... with Dr. Lindberg (right) and National Center for Biotechnology Information Director Dr. David Lipman (center) at a ...

  18. 2700-IJBCS-Article-Dr Matar Seck

    African Journals Online (AJOL)

    hp

    of Maytenus senegalensis in the management of sickle cell disease. © 2016 International ... En plus de l'anémie, la vaso-occlusion, résultant de la ... crises de douleur, de la fièvre et des douleurs ... vaso-occlusives dans la drépanocytose. Ces.

  19. Practitioner Profile: An Interview with Dr. Jerry Gale, LMFT

    Directory of Open Access Journals (Sweden)

    Jerry Gale

    2012-06-01

    Full Text Available Dr. Jerry Gale is an Associate Professor and the Clinical Director of the Marriage and Family Therapy Doctoral Program at the University of Georgia. He is a Licensed Marriage and Family Therapist and an approved supervisor of the American Association of Marriage and Family Therapists. He earned a B.A. from the University of Michigan, a MEd from the University of Arizona, and a Ph.D. from Texas Tech University. Over the course of his career, Dr. Gale has authored three books and over 60 articles and book chapters. He is a co-developer of a relational financial therapy approach that combines financial counseling with family therapy and has extensive training in clinical hypnosis, couples therapy, and family therapy, as well as mindfulness meditation. He is the recipient of the American Family Therapy Academy 2006 Outstanding Research Award. In addition to his work at the University of Georgia, Dr. Gale conducts therapy at Athens Associates for Counseling and Psychotherapy.

  20. Operating experiences and utilization programmes of the BAEC 3 MW TRIGA Mark-II research reactor of Bangladesh

    International Nuclear Information System (INIS)

    Haque, M.M.; Soner, M.A.M.; Saha, P.K.; Salam, M.A.; Zulquarnain, M.A.

    2008-01-01

    The 3 MW TRIGA Mark-II research reactor of Bangladesh Atomic Energy Commission (BAEC) has been operating since September 14, 1986. The reactor is used for radioisotope production ( 131 I, 99m Tc, 46 Sc), various R and D activities, manpower training and education. The reactor has been operated successfully since its commissioning with the exception of a few reportable incidents. Of these, the decay tank leakage incident of 1997 is considered to be the most significant one. As a result of this incident, reactor operation at full power remained suspended for about 4 years. However, the reactor operation was continued during this period at a power level of 250 kW to cater the needs of various R and D groups, which required lower neutron flux for their experiments. This was made possible by establishing a temporary by pass connection across the decay tank using local technology. The reactor was made operational again at full power after successful replacement of the damaged decay tank in August 2001. At that time, several modifications of the reactor cooling system along with its associated structures were also implemented and then necessary testing and commissioning of the newly installed component/equipment were carried out. The other incident was the contamination of the Dry Central Thimble (DCT) that took place in March 2002 when a pyrex vial containing 50g of TeO 2 powder got melted inside the DCT. The vial was melted due to high heat generation on its surface while the reactor was operated for 8 hours at 3 MW for trial production of Iodine-131 ( 131 I). A Wet Central Thimble (WCT) was used to replace the damaged DCT in June 2002 such that the reactor operation could be resumed. The WCT was again replaced by a new DCT in June 2003 such that radioisotope production could be continued. The facility has so far been used to train up a total of 27 personnel including several foreign nationals to the level of Senior Reactor Operator (SRO) and Reactor Operator (RO). The

  1. Comparative study between rib imaging of DR dual energy subtraction technology and chest imaging

    International Nuclear Information System (INIS)

    Yu Jianming; Lei Ziqiao; Kong Xiangchuang

    2006-01-01

    Objective: To investigate the application value of DR dual energy subtraction technology in rib lesions. Methods: 200 patients were performed with chest DR dual energy subtraction, comparing the rib imaging between DR of thorax and chest imaging using ROC analysis. Results: Among the total of 200 patients, there are 50 cases of rib calcification, 7 cases of rib destruction, 22 cases of rib fracture. The calcification, destruction and fracture were displayed respectively by ribs below diaphragm and rib markings. The analytic parameter of rib imaging of DR dual energy subtraction Az is 0.9367, while that of rib imaging of chest Az is 0.6830. Conclusion: DR dual energy subtraction technology is superior to chest imaging in the displaying of rib lesion and ribs below diaphragm. (authors)

  2. Effect of fuel assembly when changing from AFA 2G to AFA 3G on seismic loads of reactor internal

    International Nuclear Information System (INIS)

    Liu Wenjin; Zeng Zhongxiu; Ye Xianhui; Wu Wanjun

    2013-01-01

    Nonlinear seismic model for reactor with fuel assemblies of AFA 2G and AFA 3G is established. Using ANSYS software, seismic nonlinear time -history analysis is completed and the effects on seismic loads of reactor system are obtained. The result shows that when the fuel assembly changing from AFA 2G to AFA 3G, it is necessary to reevaluate the fuel assembly itself, but not the reactor internal. (authors)

  3. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    International Nuclear Information System (INIS)

    Greene, S.R.; Fisher, S.E.; Bevard, B.B.

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative

  4. FMDP Reactor Alternative Summary Report: Volume 3 - partially complete LWR alternative

    Energy Technology Data Exchange (ETDEWEB)

    Greene, S.R.; Fisher, S.E.; Bevard, B.B. [and others

    1996-09-01

    The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 3 of a four volume report summarizes the results of these analyses for the partially complete LWR (PCLWR) reactor based plutonium disposition alternative.

  5. Dr. Tulga Ersal at NSF Workshop Accessible Remote Testbeds ART'15

    Science.gov (United States)

    Event Archives Dr. Tulga Ersal at NSF Workshop Accessible Remote Testbeds ART'15 On November 12th, Dr Workshop on Accessible Remote Testbeds (ART'15) at Georgia Tech. From the event website: The rationale behind the ART'15 workshop is that remote-access testbeds could, if done right, significantly change how

  6. HLA class II (DR, DQ, DP) in patients with sarcoidosis: evidence of an increased frequency of DRw6

    DEFF Research Database (Denmark)

    Ødum, Niels; Milman, N; Jakobsen, B K

    1991-01-01

    using primed lymphocyte typing. The frequencies of DRw6 were 41.5% in SA patients and 17.9% in controls (relative risk, RR = 3.2, p = 0.00087, p less than 0.05 when corrected). DR3 was decreased to 14.6% in SA patients compared to 25.9% in controls (RR = 0.49, p = 0.07, i.e., not statistically...... significant). The decreased frequency of DR3 was only seen in patients with severe, long-standing disease. In contrast, the DRw6 increase was most pronounced in patients with severe disease (RR = 6.4; p = 0.003). There were no statistically significant deviations in the frequencies of DQ and DP alleles...

  7. Modelling and thermal hydraulic analysis of the Angra-2 nuclear reactor using RELAP5-3D code

    International Nuclear Information System (INIS)

    González Mantecón, Javier

    2015-01-01

    The evaluation of Nuclear Power Plants (NPPs) performance during steady-state and accident conditions has been one of the main research subjects in the nuclear field. In order to simulate the behavior of water-cooled reactors, several complex thermal-hydraulic codes systems have been developed. Particularly, the RELAP5 code, developed by the Idaho National Laboratory, is a best-estimate thermal-hydraulic analysis tool and one of the most used in nuclear industry. The RELAP5-3D 3.0.0 code was used to develop a detailed model of Angra 2 nuclear reactor using reference data from the Final Safety Analysis Report. Angra 2 is the second Brazilian NPP, which began commercial operation in 2001. The plant is equipped with a Pressurized Water Reactor (PWR) type with 3771.0 MWt. Simulations of the reactor behavior during normal operation conditions and postulated accident conditions were performed. Results achieved in the reactor steady-state simulation were compared with nominal parameters of the NPP. These results proved to be in good agreement, with relative errors less than 1%. In the transient simulation, the obtained results were coherent and satisfactory. This study demonstrates that the RELAP5-3D model is capable to reproduce the thermal-hydraulic behavior of the Angra-2 PWR during diverse operation conditions and it can contribute for the process of the plant safety analysis. (author)

  8. Summary of ORSphere Critical and Reactor Physics Measurements

    Energy Technology Data Exchange (ETDEWEB)

    Marshall, Margaret A.; Bess, John D.

    2016-09-01

    In the early 1970s Dr. John T. Mihalczo (team leader), J. J. Lynn, and J. R. Taylor performed experiments at the Oak Ridge Critical Experiments Facility (ORCEF) with highly enriched uranium (HEU) metal (called Oak Ridge Alloy or ORALLOY) to recreate GODIVA I results with greater accuracy than those performed at Los Alamos National Laboratory in the 1950s. The purpose of the Oak Ridge ORALLOY Sphere (ORSphere) experiments was to estimate the unreflected and unmoderated critical mass of an idealized sphere of uranium metal corrected to a density, purity, and enrichment such that it could be compared with the GODIVA I experiments. This critical configuration has been evaluated. Preliminary results were presented at ND2013. Since then, the evaluation was finalized and judged to be an acceptable benchmark experiment for the International Criticality Safety Benchmark Experiment Project (ICSBEP). Additionally, reactor physics measurements were performed to determine surface button worths, central void worth, delayed neutron fraction, prompt neutron decay constant, fission density and neutron importance. These measurements have been evaluated and found to be acceptable experiments and are discussed in full detail in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. The purpose of this paper is summary summarize all the critical and reactor physics measurements evaluations and, when possible, to compare them to GODIVA experiment results.

  9. Summary of Symposium on Cloud Systems, Hurricanes and TRMM: Celebration of Dr. Joanne Simpson's Career, The First Fifty Years

    Science.gov (United States)

    Tao, W.-K.; Adler, R.; Braun, S.; Einaudi, F.; Ferrier, B.; Halverson, J.; Heymsfield, G.; Kummerow, C.; Negri, A.; Kakar, R.; hide

    2000-01-01

    A symposium celebrating the first 50 years of Dr. Joanne Simpson's career took place at the NASA/Goddard Space Flight Center from December 1 - 3, 1999. This symposium consisted of presentations that focused on: historical and personal points of view concerning Dr. Simpson's research career, her interactions with the American Meteorological Society, and her leadership in TRMM; scientific interactions with Dr. Simpson that influenced personal research; research related to observations and modeling of clouds, cloud systems and hurricanes; and research related to the Tropical Rainfall Measuring Mission (TRMM). There were a total of 36 presentations and 103 participants from the US, Japan and Australia. The specific presentations during the symposium are summarized in this paper.

  10. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    International Nuclear Information System (INIS)

    2014-02-01

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)

  11. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2005

    International Nuclear Information System (INIS)

    2007-03-01

    In the fiscal year 2005, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation : 137 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography. Irradiation for activation analyses, radioisotope (RI) productions, fission tracks. Irradiation test of reactor materials etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT). Prompt gamma-ray analyses. Sensitivity measurement of radiation detectors. Experiment in the nuclear reactor training. Practice of Reactor operation. Irradiation for activation analyses, RI productions, fission tracks etc. The volume contains 100 activity reports, which are categorized into the fields of neutron scattering (9 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  12. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2006

    International Nuclear Information System (INIS)

    2009-01-01

    In the fiscal year 2006, the research reactor JRR-3 was operated 7 cycles (cycle operation: 26 days/cycle) for utilization sharing of the facility. And JRR-4 was operated 37 cycles (daily operation: 151 days). JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. The volume contains 294 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, neutron activation analyses, RI productions, prompt gamma-ray analyses, and others submitted by the users in JAEA and from other organizations. (author)

  13. Activity report on the utilization of research reactors (JRR-3 and JRR-4). Japanese fiscal year, 2009

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2014-02-15

    JRR-3 is used for the purposes below; Experimental studies such as neutron scattering, prompt gamma-ray analyses, neutron radiography, Irradiation for activation analyses, radioisotope (RI) productions, fission tracks, Irradiation test of reactor materials, etc. JRR-4 is used for the purposes below; Medical irradiation (Boron Neutron Capture Therapy : BNCT), Prompt gamma-ray analyses, Sensitivity measurement of radiation detectors, Experiment in the nuclear reactor training, Practice of Reactor operation, Irradiation for activation analyses, RI productions, fission tracks, etc. In the fiscal year 2009, The research reactor JRR-3 was operated 7 cycles (cycle operation : 26days/cycle) for utilization sharing of the facility. And JRR-4 was operated 6 cycles (daily operation : 24 days). The volume contains 138 activity reports, which are categorized into the fields of neutron scattering (11 subcategories), neutron radiography, prompt gamma-ray analyses, neutron activation analyses, RI productions, and others submitted by the users in JAEA and from other organizations. (author)

  14. A 3D transport-based core analysis code for research reactors with unstructured geometry

    International Nuclear Information System (INIS)

    Zhang, Tengfei; Wu, Hongchun; Zheng, Youqi; Cao, Liangzhi; Li, Yunzhao

    2013-01-01

    Highlights: • A core analysis code package based on 3D neutron transport calculation in complex geometry is developed. • The fine considerations on flux mapping, control rod effects and isotope depletion are modeled. • The code is proved to be with high accuracy and capable of handling flexible operational cases for research reactors. - Abstract: As an effort to enhance the accuracy in simulating the operations of research reactors, a 3D transport core analysis code system named REFT was developed. HELIOS is employed due to the flexibility of describing complex geometry. A 3D triangular nodal S N method transport solver, DNTR, endows the package the capability of modeling cores with unstructured geometry assemblies. A series of dedicated methods were introduced to meet the requirements of research reactor simulations. Afterwards, to make it more user friendly, a graphical user interface was also developed for REFT. In order to validate the developed code system, the calculated results were compared with the experimental results. Both the numerical and experimental results are in close agreement with each other, with the relative errors of k eff being less than 0.5%. Results for depletion calculations were also verified by comparing them with the experimental data and acceptable consistency was observed in results

  15. Resistensi dan Sensitivitas Bakteri terhadap Antibiotik di RSU dr. Soedarso Pontianak Tahun 2011-2013

    Directory of Open Access Journals (Sweden)

    Nurmala Nurmala

    2015-09-01

    Full Text Available Normal 0 false false false IN X-NONE X-NONE MicrosoftInternetExplorer4 Salah satu upaya untuk mengurangi resistensi, pemberian antibiotik harus berdasarkan pola bakteri penyebab infeksi dan kepekaan bakteri terhadap antibiotik. Tujuan penelitian ini untukmengetahui pola bakteri, resistensi dan sensitivitasnya terhadap antibiotik di RSU dr. SoedarsoPontianak tahun 2011-2013. Penelitian deskriptif dengan pendekatan retrospektif dilakukan RSU dr. Soedarso, Pontianak. Sampel penelitian adalah hasil pemeriksaan kultur dan uji kepekaan spesimen pus pasien yang diperiksa di Bagian Mikrobiologi Unit Labolatorium Kesehatan (ULK. Dari 111 sampel,terdapat 21 jenis bakteri. Bakteri gram-negatif lebih banyak dari gram-positif, yaitu 70,7% dan 29,3%.Tiga bakteri terbanyak adalah Citrobacter freundii (18%, P. aeruginosa (17,1% dan Staphylococcusepidermidis (15,3%. Resistensi tertinggi bakteri adalah terhadap metronidazol (96,4%, sefaleksin(95,8%, sefuroksim (92,2%, oksasilin (91,7% dan sefadroksil (91,5% dan sensitivitas tertinggibakteri terhadap piperasilin/tozobaktam (89,7%, meropenem (82,9%, imepenem (78,1%, amikasin(76,3%, fosfomisin/trometamol (59,5% dan levofloksasin (56,1%. Kata kunci: bakteri, antibiotik, resistensi, sensitivitas, pus. Resistance and Sensitivity of Bacteria to Antibioticsat dr. Soedarso Hospital Pontianak 2011-2013 Abstract An effort to reduce resistance, antibiotics prescription should be based on information about pattern of bacteria and  sensitivity to antibiotics. The aim of the study is to  determine the patternof bacteria, resistance and sensitivity to antibiotics at dr. Soedarso Hospital Pontianak 2011-2013. This research is a descriptive study with retrospective approach. Samples were culture and sensitivity test result in pus specimen of dr. Soedarso Hospital patient’s examined at ULK. Thenumber of samples in this study were 111 samples. There were 21 type of bacterias. Gram-negativebacterias were found more than gram

  16. Verification of using SABINE-3.1 code for calculations of radioactive inventory in reactor shield

    International Nuclear Information System (INIS)

    Moukhamadeev, R.; Suvorov, A.

    2000-01-01

    This report presents the results of calculations of radioactive inventory and doses of activation radiation for the International Benchmark Calculations of Radioactive Inventory for Fission Reactor Decommissioning, IAEA, and measurements of activation doses in shield of WWER-440 (Armenian NPP), using one-dimension modified code SABINE-3.1. For decommissioning of NPP it is very important to evaluate in correct manner radioactive inventory in reactor construction and shield materials. One-dimension code SABINE-3.1 (removing-diffusion method for neutron calculation) was modified to perform calculation of radioactive inventory in reactor shield materials and dose from activation photons behind them. These calculations are carried out on the base of nuclear constant system ABBN-78 and new library of activation data for a number of long-lived isotopes, prepared by authors on the base of [9], which present at shield materials as microimpurities and manage radiation situation under the decay more than 1 year. (Authors)

  17. PROFIL LEUKOKORIA PADA ANAK DI RSUP Dr. M. DJAMIL PADANG

    Directory of Open Access Journals (Sweden)

    Kemala Sayuti

    2014-05-01

    Full Text Available AbstrakTujuan penelitian ini ialah menilai penyebab leukokoria pada pasien anak di RSUP Dr. M. Djamil Padang dengan rancang studi cross sectional. Data dikumpulkan dari medical record pasien dengan riwayat leukokoria atau pupil putih yang berusia kurang dari 13 tahun di bagian mata RSUP Dr M Djamil Padang periode Oktober 2009 Februari 2011. Diagnosis banding disingkirkan melalui pemeriksaan USG dan patologi. Dari 36 pasien dengan leukokoria, 21 orang (58,3% laki-laki dan umur rata-rata 31,3 bulan. Penyebab leukokoria adalah retinoblastoma 12 pasien (33,4%, tiga diantaranya bilateral, katarak kongenital 11 pasien (30,5%, delapan diantaranya bilateral, katarak traumatika 5 pasien (13,8%, uveitis intra uterin 2 pasien (5,5%, keduanya bilateral, dan ROP 2 pasien (5,5%, satu diantaranya bilateral. Kami juga menemukan penyebab lain, masing-masing satu pasien dengan leukokoria unilateral, antara lain: PHPV (2,7%, endoftalmitis eksogen (2,7%, uveitis anterior (2,7%, dan glioma nervus optikus (2,7%. Sangat krusial mengetahui perbedaan gambaran klinik retinoblastoma dan katarak kongenital, karena pengobatannya berbeda, dan retinoblastoma mengancam kehidupan, sedangkan katarak kongenital mengancam penglihatan.AbstractThe objective of this study was to determine the etiology of leukocoria in children using cross sectional study conducted in eye clinic of Dr. M. Djamil Hospital Padang. Samples were taken from medical records of patients with children leukocoria during the period of October 2009 to February 2011. Differential diagnosis eliminated by USG and pathology examination. There were 36 children with leukocoria in total, 21 of them were boys (58,3%. The mean age was 31.3 months old. The causes of leukocoria were retinoblastoma in 12 patients (33,4% three of them were bilateral, followed respectively by congenital cataract in 11 patients (30.5% which 8 of them were bilateral, traumatic cataract in 5 patients (13.8%, intrauterine uveitis in 2 patients (5

  18. Sub-critical crack growth and clad integrity in a PWR reactor pressure vessel

    International Nuclear Information System (INIS)

    Tice, D.R.; Foreman, A.J.E.; Sharples, J.K.

    1987-10-01

    The possibility of in-service growth of sub-critical defects in a PWR reactor pressure vessel to a critical size which could result in vessel failure was addressed in both the 1976 and 1982 reports of the Light Water Reactor Study Group (LWRSG), under the Chairmanship of Dr W Marshall (now Lord Marshall). An addendum to this report was published by UKAEA in April 1987. The section of the addendum dealing with subcritical crack growth and the related issue of integrity of the stainless steel cladding on the inner vessel surface is reproduced in this report. This section of the LWRSG addendum provides a review of the current status of fatigue crack growth and environmentally assisted cracking research for pressure vessel steels in light water reactor environments, as well as a review of developments in crack growth assessment methods. The review concludes that the alternative assessment procedures now being developed give a more realistic prediction of in service crack growth than the ASME Section XI Appendix A fatigue crack growth curves. (author)

  19. Dr. Ding Hou 80 years young

    NARCIS (Netherlands)

    Baas, Pieter; Adema, Frits

    2001-01-01

    Eleven October 2001 is the 80th birthday of Dr. Ding Hou, much appreciated Honorary Staff Member of our Nationaal Herbarium Nederland. Time to reflect on the life and career of this modest but highly productive and talented botanist. Ding Hou was born in 1921 in Hsingkan, Kiangsi Province, China.

  20. Drømmefabrikken

    Directory of Open Access Journals (Sweden)

    Paulo Affonso Grisolli

    1994-09-01

    Full Text Available Som mangeårig producent af telenovelaer både i Brasilien og Portugal, kender Grisolli alle sider af telenovelaen: Novelaen som de fattiges drøm om rigdom og succes, novelaen som et redskab i TV-kanalernes kamp om seerne, som exportvare, som glansbillede under det brasillianske dik- tatur, som industriprodukt og som politisk igangsætter. I denne artikel be- skriver Grisolli sine erfaringer med gode og dårlige sider af telenovela- fascinationen i Latinamerika og præsenterer en ny genre, som er på vej frem i Brasilien, mini-serien. Artiklen er Grisollis foredrag på Folkekirkens Nødhjælps Konference om TV og Video i Latinamerika, november 1992.

  1. ASAMPSA2 best-practices guidelines for L2 PSA development and applications. Volume 3 - Extension to Gen IV reactors

    International Nuclear Information System (INIS)

    Bassi, C.; Bonneville, H.; Brinkman, H.; Burgazzi, L.; Polidoro, F.; Vincon, L.; Jouve, S.

    2010-01-01

    The main objective assigned to the Work Package 4 (WP4) of the 'ASAMPSA2' project (EC 7. FPRD) consist in the verification of the potential compliance of L2PSA guidelines based on PWR/BWR reactors (which are specific tasks of WP2 and WP3) with Generation IV representative concepts. Therefore, in order to exhibit potential discrepancies between LWRs and new reactor types, the following work was based on the up-to-date designs of: - The European Fast Reactor (EFR) which will be considered as prototypical of a pool-type Sodium-cooled Fast Reactor (SFR); - The ELSY design for the Lead-cooled Fast Reactor (LFR) technology; - The ANTARES project which could be representative of a Very-High Temperature Reactor (VHTR); - The CEA 2400 MWth Gas-cooled Fast Reactor (GFR). (authors)

  2. Plutonium-burn high temperature gas-cooled reactor for 3E+3S

    International Nuclear Information System (INIS)

    Okamoto, Koji

    2015-01-01

    The Nuclear Energy Development in Japan is facing a very difficult conditions after Fukushima-Daiichi NPP Accident. Nuclear Energy has strong advantages on 3E, i.e., Energy security, Economical efficiency and Environment. However, people does not believe the Safety 'S' of Nuclear Energy, now. The disadvantage of 'S' overrides the advantages of '3E'. In Nuclear Energy, 'S' is expanded into 3S, i.e., Safety, Security and Safeguards. Especially, the management of Plutonium inventory in Spent Fuel generated by the NPP operation is very important in the viewpoints of non-proliferation. The high-temperature gas cooled reactor (HTGR) is the solution of these disadvantages of '3S' in Nuclear Energy. The fuel of HTGR is composed by 1 mm spherical fuel particle, i.e., TRISO made by fuel, graphite and silicon-carbide. The silicon-carbide can confine the fission products in any conditions of fuel life cycle, i.e., during operation, accidents and disposal for 1 million years. The confinement of the radioactive materials can be confirmed by the TRISO. The HTGR core has strong negative feedback for temperature. So, the fission automatically stopped at the accidental conditions, such as loss of flow and LOCA. Also, the residual heat can be cooled by the radiation heat transfer to reactor vessel wall. The HTGR system usually has passive vessel wall cooling system. When the passive cooling system had been failed, the heat can be transferred to the land by heat conductions, and fuel does not reach the SiC broken temperature. The fission chain reaction has been stopped automatically by negative feedback, i.e., physics. The residual heat had been cooled automatically by radiation. The radioactive materials had been confined automatically by silicon-carbide. The HTGR is superior for 'S' safety. Plutonium can be burned by the HTGR. In the viewpoints of non-proliferation, the fuel should be made by YSZ-PuO 2 , stabilized buffer

  3. Mathematical Modelling of Catalytic Fixed-Bed Reactor for Carbon Dioxide Reforming of Methane over Rh/Al2O3 Catalyst

    Directory of Open Access Journals (Sweden)

    New Pei Yee

    2008-04-01

    Full Text Available A one-dimensional mathematical model was developed to simulate the performance of catalytic fixed bedreactor for carbon dioxide reforming of methane over Rh/Al2O3 catalyst at atmospheric pressure. The reactionsinvolved in the system are carbon dioxide reforming of methane (CORM and reverse water gas shiftreaction (RWGS. The profiles of CH4 and CO2 conversions, CO and H2 yields, molar flow rate and molefraction of all species as well as reactor temperature along the axial bed of catalyst were simulated. In addition,the effects of different reactor temperature on the reactor performance were also studied. The modelscan also be applied to analyze the performances of lab-scale micro reactor as well as pilot-plant scale reactorwith certain modifications and model verification with experimental data. © 2008 BCREC UNDIP. All rights reserved.[Received: 20 August 2008; Accepted: 25 September 2008][How to Cite: N.A.S. Amin, I. Istadi, N.P. Yee. (2008. Mathematical Modelling of Catalytic Fixed-Bed Reactor for Carbon Dioxide Reforming of Methane over Rh/Al2O3 Catalyst. Bulletin of Chemical Reaction Engineering and Catalysis, 3 (1-3: 21-29. doi:10.9767/bcrec.3.1-3.19.21-29

  4. The life and contribution of Dr. Ronald Gitelman: a pioneer of modern chiropractic science.

    Science.gov (United States)

    Vernon, Howard

    2013-03-01

    The life and contribution to chiropractic science of Dr. Ronald Gitelman is reviewed. Sources for this article included review of the notes prepared by Dr. Joseph Keating in his "biography" of the Canadian Memorial Chiropractic College (CMCC); review of the important articles published by Dr. Gitelman; review of the important projects undertaken by him along with various colleagues; notes from reminiscences obtained from many of these colleagues and discussions with his family. Dr. Gitelman's academic career spanned from 1963 to the late 1980's. During that time, he made foundational contributions to the development of chiropractic science including: developing the Archives (1974), the first collection of scientific articles supporting chiropractic science (which was subsequently published as the Chiropractic Archives Research Collection (CRAC)); delivering one of the few chiropractic papers at the seminal NINCDS conference (1975) and, developing the collaboration between CMCC and Dr. Kirkaldy-Willis at the University of Saskatoon (1976). He practiced in Toronto from 1961 to 2007. Dr. Gitelman was a pioneer in the development of chiropractic science. He died on October 7, 2012.

  5. [Sexuality education on the Internet : From Dr. Sommer to Dr. Google].

    Science.gov (United States)

    Döring, Nicola

    2017-09-01

    Female and male adolescents in Germany are increasingly using the Internet to find information about sexuality and sexual health. This review paper summarizes what we know about the status quo of online sexuality education in Germany.Based on a systematic literature review including 40 papers from international, peer-reviewed journals spanning 2010-2017, this paper first describes different aspects of the sexuality-related online search behavior of adolescents: its prevalence, predictors, topics and contexts. One main finding is the fact that adolescents use a computer or smartphone to type their sexuality-related questions into the search engine Google or the search engine of the video platform YouTube.Based on 54 online searches, this paper subsequently presents the kind of sexuality-related online content adolescents find if they ask "Dr. Google" for sexual advice; a collection of 1236 authentic sexuality-related questions of adolescents was used for this analysis. It turned out that online sexuality education offered by leading professional organizations like the BZgA ("Bundeszentrale für gesundheitliche Aufklärung") or pro familia was nearly invisible, while numerous other providers of online sex education consistently appeared in the top Google search results. Among them were the "Dr. Sommer" team of the youth magazine Bravo; online healthcare and advice portals; online forums; the online encyclopedia Wikipedia and, above all, sex education channels on YouTube. In this paper, the latter are presented in more detail for the first time.The third part of the paper addresses the quality of online sexual education over four main areas of quality evaluation. The presentation of the status quo ends with some recommendations both for future research and for sexuality education in practice.

  6. Collective occupational dose for nuclear reactors of the 2., 3. and 4. generation

    International Nuclear Information System (INIS)

    Guidez, J.; Saturnin, A.

    2016-01-01

    In France during reactor operation the individual occupational doses are collected and recorded according to the law. When you sum up all the individual doses you get the yearly collective dose expressed in Man.Sv/year. This piece of information can be used to make comparisons between various types of reactors and between reactors of the same type. The results show a steady decrease of the collective dose for all types of reactors over the time except for CANDU reactors for which a slight increase of the dose has appeared since the years 1996-1998. The decrease is due to the continuous improvement of reactor operating and to changes in the reactor design. There is also a constant gap over time between the collective dose for a BWR reactor (1.12 Man.Sv/y) and a PWR reactor 0.60 Man.Sv/y), this gap is certainly due to N 16 nuclide that is created in the primary circuit and transported to turbines in the case of a BWR reactor. For sodium-cooled fast reactors (RNR-Na) the collective dose is below 0.40 Man.Sv/y except for the BN-600 reactor. (A.C.)

  7. Words of gratitude to Dr. Michel Huguet

    International Nuclear Information System (INIS)

    Yoshikawa, Masaji

    2003-01-01

    It is impossible for the Japanese fusion community, in particular for those associated with the ITER Project,to hear about the retirement of Dr. Michel Huguet without a great amount of gratitude, recollections, warm feelings, and the inevitable sadness. He was a first-generation ITER EDA person. Three months after the signing of the ITER EDA Agreement in July 1992, he arrived at the Naka Joint Work Site as Deputy Director of the ITER Central Team and Head of the site and he stayed for more than ten years. The Naka site was for design and technical co-ordination in the areas of magnets, plasma control and heating, plant systems, buildings, etc. Dr. Huguet was considered a highly qualified person to fill the position, since he had been successful as Deputy Director in similar areas in the JET Joint Undertaking. During the ITER EDA he co-ordinated the R and D activities in areas for which the Naka Joint Work Site was responsible. These R and D results permitted the completion of the ITER design in the above areas under his supervision. We thank Dr. Huguet for his achievements and contributions to ITER. He played a crucial role in establishing the convincing scientific and technical basis for ITER implementation. This was only made possible by his broad abilities and his dedication to the cause of fusion in general and ITER in particular

  8. HLA-DR-specific suppressor cells after repeated allogeneic sensitizations of human lymphocytes in vitro

    International Nuclear Information System (INIS)

    Sasportes, M.; Fradelizi, D.; Dausset, J.

    1978-01-01

    In conclusion, DR-specific suppressor cells can be induced by repeated in vitro sensitizations. They were able to decrease a secondary proliferation, to suppress consistently, in a primary proliferative assay, when added as third cells (primed twice against a DR antigen [PLT II] and γ-irradiated), the response of unprimed cells towards stimulating cells, which share a DR specificity with the priming cell of the PLT II. The suppression follows the D part of the recombinant haplotype within an HLA-B/D recombinant family and is specific for the DR antigen used twice as stimulator for production of the PLT II

  9. RA Reactor operation and maintenance (I-IX), Part IV, Task 3.08/04, Refurbishment of the RA reactor

    International Nuclear Information System (INIS)

    Zecevic, V.

    1963-12-01

    This volume contains reports describing maintenance and repair work of the RA reactor instrumentation, equipment of the reactor dosimetry control system, and equipment for regulation and control systems

  10. Polymorphism at Expressed DQ and DR Loci in Five Common Equine MHC Haplotypes

    Science.gov (United States)

    Miller, Donald; Tallmadge, Rebecca L.; Binns, Matthew; Zhu, Baoli; Mohamoud, Yasmin Ali; Ahmed, Ayeda; Brooks, Samantha A.; Antczak, Douglas F.

    2016-01-01

    The polymorphism of Major Histocompatibility Complex (MHC) class II DQ and DR genes in five common Equine Leukocyte Antigen (ELA) haplotypes was determined through sequencing of mRNA transcripts isolated from lymphocytes of eight ELA homozygous horses. Ten expressed MHC class II genes were detected in horses of the ELA-A3 haplotype carried by the donor horses of the equine Bacterial Artificial Chromosome (BAC) library and the reference genome sequence: four DR genes and six DQ genes. The other four ELA haplotypes contained at least eight expressed polymorphic MHC class II loci. Next Generation Sequencing (NGS) of genomic DNA of these four MHC haplotypes revealed stop codons in the DQA3 gene in the ELA-A2, ELA-A5, and ELA-A9 haplotypes. Few NGS reads were obtained for the other MHC class II genes that were not amplified in these horses. The amino acid sequences across haplotypes contained locus-specific residues, and the locus clusters produced by phylogenetic analysis were well supported. The MHC class II alleles within the five tested haplotypes were largely non-overlapping between haplotypes. The complement of equine MHC class II DQ and DR genes appears to be well conserved between haplotypes, in contrast to the recently described variation in class I gene loci between equine MHC haplotypes. The identification of allelic series of equine MHC class II loci will aid comparative studies of mammalian MHC conservation and evolution and may also help to interpret associations between the equine MHC class II region and diseases of the horse. PMID:27889800

  11. Safeguarding research reactors

    International Nuclear Information System (INIS)

    Powers, J.A.

    1983-03-01

    The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

  12. Reactor noise analysis of experimental fast reactor 'JOYO'

    International Nuclear Information System (INIS)

    Ohtani, Hideji; Yamamoto, Hisashi

    1980-01-01

    As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

  13. Dr. Francis Collins Is New NIH Director

    Science.gov (United States)

    ... Ph.D., a physician and geneticist, is the new Director of the National Institutes of Health (NIH), part of the U.S. Department of Health and Human Services. President Barack Obama nominated Dr. Collins, who served as Director of ...

  14. Reactor safety study applied to the Forsmark 3 Power Plant

    International Nuclear Information System (INIS)

    Ericsson, G.; Tiren, L.I.

    1978-01-01

    A reactor safety study of the Forsmark 3 BWR power plant has been carried out for the purpose of calculating core melt probabilities using WASH-1400 methods. A sensitivity analysis shows that the calculated core melt probability is changed by approximately a factor of 10 depending on assumptions made with respect to the probability of human error. The importance of the availability of off-site power and the influence of common cause failure is also discussed. (author)

  15. In Memoriam Dr. J. H. Kern

    NARCIS (Netherlands)

    Kalkman, C.

    1974-01-01

    On 29 July 1974 dr. J. H. Kern died at the age of 70. At the occasion of his official retirement from the Rijksherbarium staff (January 1969) Van Steenis and Van Ooststroom gave due recognition to his achievements in tropical botany and to his share in the progress of the knowledge of the Dutch

  16. Effect of increasing nitrobenzene loading rates on the performance of anaerobic migrating blanket reactor and sequential anaerobic migrating blanket reactor/completely stirred tank reactor system

    International Nuclear Information System (INIS)

    Kuscu, Ozlem Selcuk; Sponza, Delia Teresa

    2009-01-01

    A laboratory scale anaerobic migrating blanket reactor (AMBR) reactor was operated at nitrobenzene (NB) loading rates increasing from 3.33 to 66.67 g NB/m 3 day and at a constant hydraulic retention time (HRT) of 6 days to observe the effects of increasing NB concentrations on chemical oxygen demand (COD), NB removal efficiencies, bicarbonate alkalinity, volatile fatty acid (VFA) accumulation and methane gas percentage. Moreover, the effect of an aerobic completely stirred tank reactor (CSTR) reactor, following the anaerobic reactor, on treatment efficiencies was also investigated. Approximately 91-94% COD removal efficiencies were observed up to a NB loading rate of 30.00 g/m 3 day in the AMBR reactor. The COD removal efficiencies decreased from 91% to 85% at a NB loading rate of 66.67 g/m 3 day. NB removal efficiencies were approximately 100% at all NB loading rates. The maximum total gas, methane gas productions and methane percentage were found to be 4.1, 2.6 l/day and 59%, respectively, at a NB loading rate of 30.00 g/m 3 day. The optimum pH values were found to be between 7.2 and 8.4 for maximum methanogenesis. The total volatile fatty acid (TVFA) concentrations in the effluent were 110 and 70 mg/l in the first and second compartments at NB loading rates as high as 66.67 and 6.67 g/m 3 day, respectively, while they were measured as zero in the effluent of the AMBR reactor. In this study, from 180 mg/l NB 66 mg/l aniline was produced in the anaerobic reactor while aniline was completely removed and transformed to 2 mg/l of cathechol in the aerobic CSTR reactor. Overall COD removal efficiencies were found to be 95% and 99% for NB loading rates of 3.33 and 66.67 g/m 3 day in the sequential anaerobic AMBR/aerobic CSTR reactor system, respectively. The toxicity tests performed with Photobacterium phosphoreum (LCK 480, LUMIStox) and Daphnia magna showed that the toxicity decreased with anaerobic/aerobic sequential reactor system from the influent, anaerobic and to

  17. The first critical experiment with a new type of fuel assemblies IRT-3M on the training reactor VR-I

    International Nuclear Information System (INIS)

    Matejka, Karel; Sklenka, Lubomir

    1997-01-01

    The paper 'The first critical experiment with a new type of fuel assemblies IRT-3M on training reactor VR-1 presents basic information about the replacement of fuel on the reactor VR-1 run on FJFI CVUT in Prague. In spring 1997 the IRT-2M fuel type used till then was replaced by the IRT-3M type. When the fuel was replaced, no change in its enrichment was made, i.e. its level remained as 36% 235 U. The replacement itself was carried out in tight co-operation with the Nuclear Research Institute Rez plc., as related to the operation of the research reactor LVR-15. The fuel replacement on the VR-I reactor is a part of the international program RERTR (Reduced Enrichment for Research and Test Reactors) in which the Czech Republic participates. (author)

  18. Evaluation on activation activity of reactor in JRR-2 applied 3 dimensional model to neutron flux calculation

    International Nuclear Information System (INIS)

    Kishimoto, Katsumi; Arigane, Kenji

    2005-03-01

    Revaluation to activation activity of reactor evaluated at the notification of dismantling submitted in 1997 was carried out in JRR-2 where decommissioning was advanced now. In the revaluation, estimation accuracy on neutron streaming at various horizontal experimental tubes was improved by applying 3 dimensional model to neutron transport calculation that had been carried out by 2 dimensional model, and calculating with TORT. As the result, excessive overestimations on horizontal experimental tubes and biological shield that had greatly contributed to total activation activity in evaluation at the notification of dismantling was revised, sum of their activation activities in the revaluation decreased to 1/18 (case after 1 year from the permanent shutdown of reactor) of evaluation at the notification of dismantling, and the structural materials that had large activation activity were changed. By the above, it was shown that introducing 3 dimensional model was effective in evaluation on activation activity of the research reactor that had a lot of various experimental tubes. Total activation activity of reactor by the revaluation depended on control rods, thermal shield plates and horizontal experimental tubes, and the value after 1 year from the permanent shutdown of reactor was 1.9x10 14 Bq. (author)

  19. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  20. Simulation software of 3-D two-neutron energy groups for ship reactor with hexagonal fuel subassembly

    International Nuclear Information System (INIS)

    Zhang Fan; Cai Zhangsheng; Yu Lei; Gui Xuewen

    2005-01-01

    Core simulation software for 3-D two-neutron energy groups is developed. This software is used to simulate the ship reactor with hexagonal fuel subassembly after 10, 150 and 200 burnup days, considering the hydraulic and thermal feedback. It accurately simulates the characteristics of the fast and thermal neutrons and the detailed power distribution in a reactor under normal and abnormal operation condition. (authors)