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.

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

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

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.

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

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

Submersion-Subcritical Safe Space (S4) reactor

International Nuclear Information System (INIS)

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

2006-01-01

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

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

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

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

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

Reactor Power Meter type SG-8

Energy Technology Data Exchange (ETDEWEB)

Glowacki, S W

1981-01-01

The report describes the principle and electronic circuits of the Reactor Power Meter type SG-8. The gamma radiation caused by the activity of the reactor first cooling circuit affectes the ionization chamber being the detector of the instrument. The output detector signal direct current is converted into the frequency of electric pulses by means of the current-to-frequency converter. The output converter frequency is measured by the digital frequency meter: the number of measured digits in time unit is proportional to the reactor power.

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)

Successful Collaborations with Dr. S. Raman in Research on Nuclear Data in Japan

International Nuclear Information System (INIS)

Mizumoto, Motoharu

2005-01-01

Since the early 1970s, Dr. Raman visited Japan many times and established a good and fruitful relationship with many scientists from universities and institutions in Japan. Many Japanese scientists, in particular young researchers, also worked together with him at Oak Ridge National Laboratory (ORNL). Through this successful collaboration, we made various achievements in the nuclear data and nuclear physics fields. Japanese researchers all remember Dr. Raman as a very active and warmhearted person. In this paper, some of the results that Dr. Raman established by collaborating with Japanese scientists will be presented

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.

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.

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

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

redMaPPer. I. Algorithm and SDSS DR8 catalog

Energy Technology Data Exchange (ETDEWEB)

Rykoff, E. S.; Rozo, E.; Reddick, R.; Wechsler, R. H. [SLAC National Accelerator Laboratory, Menlo Park, CA 94025 (United States); Busha, M. T. [Institute for Theoretical Physics, University of Zürich, 8057 Zürich (Switzerland); Cunha, C. E. [Kavli Institute for Particle Astrophysics and Cosmology, Stanford University, Palo Alto, CA 94305 (United States); Finoguenov, A. [Department of Physics, University of Helsinki, FI-00014 Helsinki (Finland); Evrard, A.; Koester, B. P. [Physics Department, University of Michigan, Ann Arbor, MI 48109 (United States); Hao, J.; Nord, B. [Center for Particle Astrophysics, Fermi National Accelerator Laboratory, Batavia, IL 60510 (United States); Leauthaud, A. [Kavli Institute for the Physics and Mathematics of the Universe, University of Tokyo, Kashiwa 277-8583 (Japan); Pierre, M.; Sadibekova, T. [Service d' Astrophysique, CEA Saclay, F-91191 Gif sur Yvette Cedex (France); Sheldon, E. S. [Brookhaven National Laboratory, Upton, NY 11973 (United States)

2014-04-20

We describe redMaPPer, a new red sequence cluster finder specifically designed to make optimal use of ongoing and near-future large photometric surveys. The algorithm has multiple attractive features: (1) it can iteratively self-train the red sequence model based on a minimal spectroscopic training sample, an important feature for high-redshift surveys. (2) It can handle complex masks with varying depth. (3) It produces cluster-appropriate random points to enable large-scale structure studies. (4) All clusters are assigned a full redshift probability distribution P(z). (5) Similarly, clusters can have multiple candidate central galaxies, each with corresponding centering probabilities. (6) The algorithm is parallel and numerically efficient: it can run a Dark Energy Survey-like catalog in ∼500 CPU hours. (7) The algorithm exhibits excellent photometric redshift performance, the richness estimates are tightly correlated with external mass proxies, and the completeness and purity of the corresponding catalogs are superb. We apply the redMaPPer algorithm to ∼10, 000 deg{sup 2} of SDSS DR8 data and present the resulting catalog of ∼25,000 clusters over the redshift range z in [0.08, 0.55]. The redMaPPer photometric redshifts are nearly Gaussian, with a scatter σ {sub z} ≈ 0.006 at z ≈ 0.1, increasing to σ {sub z} ≈ 0.02 at z ≈ 0.5 due to increased photometric noise near the survey limit. The median value for |Δz|/(1 + z) for the full sample is 0.006. The incidence of projection effects is low (≤5%). Detailed performance comparisons of the redMaPPer DR8 cluster catalog to X-ray and Sunyaev-Zel'dovich catalogs are presented in a companion paper.

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.

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

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

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)

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.

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)

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

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

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)

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...

Reading Chatelaine: Dr. Marion Hilliard and 1950s Women’s Health Advice

OpenAIRE

Mendes, Kaitlynn

2011-01-01

This article explores key themes and discourses surrounding women’s health advice written by Dr. Marion Hilliard between 1954 and 1957. Her works, published in eight Chatelaine articles and a 1957 book, are of particular significance because they demonstrate some of the many paradoxes Canadian women faced: women were told to stay at home and be housewives, but that they could have an identity of their own; that women too were sexual beings, but that their sexuality was confined within hete...

U.S. and foreign breeder reactors

International Nuclear Information System (INIS)

Hill, E.H.

1977-01-01

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

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

International Nuclear Information System (INIS)

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

1975-01-01

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

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

MGMT, GATA6, CD81, DR4, and CASP8 gene promoter methylation in glioblastoma

Directory of Open Access Journals (Sweden)

Skiriute Daina

2012-06-01

Full Text Available Abstract Background Methylation of promoter region is the major mechanism affecting gene expression in tumors. Recent methylome studies of brain tumors revealed a list of new epigenetically modified genes. Our aim was to study promoter methylation of newly identified epigenetically silenced genes together with already known epigenetic markers and evaluate its separate and concomitant role in glioblastoma genesis and patient outcome. Methods The methylation status of MGMT, CD81, GATA6, DR4, and CASP8 in 76 patients with primary glioblastomas was investigated. Methylation-specific PCR reaction was performed using bisulfite treated DNA. Evaluating glioblastoma patient survival time after operation, patient data and gene methylation effect on survival was estimated using survival analysis. Results The overwhelming majority (97.3% of tumors were methylated in at least one of five genes tested. In glioblastoma specimens gene methylation was observed as follows: MGMT in 51.3%, GATA6 in 68.4%, CD81 in 46.1%, DR4 in 41.3% and CASP8 in 56.8% of tumors. Methylation of MGMT was associated with younger patient age (p CASP8 with older (p MGMT methylation was significantly more frequent event in patient group who survived longer than 36 months after operation (p CASP8 was more frequent in patients who survived shorter than 36 months (p MGMT, GATA6 and CASP8 as independent predictors for glioblastoma patient outcome (p MGMT and GATA6 were independent predictors for patient survival in younger patients’ group, while there were no significant associations observed in older patients’ group when adjusted for therapy. Conclusions High methylation frequency of tested genes shows heterogeneity of glioblastoma epigenome and the importance of MGMT, GATA6 and CASP8 genes methylation in glioblastoma patient outcome.

Phonon Measurements and Model Calculations for Naphtalene-d8

DEFF Research Database (Denmark)

Mackenzie, Gordon A.; Pawley, G. S.; Dietrich, O. W.

1977-01-01

Measurements of the phonon dispersion curves in naphthalene-d8, (deuteration >99%), taken at 77K are presented. The experiments were done on two crystals, using the triple-axis neutron spectrometers at the medium flux reactor, DR3 at Riso. Most of the external or lattice modes have been measured...

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:

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.

U.S. Domestic Reactor Conversion Programs

International Nuclear Information System (INIS)

Woolstenhulme, Eric

2008-01-01

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

Dr. E.S. Mulder, Die Teologie van die Jesaja-apokalipse (Jes. 24-27 ...

African Journals Online (AJOL)

Dr. E.S. Mulder, Die Teologie van die Jesaja-apokalipse (Jes. 24-27). Proefschrift ter verkrijging van de graad van Doctor in de Godgeleerdheid aan de Rijksuniversiteit te Groningen. Groningen, J. B. Wolters, 1954, 125 bis.

PHOTOMETRIC REDSHIFT PROBABILITY DISTRIBUTIONS FOR GALAXIES IN THE SDSS DR8

International Nuclear Information System (INIS)

Sheldon, Erin S.; Cunha, Carlos E.; Mandelbaum, Rachel; Brinkmann, J.; Weaver, Benjamin A.

2012-01-01

We present redshift probability distributions for galaxies in the Sloan Digital Sky Survey (SDSS) Data Release 8 imaging data. We used the nearest-neighbor weighting algorithm to derive the ensemble redshift distribution N(z), and individual redshift probability distributions P(z) for galaxies with r < 21.8 and u < 29.0. As part of this technique, we calculated weights for a set of training galaxies with known redshifts such that their density distribution in five-dimensional color-magnitude space was proportional to that of the photometry-only sample, producing a nearly fair sample in that space. We estimated the ensemble N(z) of the photometric sample by constructing a weighted histogram of the training-set redshifts. We derived P(z)'s for individual objects by using training-set objects from the local color-magnitude space around each photometric object. Using the P(z) for each galaxy can reduce the statistical error in measurements that depend on the redshifts of individual galaxies. The spectroscopic training sample is substantially larger than that used for the DR7 release. The newly added PRIMUS catalog is now the most important training set used in this analysis by a wide margin. We expect the primary sources of error in the N(z) reconstruction to be sample variance and spectroscopic failures: The training sets are drawn from relatively small volumes of space, and some samples have large incompleteness. Using simulations we estimated the uncertainty in N(z) due to sample variance at a given redshift to be ∼10%-15%. The uncertainty on calculations incorporating N(z) or P(z) depends on how they are used; we discuss the case of weak lensing measurements. The P(z) catalog is publicly available from the SDSS Web site.

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

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.

Recent U.S. reactor operating experience

International Nuclear Information System (INIS)

Stello, V. Jr.

1977-01-01

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

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

Determination of neutron flux densities in WWR-S reactor core

International Nuclear Information System (INIS)

Tomasek, F.

1989-04-01

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

Overview of standards subcommittee 8, fissionable materials outside reactors

International Nuclear Information System (INIS)

McLaughlin, T.P.

1996-01-01

The American Nuclear Society's Standards Subcommittee 8, titled open-quotes Fissionable Materials Outside Reactors,close quotes has worked for the past 35 yr to prepare and promote standards on nuclear criticality safety for the handling, processing, storing, and transportation of fissionable materials outside reactors. The reader is referred to the Transactions of the American Nuclear Society, Vols. 39 (1981) and 64 (1991), for previous papers associated with ANS-8 poster sessions. In addition to discussions on the then-current standards, the reader will find articles on working group efforts that never materialized into standards, such as proposed 8.13, open-quotes Use of the Solid-Angle Method in Nuclear Criticality Safety,close quotes and on applications and critiques of current standards. The paper by McLendon in Vol. 39 is particularly interesting as an overview of the early history of ANS-8 and its standards

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

Research reactor`s role in Korea

Energy Technology Data Exchange (ETDEWEB)

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

1996-12-31

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

Research and Development Program in Reactor Diagnostics and Monitoring with Neutron Noise Methods. Stage 8. Final report

International Nuclear Information System (INIS)

Pazsit, I.; Demaziere, C.; Arzhanov, V.

2003-01-01

This report constitutes Stage 8 of a long-term research and development program concerning the development of diagnostics and monitoring methods for nuclear reactors. A brief proposal for the continuation of this program in stage 9 is also given at the end of the report. The program executed in Stage 8 consists of three parts and the work performed in each part is summarized below. In Stage 7, an anomaly localisation algorithm was presented and applied to the Forsmark-1 channel instability event. This investigation was carried out with a set of static data that were typical of a generic BWR model, since no data except the Local Power Range Monitors (LPRMs) time signals recorded during the instability event were made accessible to us at that time. In the present Stage, these static data were obtained from Vattenfall Fuel AB, who used the SIMULATE-3 code. The first Section of this report is thus devoted to this anomaly localisation but this time with a relevant set of data, both regarding the static core conditions and regarding the LPRMs time signals. The noise source pointed out by the localisation algorithm was once again found to be very close to an unseated fuel assembly discovered during the fuel outage following the instability event. The localisation procedure relies in fact on the prior calculation of the reactor transfer function, carried out via the neutron noise simulator first presented in Stage 6 and later improved in Stage 7. The neutron noise simulator was also improved in this Stage. More precisely, a 2-D 2- group static core simulator was developed in order to calculate the static flux and the associated eigenvalue with a spatial discretization scheme compatible with the one in use in the neutron noise simulator, i.e. finite differences. It has generally been assumed that the Decay Ratio (DR), a parameter characterizing the stability of BWRs, is a space-independent parameter of the reactor, i.e. it is independent of which LPRM is used in the core to

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

Energy Technology Data Exchange (ETDEWEB)

GERBER MS

2009-04-28

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

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.

DR. ANDRÉS MARÍA PARDO Y ALVAREZ, APOSTOL DE LA MEDICINA

Directory of Open Access Journals (Sweden)

Alvaro López Pardo

1981-10-01

Full Text Available

El 20 de julio de 1879 fue una fecha nefasta para las fiestas nacionales. Ese día dejó de existir el entonces Rector de la Facultad de Medicina, Dr. ANDRES MARIA PARDO Y ALVAREZ, en su casa de habitación, que actualmente se conoce, reformada, con el nombre de Palacio de Nariño o de la Carrera (1.
El Dr. Pardo, considerado por el historiador y médico Pedro María Ibáñez, (2 como uno de los más ilustres galenos que ha tenido el país, nació el2 de febrero de 1814. En su linajudo hogar se respiraba, al mismo tiempo, el amor por la medicina y el amor por la libertad.

Era descendiente de muy ilustres personajes. Su padre fue el Dr. Juan Maria Pardo y Pardo, médico del Colegio del Rosario, único galeno firmante del Acta de la Independencia. Su abuelo paterno, Don Manuel Pardo, también firmó dicha acta y fue encargado de llevar prisionero al Virrey Amar a Cartagena (3. La linea materna de doña Maria Tadea Alvarez Lozano lo vinculaba con Don Manuel Bernardo Alvarez, presidente de Cundinamarca,
y firmante de la Independencia; con Don Jorge Miguel Lozano Peralta y Varaes, Maldonado de Mendoza, y Olaya Primer Marqués de San Jorge. A su vez, descendiente de don Anton de Olaya, Alférez Mayor de los ejércitos de Gonzalo Jiménez de Quezada, y a Don Fernando Maldonado de Mendoza, Gran Almirante de Castilla (4.

Nació el Dr. Pardo en los primeros años de la Patria Boba, cuando ya los españoles se preocupaban por organizar una expedición para recuperar sus antiguas colonias. En efecto, La Junta de Generales a propuesta del Héroe de Bailén, General Castaños, decidió comisionar a Morillo para dirigirla.
Entró este a Santa Fé, de incógnito, el 26 de mayo de 1816 y el 30 de dicho mes, firmó un indulto, que no tenía un contenido real y comenzó la persecusión de los patriotas.
Cuando sólo contaba el Dr. Pardo con 2 años, su familia sufrió el peso de la bota española. EI4 de septiembre de ese a

U.S. Nuclear Power Reactor Plant Status

Data.gov (United States)

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

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.

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: ...

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

International Nuclear Information System (INIS)

Ene, D.C.

2002-01-01

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

Advances in U.S. reactor physics standards

International Nuclear Information System (INIS)

Cokinos, Dimitrios

2008-01-01

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

Actions for continued safe wet storage of spent nuclear fuel at VVR-S reactor in Bucharest-Magurele

International Nuclear Information System (INIS)

Isbasescu, M.; Zorliu, A.; Silviu-laurentiu, B.; Stefan, V. . E-mail address of corresponding author: mirifa@ifin.nipne.ro; Isbasescu, M.)

2005-01-01

The Romanian VVR-S research reactor is located 8 kilometers from Bucharest in the town of Magurele and was operated by the Horia Hulubei National Institute of Physics and Nuclear Engineering (IFIN-HH). The reactor first reached criticality in July 1957 and operated until December 1997 when it was permanently shutdown. The VVR - S reactor of IFIN has two repositories for spent fuel elements: (1) Cooling pool located in the reactor room; (2) Long-term repositories located outside the reactor building - SNFW (spent nuclear fuel warehouse). The major factors believed to influence the pitting of aluminium alloys are conductivity, pH, and bicarbonate, chloride, sulphate and oxygen content. Some of these parameters have been analyzed at SNFW-IFIN-HH. (author)

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:

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

International Nuclear Information System (INIS)

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

2017-01-01

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

An MCNP parametric study of George C. Laurence's subcritical pile experiment

Energy Technology Data Exchange (ETDEWEB)

Dranga, R.; Blomeley, L., E-mail: ruxandra.dranga@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carrington, R. [McGill Univ., Dept. of Mathematics and Statistics, Montreal, Quebec (Canada)

2014-12-01

In the early 1940s at the National Research Council (NRC) Laboratories in Ottawa, Canada, Dr. George Laurence conducted several experiments to determine if a sustained nuclear fission chain reaction in a carbon-uranium arrangement (or 'pile') was possible. Although Dr. Laurence did not achieve criticality, these pioneering experiments marked a significant historical event in nuclear science, and they provided a valuable reference for subsequent experiments that led to the design of Canada's first heavy-water reactors at the Chalk River Nuclear Laboratories. This paper summarizes the results of a recent collaborative project between Atomic Energy of Canada Limited and the Deep River Science Academy undertaken to numerically explore the experiments carried out at the NRC Laboratories by Dr. Laurence, while teaching high school students about nuclear science and technology. In this study, a modern Monte Carlo reactor physics code, MCNP6, was utilized to identify and study the key parameters impacting the subcritical pile's neutron multiplication factor (e.g., moderation, geometry, material impurities) and quantify their effect on the extent of subcriticality. The findings presented constitute the first endeavour to model, using a current computational reactor physics tool, the seminal experiment that provided the foundation of Canada's nuclear science and technology program. (author)

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.)

Famous people with Tourette′s syndrome: Dr. Samuel Johnson (yes & Wolfgang Amadeus Mozart (may be: Victims of Tourette′s syndrome?

Directory of Open Access Journals (Sweden)

Kalyan B Bhattacharyya

2015-01-01

Full Text Available Tourette′s syndrome is a clinical condition characterized by multiple motor tics and vocal tics which occurs in the age range 5-25 years and the intensity of the symptoms changes with time. It is felt that at least two remarkable personalities namely, Dr. Samuel Johnson from England, a man of letters and the compiler of the first ever English dictionary, and Wolfgang Amadeus Mozart from Austria, one of the greatest musical genius of all time, possibly suffered from this condition. Tourette′s syndrome is often described as the classical borderzone between neurology and psychiatry and every neurologist wonders at the curious and fascinating clinical features of this condition. It seems that at least two remarkable personalities, Dr. Samuel Johnson, a man of letters and the first person to compile an English dictionary, and Wolfgang Amadeus Mozart, arguably the most creative musical composer of all time, were possibly afflicted with this condition.

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

International Nuclear Information System (INIS)

Setiyanto; Sembiring, Tagor M.; Pinem, Surian

2007-01-01

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

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...

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. ...

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

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

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

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 ...

Identification of Chemical Reactor Plant’s Mathematical Model

OpenAIRE

Pyakullya, Boris Ivanovich; Kladiev, Sergey Nikolaevich

2015-01-01

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

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 ...

22 May 2009-DE-President of Hamburg University-Prof. Dr M. Auweter-Kurtz signing the Guest book with Director for Research and Computing,S. Bertolucci

CERN Multimedia

Maximilien Brice

2009-01-01

Tirage 1 to 3:Signature of the Guest book,Prof. Dr M. Auweter-Kurtz with S. Bertolucci, Director for Research and Computing Tirage 4 to 5 :Dr M. Auweter-Kurtz with S. Bertolucci and Senior Physicist, ATLAS Collaboration, External Relations Office, Dr R. Voss Tirage 6 : Deputy to the BE Department Head,O. Brüning,H. Kurtz,M. Auweter-Kurtz, Dean of the Faculty of Mathematics, Informatics and Natural Sciences H. Graener, S. Bertolucci,R. Voss,CMS Collaboration, Universität Hamburg, Former SPC Member, R. Klanner

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.

Identification of Chemical Reactor Plant’s Mathematical Model

Directory of Open Access Journals (Sweden)

Pyakillya Boris

2015-01-01

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

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)

Operating history of U.S. nuclear power reactors

International Nuclear Information System (INIS)

1974-01-01

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

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, ...

Research about reactor operator's personability characteristics and performance

Energy Technology Data Exchange (ETDEWEB)

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

2003-03-01

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

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

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

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...

Limits and conditions for continuous operation of WWR-S reactor

International Nuclear Information System (INIS)

Pittermann, P.; Listik, E.

1979-02-01

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

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)

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

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

International Nuclear Information System (INIS)

Ninokata, Hisashi; Sasao, Nobuyki

2007-01-01

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

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

Remarks to Dr. Paul E. Tomaszewski’s comments on the research of Jan Czochralski’s curriculum vitae (a reply (in Polish

Directory of Open Access Journals (Sweden)

Michał KOKOWSKI

2015-12-01

Full Text Available The author replies to the text entitled “Remarks to the comment by Prof.  Michal Kokowski on the research of Jan Czochralski’s biography” by Dr. Paweł E. Tomaszewski (2015, highlighting the key contentious issues, including the need to rely systematically on historical sources and the criticism thereof.

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)

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)

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”...

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"...

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.

U.S. Status of Fast Reactor Research and Technology

International Nuclear Information System (INIS)

Hill, Robert

2012-01-01

Summary: • Fast reactor R&D is focused on key technologies innovations for performance improvement (cost reduction) and safety: 1. System Integration and Concept Development; 2. Safety Technology; 3. Advanced Materials; 4. Ultrasonic Viewing; 5. Advanced Energy Conversion (Supercritical CO 2 Brayton cycle); 6. Reactor Simulation; 7. Nuclear Data; 8. Advanced Fuels. • Fast reactors have flexible capability for actinide management: – A wide variety of fuel cycle options are being considered; • International R&D collaboration pursued in Generation-IV and multilateral arrangements

Dielectronic recombination of Xe8+ ions

International Nuclear Information System (INIS)

Zhang Guoding; Fu Yanbiao; Dong Chenzhong; Zhang Yizhao

2012-01-01

Based on the fully relativistic configuration interaction method, theoretical calculations are carried out for the dielectronic recombination (DR) rate coefficients of Xe 8+ ions in the temperature region from 0.1 to 1 650 eV. The comparison of the DR rate coefficients from 4s, 4p and 4d subshell excitations shows that 4d subshell excitation dominates in the whole temperature region. The contribution from 4p subshell excitation is very important at temperature above 10 eV and the contributions from 4s subshell ex- citation is lower than 7.5% in the whole temperature region. Similarly, the comparison of the DR rate coefficients through △n= 0, I and 2 core excitation shows that the contribution from △n= 2 core excitation can not be neglected, the contributions from n'>15 can also not be neglected. The DR rate coefficients of △n=0, 1 and 2 core excitation and the total DR rate coefficients are fitted with some parameters, which are in good agreement with theoretical calculations values (within 1 % difference)The total DR rate coefficients are greater than radiative recombination (RR) and three-body recombination (TBR) rate coefficients at temperature above 1 eV. Therefore, the DR process can strongly influence the ionization balance of laser produced xenon plasmas. (authors)

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:

Etude de l’hémogramme dans la drépanocytose homozygote: à propos de 87 patients

Science.gov (United States)

Dahmani, Fatima; Benkirane, Souad; Kouzih, Jaafar; Woumki, Aziz; Mamad, Hassan; Masrar, Azlarab

2016-01-01

La drépanocytose homozygote, fait partie des hémoglobinopathies les plus fréquentes au Maroc. La drépanocytose est caractérisée par une grande variabilité d’expressions clinique et biologique qui dépendent des facteurs génétiques modulateurs et environnementaux. Elle se manifeste par une anémie régénérative de gravité très variable selon les individus. L’évolution spontanée en l’absence de traitement est le décès précoce. La drépanocytose est caractérisée par une grande variabilité d’expression clinique et biologique qui dépend des facteurs génétiques et environnementaux. Un tableau clinique sévère marqué par une fréquence de transfusion élevée et précoce, des complications infectieuses graves et une mortalité précoce. Un état inflammatoire constant caractérisé par des protéines inflammatoires élevées et état nutritionnel compromis. L’objectif est de déterminer le profil des paramètres hématologiques du drépanocytaire homozygote (SS) marocain au cours des stades stationnaires. Nous avons fait une étude descriptive transversale de 87 patients drépanocytaires (SS). Nous avons réalisé une étude biologique comportant: l’hémogramme avec étude morphologique des globules rouges en coloration MGG et numération automatique des réticulocytes. Les électrophorèses de l’hémoglobine à pH alcalin (8.8) sur gel d’agarose avec intégration densitométrique. L’âge moyen est de 13.22 ans ± 16.36 avec un sex- ratio (H/F) de 1.175 et des extrêmes allant de 0.6 à 36 ans. La répercussion de l’anémie sur le plan biologique, est intense chez 88.5% des patients, 67.8% ont une anémie normocytaire contre 29.9% présentant une microcytose, et 2.3% qui présentaient une macrocytose. Le degré d’anisocytose est lié au degré d’anémie, très évocatrice chez les drépanocytaires homozygotes S/S (95,4%). Une réticulocytose était observée chez nos patients (81,6%) et 52.9% présentaient une

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

Science.gov (United States)

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

2012-01-01

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

Prognostic value of the CD4+/ CD8+ ratio of tumour infiltrating lymphocytes in colorectal cancer and HLA-DR expression on tumour cells

DEFF Research Database (Denmark)

Diederichsen, Axel Cosmus Pyndt; Hjelmborg, J v B; Christensen, Per B

2003-01-01

class II in 70 enzymatically dissociated colorectal cancers and the phenotype of tumour infiltrating lymphocytes (TILs) in 41 cases. There was no trend in 5-year survival between three levels (low, medium, high) of HLA-DR expression on the tumour cells. Patients with low CD4+/CD8+ ratios had a better...

The tissue microlocalisation and cellular expression of CD163, VEGF, HLA-DR, iNOS, and MRP 8/14 is correlated to clinical outcome in NSCLC.

Science.gov (United States)

Ohri, Chandra M; Shikotra, Aarti; Green, Ruth H; Waller, David A; Bradding, Peter

2011-01-01

We have previously investigated the microlocalisation of M1 and M2 macrophages in NSCLC. This study investigated the non-macrophage (NM) expression of proteins associated with M1 and M2 macrophages in NSCLC. Using immunohistochemistry, CD68(+) macrophages and proteins associated with either a cytotoxic M1 phenotype (HLA-DR, iNOS, and MRP 8/14), or a non-cytotoxic M2 phenotype (CD163 and VEGF) were identified. NM expression of the markers was analysed in the islets and stroma of surgically resected tumours from 20 patients with extended survival (ES) (median 92.7 months) and 20 patients with poor survival (PS) (median 7.7 months). The NM expression of NM-HLA-DR (pMRP 8/14 (p = 0.02) was increased in ES compared to PS patients in the tumour islets. The tumour islet expression of NM-VEGF, was decreased in ES compared to PS patients (pMRP 8/14 (p = 0.01) expression in the stroma of ES patients compared with PS patients. The 5-year survival for patients with above and below median NM expression of the markers in the islets was 74.9% versus 4.7% (NM-HLA-DR pMRP 8/14 p = 0.04), as opposed to 34.1% versus 44.4% (NM-CD163 p = 0.41) and 19.4% versus 59.0% (NM-VEGF p = 0.001). Cell proteins associated with M1 and M2 macrophages are also expressed by other cell types in the tumour islets and stroma of patients with NSCLC. Their tissue and cellular microlocalisation is associated with important differences in clinical outcome.

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

Safety report on WWR-S reactor

International Nuclear Information System (INIS)

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

1981-04-01

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

Accident Source Terms for Pressurized Water Reactors with High-Burnup Cores Calculated using MELCOR 1.8.5.

Energy Technology Data Exchange (ETDEWEB)

Gauntt, Randall O.; Goldmann, Andrew; Kalinich, Donald A.; Powers, Dana A.

2016-12-01

In this study, risk-significant pressurized-water reactor severe accident sequences are examined using MELCOR 1.8.5 to explore the range of fission product releases to the reactor containment building. Advances in the understanding of fission product release and transport behavior and severe accident progression are used to render best estimate analyses of selected accident sequences. Particular emphasis is placed on estimating the effects of high fuel burnup in contrast with low burnup on fission product releases to the containment. Supporting this emphasis, recent data available on fission product release from high-burnup (HBU) fuel from the French VERCOR project are used in this study. The results of these analyses are treated as samples from a population of accident sequences in order to employ approximate order statistics characterization of the results. These trends and tendencies are then compared to the NUREG-1465 alternative source term prescription used today for regulatory applications. In general, greater differences are observed between the state-of-the-art calculations for either HBU or low-burnup (LBU) fuel and the NUREG-1465 containment release fractions than exist between HBU and LBU release fractions. Current analyses suggest that retention of fission products within the vessel and the reactor coolant system (RCS) are greater than contemplated in the NUREG-1465 prescription, and that, overall, release fractions to the containment are therefore lower across the board in the present analyses than suggested in NUREG-1465. The decreased volatility of Cs 2 MoO 4 compared to CsI or CsOH increases the predicted RCS retention of cesium, and as a result, cesium and iodine do not follow identical behaviors with respect to distribution among vessel, RCS, and containment. With respect to the regulatory alternative source term, greater differences are observed between the NUREG-1465 prescription and both HBU and LBU predictions than exist between HBU and LBU

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)

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

International Nuclear Information System (INIS)

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

2001-01-01

robustness of this type of repository. The ponds are supplied with distilled water from reactor tank No 1. The spent fuel assemblies used in the WWR-S reactor and stored in this repository contain two types of fuel: the EK-10 (153 pieces) and the S-36 (70 pieces). The EK-10 and S-36 fuel assemblies have the same shape but distinct numbers of fuel rods and different percentage of U-235 enrichment. So, the EK-10 contains 16 fuel rods and 10% enrichment while the S-36 contains 15 fuel rods of 36% U-235 enrichment. Total activity of the fuel assemblies is about 10.69 x 10 4 Ci. The most important fission products in fuel rods are Sr-90 and Cs-137. Depending on fuel assembly type the calculated values of the activity of these elements are: - a. 7.14 x 10 3 Ci (Sr-90) and 7.67 x 10 3 Ci (Cs-137) for EK-10 and, - b. 8.21 x 10 3 Ci (Sr-90) and 8.08 x 10 3 Ci (Cs-137) for S-36. The gamma spectrometry analysis performed on water samples from storage ponds showed the dominant presence of Cs and other nuclides. The presence of Cs in the water is due to fuel rods flaws, the occurrence of pores and cracks because of fuel manipulation in active core of the reactor or in the storage pond or because of corrosion pits due to a low quality of water. The manufacturer have specified the water conditions for the EK-10 and S-36 fuel assemblies, which they believe will avoid corrosion problems. These are displayed in a table which enlists for EK-10 and C-36 the values of the water parameters, namely the values of pH, conductivity, constant residuals, corrosion products, Cl - and O 2 concentration. The IAEA recommends values of 1 μS/cm, but values up to 2 μS/cm might be accepted if the chlorine, copper and sulphate concentrations are very low. To maintain these parameters of the water in compliance with IAEA recommendations, it was designed and realised a filtration installation for the distilled water produced at the reactor. Till this installation will be assembled the water chemistry is

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).

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)

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.

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

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

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)

The spatial trascendence of dasein in Heidegger´s analytic and in Mullā Sādrā´s trascendental philosophy

Directory of Open Access Journals (Sweden)

Carlos Medina Labayru

2016-05-01

Full Text Available According to Heidegger, the situation of the circumspect experience that reflects the athematic use of the utensils characterizes away of life of Dasein that is more genuine from the ontological standpoint than the mentalist (representationalist description of intentionality. This primacy of the circumspect rebuff suggests that it is founded on the spatial condition of Dasein, as one of its characteristic (existentiell modes. However, the exacerbated caution before the substantialist metaphysic restricts the scope of Heidegger’s analytic in this respect. Mullā Sādrā’s theory of transubstantial movement is an alternative that overcomes this limitation

Tun Dr. Mahathir’s Leadership Communication: The Confucian Perspective

OpenAIRE

Cheah Joyce Lynn-Sze; Yusof Norhafezah; Ahmad Mohd Khairie

2017-01-01

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...

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, ...

‘Great ease and simplicity of action’: Dr Nelson’s Inhaler and the origins of modern inhalation therapy

Directory of Open Access Journals (Sweden)

Barry Murnane

2017-11-01

Full Text Available Unveiled at the conclusion of a meeting of the Royal Medical and Chirurgical Society in 1861,[1] ‘Dr Nelson’s Improved Inhaler’ was one of the most important milestones in the genesis of reliable treatment of respiratory ailments in the modern era. Affordable and suitable for self-medication, the Dr Nelson’s Inhaler offered simple and reliable relief for patients with respiratory and pulmonary ailments. Conspicuous for its modesty and simplicity, it was one of the most widely produced, reproduced, and used inhalation devices in the final third of the nineteenth century. By reconstructing the ‘biography’ of the Nelson Inhaler, this article will attempt to sketch a network of medical and commercial interests and expertise in London which aligned in the 1860s to help establish inhalation as a popular, inexpensive, and trusted form of medical therapy for pulmonary ailments. This article will look at what connects physicians, apothecaries, and patients in the era: the medicines and technologies that were prescribed, made, bought, and which caused wellness, side-effects, and even death. This approach allows us to develop a narrative of respiratory illness as it was experienced by practitioners and patients alike.

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

The clustering of the SDSS-IV extended Baryon Oscillation Spectroscopic Survey DR14 quasar sample: measurement of the growth rate of structure from the anisotropic correlation function between redshift 0.8 and 2.2

Science.gov (United States)

Zarrouk, Pauline; Burtin, Etienne; Gil-Marín, Héctor; Ross, Ashley J.; Tojeiro, Rita; Pâris, Isabelle; Dawson, Kyle S.; Myers, Adam D.; Percival, Will J.; Chuang, Chia-Hsun; Zhao, Gong-Bo; Bautista, Julian; Comparat, Johan; González-Pérez, Violeta; Habib, Salman; Heitmann, Katrin; Hou, Jiamin; Laurent, Pierre; Le Goff, Jean-Marc; Prada, Francisco; Rodríguez-Torres, Sergio A.; Rossi, Graziano; Ruggeri, Rossana; Sánchez, Ariel G.; Schneider, Donald P.; Tinker, Jeremy L.; Wang, Yuting; Yèche, Christophe; Baumgarten, Falk; Brownstein, Joel R.; de la Torre, Sylvain; du Mas des Bourboux, Hélion; Kneib, Jean-Paul; Mariappan, Vivek; Palanque-Delabrouille, Nathalie; Peacock, John; Petitjean, Patrick; Seo, Hee-Jong; Zhao, Cheng

2018-06-01

We present the clustering measurements of quasars in configuration space based on the Data Release 14 (DR14) of the Sloan Digital Sky Survey IV extended Baryon Oscillation Spectroscopic Survey (eBOSS). This data set includes 148 659 quasars spread over the redshift range 0.8 ≤ z ≤ 2.2 and spanning 2112.9 deg2. We use the Convolution Lagrangian Perturbation Theory approach with a Gaussian Streaming model for the redshift space distortions of the correlation function and demonstrate its applicability for dark matter haloes hosting eBOSS quasar tracers. At the effective redshift zeff = 1.52, we measure the linear growth rate of structure fσ8(zeff) = 0.426 ± 0.077, the expansion rate H(z_eff)= 159^{+12}_{-13}(rs^fid/r_s) {{}km s}^{-1} Mpc^{-1}, and the angular diameter distance DA(z_eff)=1850^{+90}_{-115} (r_s/rs^fid) {}Mpc, where rs is the sound horizon at the end of the baryon drag epoch and rs^fid is its value in the fiducial cosmology. The quoted uncertainties include both systematic and statistical contributions. The results on the evolution of distances are consistent with the predictions of flat Λ-cold dark matter cosmology with Planck parameters, and the measurement of fσ8 extends the validity of General Relativity to higher redshifts (z > 1). This paper is released with companion papers using the same sample. The results on the cosmological parameters of the studies are found to be in very good agreement, providing clear evidence of the complementarity and of the robustness of the first full-shape clustering measurements with the eBOSS DR14 quasar sample.

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

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)

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....

MELCOR 1.8.2 Analyses in Support of ITER's RPrS

International Nuclear Information System (INIS)

Brad J Merrill

2008-01-01

The International Thermonuclear Experimental Reactor (ITER) Program is performing accident analyses for ITER's 'Rapport Preliminaire de Surete' (Report Preliminary on Safety - RPrS) with a modified version of the MELCOR 1.8.2 code. The RPrS is an ITER safety document required in the ITER licensing process to obtain a 'Decret Autorisation de Construction' (a Decree Authorizing Construction - DAC) for the ITER device. This report documents the accident analyses performed by the US with the MELCOR 1.8.2 code in support of the ITER RPrS effort. This work was funded through an ITER Task Agreement for MELCOR Quality Assurance and Safety Analyses. Under this agreement, the US was tasked with performing analyses for three accident scenarios in the ITER facility. Contained within the text of this report are discussions that identify the cause of these accidents, descriptions of how these accidents are likely to proceed, the method used to analyze the consequences of these accidents, and discussions of the transient thermal hydraulic and radiological release results for these accidents

An Account of Oak Ridge National Laboratory's Thirteen Research Reactors

Energy Technology Data Exchange (ETDEWEB)

Rosenthal, Murray Wilford [ORNL

2009-08-01

The Oak Ridge National Laboratory has built and operated 13 nuclear reactors in its 66-year history. The first was the graphite reactor, the world's first operational nuclear reactor, which served as a plutonium production pilot plant during World War II. It was followed by two aqueous-homogeneous reactors and two red-hot molten-salt reactors that were parts of power-reactor development programs and by eight others designed for research and radioisotope production. One of the eight was an all-metal fast burst reactor used for health physics studies. All of the others were light-water cooled and moderated, including the famous swimming-pool reactor that was copied dozens of times around the world. Two of the reactors were hoisted 200 feet into the air to study the shielding needs of proposed nuclear-powered aircraft. The final reactor, and the only one still operating today, is the High Flux Isotope Reactor (HFIR) that was built particularly for the production of californium and other heavy elements. With the world's highest flux and recent upgrades that include the addition of a cold neutron source, the 44-year-old HFIR continues to be a valuable tool for research and isotope production, attracting some 500 scientific visitors and guests to Oak Ridge each year. This report describes all of the reactors and their histories.

The tissue microlocalisation and cellular expression of CD163, VEGF, HLA-DR, iNOS, and MRP 8/14 is correlated to clinical outcome in NSCLC.

Directory of Open Access Journals (Sweden)

Chandra M Ohri

Full Text Available BACKGROUND: We have previously investigated the microlocalisation of M1 and M2 macrophages in NSCLC. This study investigated the non-macrophage (NM expression of proteins associated with M1 and M2 macrophages in NSCLC. METHODS: Using immunohistochemistry, CD68(+ macrophages and proteins associated with either a cytotoxic M1 phenotype (HLA-DR, iNOS, and MRP 8/14, or a non-cytotoxic M2 phenotype (CD163 and VEGF were identified. NM expression of the markers was analysed in the islets and stroma of surgically resected tumours from 20 patients with extended survival (ES (median 92.7 months and 20 patients with poor survival (PS (median 7.7 months. RESULTS: The NM expression of NM-HLA-DR (p<0.001, NM-iNOS (p = 0.02 and NM-MRP 8/14 (p = 0.02 was increased in ES compared to PS patients in the tumour islets. The tumour islet expression of NM-VEGF, was decreased in ES compared to PS patients (p<0.001. There was more NM-CD163 expression (p = 0.04 but less NM-iNOS (p = 0.002 and MRP 8/14 (p = 0.01 expression in the stroma of ES patients compared with PS patients. The 5-year survival for patients with above and below median NM expression of the markers in the islets was 74.9% versus 4.7% (NM-HLA-DR p<0.001, 65.0% versus 14.6% (NM-iNOS p = 0.003, and 54.3% versus 22.2% (NM-MRP 8/14 p = 0.04, as opposed to 34.1% versus 44.4% (NM-CD163 p = 0.41 and 19.4% versus 59.0% (NM-VEGF p = 0.001. CONCLUSIONS: Cell proteins associated with M1 and M2 macrophages are also expressed by other cell types in the tumour islets and stroma of patients with NSCLC. Their tissue and cellular microlocalisation is associated with important differences in clinical outcome.

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)

Reactor-specific spent fuel discharge projections, 1987-2020

International Nuclear Information System (INIS)

Walling, R.C.; Heeb, C.M.; Purcell, W.L.

1988-03-01

The creation of five reactor-specific spent fuel data bases that contain information on the projected amounts of spent fuel to be discharged from U.S. commercial nuclear reactors through the year 2020 is described. The data bases contain detailed spent fuel information from existing, planned, and projected pressurized water reactors (PWR) and boiling water eactors (BWR), and one existing high temperature gas reactor (HTGR). The projections are based on individual reactor information supplied by the U.S. reactor owners. The basic information is adjusted to conform to Energy Information Administration (EIA) forecasts for nuclear installed capacity, generation, and spent fuel discharged. The EIA cases considered are: No New Orders (assumes increasing burnup), No New Orders with No Increased Burnup, Upper Reference (assumes increasing burnup), Upper Reference with No Increased Burnup, and Lower Reference (assumes increasing burnup). Detailed, by-reactor tables are provided for annual discharged amounts of spent fuel, for storage requirements assuming maximum at-reactor storage, and for storage requirements assuming maximum at-reactor storage plus intra-utility transshipment of spent fuel. 8 refs., 8 figs., 10 tabs

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.

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.

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.

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

Evaluation report on SCTF Core-III tests S3-7 and S3-8

International Nuclear Information System (INIS)

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi

1990-03-01

It has been said that the Emergency Core Cooling (ECC) water injected into the hot legs flows into the upper plenum and then falls back to the core (i.e. break-through) during reflood phase in a German type Pressurized Water Reactor (GPWR) with the combined-injection-type ECCS, and that the break-through occurs where the water temperature at the tie plate area is lower and subcooled. Based on this information two tests were conducted with the Slab Core Test Facility (SCTF) Core-III in order to investigate the effects of the water temperature distribution at the tie plate area on the break-through and the core cooling. In these tests, the subcooled ECC water was injected just above the Upper Core Support Plate (UCSP) in order to establish the desired water temperature distribution at the tie plate area. In one test (Test S3-7) the ECC water injection above the UCSP was performed above Bundles 3 and 4, and in the other test (Test S3-8) above Bundles 7 and 8 during initial 60 s a and then was changed to above Bundles 3 and 4. The test data were compared with those of Test S3-SH1, in which the injection was performed above Bundles 7 and 8 and the other test conditions were the same as in Tests S3-7 and S3-8. Analyzing these test data, the following has been found: The break-through occurs where the water temperature at the tie plate area is subcooled and the core cooling is enhanced significantly in the break-through region. The break-through location changes, with some time lag, following the change of the water temperature distribution at the tie plate area. Furthermore, the core cooling in the non-break-through regions is almost the same regardless of the location of the break-through. (author)

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

International Nuclear Information System (INIS)

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

1998-01-01

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

Application of S-CO_2 Cycle for Small Modular Reactor coupled with Desalination System

International Nuclear Information System (INIS)

Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik

2016-01-01

The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO_2 power cycle technology. The S-CO_2 Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO_2 cycles for SMART with desalination system is conducted. The simple recuperated S-CO_2 cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%

During Stably Suppressive Antiretroviral Therapy Integrated HIV-1 DNA Load in Peripheral Blood is Associated with the Frequency of CD8 Cells Expressing HLA-DR/DP/DQ

Directory of Open Access Journals (Sweden)

Alessandra Ruggiero

2015-09-01

Conclusions: The observed positive association between integrated HIV-1 DNA load and frequency of CD8+DR/DP/DQ+ cells indicates that a close correlation between HIV persistence and immune activation continues during consistently suppressive therapy. The inducers of the distinct activation profile warrant further investigation.

Assessment methodology applicable to safe decommissioning of Romanian VVR-S research reactor

International Nuclear Information System (INIS)

Baniu, O.; Vladescu, G.; Vidican, D.; Penescu, M.

2002-01-01

The paper contains the results of research activity performed by CITON specialists regarding the assessment methodology intended to be applied to safe decommissioning of the research reactors, developed taking into account specific conditions of the Romanian VVR-S Research Reactor. The Romanian VVR-S Research Reactor is an old reactor (1957) and its Decommissioning Plan is under study. The main topics of paper are as follows: Safety approach of nuclear facilities decommissioning. Applicable safety principles; Main steps of the proposed assessment methodology; Generic content of Decommissioning Plan. Main decommissioning activities. Discussion about the proposed Decommissioning Plan for Romanian Research Reactor; Safety risks which may occur during decommissioning activities. Normal decommissioning operations. Fault conditions. Internal and external hazards; Typical development of a scenario. Features, Events and Processes List. Exposure pathways. Calculation methodology. (author)

8th International School of Fusion Reactor Technology "Ettore Majorana"

CERN Document Server

Leotta, G G; Muon-catalyzed fusion and fusion with polarized nuclei

1988-01-01

The International School of Fusion Reactor Technology started its courses 15 years ago and since then has mantained a biennial pace. Generally, each course has developed the subject which was announced in advance at the closing of the previous course. The subject to which the present proceedings refer was chosen in violation of that rule so as to satisfy the recent and diffuse interest in cold fusion among the main European laboratories involved in controlled thermonuclear research (CTR). In the second half of 1986 we started to prepare a workshop aimed at assessing the state of the art and possibly of the perspectives of muon- catalyzed fusion. Research in this field has recently produced exciting experimental results open to important practical applications. We thought it worthwhile to consider also the beneficial effects and problems of the polarization ofthe nuclei in both cold and thermonuclear fusion. In preparing the 8th Course on Fusion Reactor Technology, it was necessary to abandon the tradi...

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.

Displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor

International Nuclear Information System (INIS)

Wang, Zujun; Huang, Shaoyan; Liu, Minbo; Xiao, Zhigang; He, Baoping; Yao, Zhibin; Sheng, Jiangkun

2014-01-01

The experiments of displacement damage effects on CMOS APS image sensors induced by neutron irradiation from a nuclear reactor are presented. The CMOS APS image sensors are manufactured in the standard 0.35 μm CMOS technology. The flux of neutron beams was about 1.33 × 10 8 n/cm 2 s. The three samples were exposed by 1 MeV neutron equivalent-fluence of 1 × 10 11 , 5 × 10 11 , and 1 × 10 12 n/cm 2 , respectively. The mean dark signal (K D ), dark signal spike, dark signal non-uniformity (DSNU), noise (V N ), saturation output signal voltage (V S ), and dynamic range (DR) versus neutron fluence are investigated. The degradation mechanisms of CMOS APS image sensors are analyzed. The mean dark signal increase due to neutron displacement damage appears to be proportional to displacement damage dose. The dark images from CMOS APS image sensors irradiated by neutrons are presented to investigate the generation of dark signal spike

Dr Oen Boen Ing Patriot doctor, social activist, and doctor of the poor

Directory of Open Access Journals (Sweden)

Ravando Lie

2017-05-01

Full Text Available This article examines the efforts and achievements of Oen Boen Ing, a Tionghoa doctor, to improve the quality of health of the poorer inhabitants of Surakarta. Dr Oen played an important role in five different periods: Dutch colonialism, the Japanese occupation, the Indonesian revolution, Soekarno’s regime, and Suharto’s New Order. Known for being a benevolent doctor, activist, and patriot of the revolution during his life-time, Dr Oen also gave medical assistance to the needy, which famously earned him the accolade of “doctor of the poor”. During the Indonesian revolution, Dr Oen assisted the Student Soldiers (Tentara Pelajar and afterwards was appointed the member of Supreme Advisory Council (Dewan Pertimbangan Agung/DPA by Soekarno in 1949. As a benevolent doctor and activist, Dr Oen is remembered for founding the Panti Kosala Hospital which was renamed to perpetuate his name on 30 October 1983, exactly a year after his passing. When he died, thousands of peoples gathered to pay their final respects to the doctor. He was honoured with a ceremony conducted in the Mangkunegaran Palace. Dr Oen’s name will be eternally respected, especially in Surakarta.

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 ...

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)

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

International Nuclear Information System (INIS)

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

2001-01-01

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

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)

Uzm Dr Sebahattin Okumuş 05-09-1937 - 14-03-2003

Directory of Open Access Journals (Sweden)

Veli Özdemir

2003-12-01

. Dr. Cengiz YEGİNALTAY kahvehanesiydi. Zaten yaşamının son saatlerini orada tamamladı. Sebahattin OKUMUŞ'un Biyografisi: Uz. Dr. Sebahattin OKUMUŞ, 05.09.1937 yılında Bitlis'te doğdu; ilk ve orta öğrenimini bu ilde tamamladı. Aymyıl kazandığı Tıp Fakültesine kaydım yaptırmak için geldiği İstanbul'da geçim sıkıntısı ve diğer nedenlerden dolayı üniversite öğrenimini yarıda bırakarak bir ilaç firmasında mümessil olarak çalışmaya başladı. Yıllar soma yeniden okuluna dönerek mezun oldu. Adli Tıp Mtiessesesi'nin 10.10.1980 tarihinde açtığı sınavda başarılı olarak Adli Tıp Asistanı olmaya hak kazandı. 17.03.1981 tarihinde S.S.K. Cibali Dispanserinden naklen tayin olarak bu görevine başladı. “Çocuk Öldürme (Infanticide Metodları ve Çocuk Öldürme İlgili Adli Tıp Sorunları” konulu teziyle 24.10.1983 tarihinde 4 asistan arkadaşıyla birlikte girdiği uzmanlık sınavını (diğerleri: Dr. Uğur Kaya GÜNDÜZ, Dr. Şerife Bilge KIRANGİL, Dr. Yaşar TIRAŞÇI ve Dr. Uğur TANAÇAN vererek Adli Tıp Uzmam oldu. (Jüri üyeleri: Prof.Dr. M. Şemsi Gök, Prof.Dr. Talia Bali Akyan, Doç. Dr. R. Özdemir Kolusaym, Uz. Dr. Vakur Sağmen ve Uz. Dr. Cahide Müdüroğlu. Bir süre Kurumda çalıştıktan soma Adli Tıp Kurumu'nun Türkiye'de teşkilatlanması politikası doğrultusunda Erzurum'da açılan Şube Müdürlüğü'nde görevlendirildi, 09.05.1984 tarihinde bu görevine başlayarak Erzurum'un ilk adli tıp uzmanı oldu. Yaklaşık 8 yıl burada görev yaptıktan soma İstanbul'a geri çağrılarak 10.02.1992 tarihinde Başkan Yar-dımcıkğı'nda görevlendirildi. Ardından kısa bir süre Bakırköy Şube Müdürü olarak çalıştı. 01.06.1993 tarihinden itibaren Fatih Şube Müdürü (kadrosunu 09.01.1998 tarihinde aldı olarak görev yaptı. 06.09.2002\ttarihinde yaş haddinden emekli oldu. 14.03.2003\tCuma günü akşamüstü idi, bir tıp bayramında aramızdan ayrıldı... Dr. Veli ÖZDEMİR

Final report. U.S. Department of Energy University Reactor Sharing Program

Energy Technology Data Exchange (ETDEWEB)

Bernard, John A

2003-01-21

Activities supported at the MIT Nuclear Reactor Laboratory under the U.S. DOE University Reactor Sharing Program are reported for Grant DE FG02-95NE38121 (September 16, 1995 through May 31, 2002). These activities fell under four subcategories: support for research at thesis and post-doctoral levels, support for college-level laboratory exercises, support for reactor tours/lectures on nuclear energy, and support for science fair participants.

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

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)

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.

Evaluation of GenoType NTM-DR Assay for Identification of Mycobacterium chimaera.

Science.gov (United States)

Mok, Simone; Rogers, Thomas R; Fitzgibbon, Margaret

2017-06-01

Identification of species within the Mycobacterium avium complex (MAC) is difficult, and most current diagnostic laboratory tests cannot distinguish between species included in the complex. Differentiation of species within the MAC is important, as Mycobacterium chimaera has recently emerged as a major cause of invasive cardiovascular infections following open heart surgery. A new commercial diagnostic assay, GenoType NTM-DR ver. 1.0, is intended to differentiate between three species within the MAC, namely, Mycobacterium avium , Mycobacterium intracellulare , and Mycobacterium chimaera In this study, we investigated an archival collection of 173 MAC isolates using 16S rRNA and 16S-23S internal transcribed spacer (ITS) gene sequencing, and GenoType NTM-DR was evaluated for identifying M. chimaera and other species belonging to the MAC. Species identification of 157/173 (91%) isolates with the GenoType NTM-DR assay was in agreement with 16S rRNA and 16S-23S ITS gene sequencing results. Misidentification occurred with 16 isolates which belonged to four species included in the MAC that are rarely encountered in clinical specimens. Despite some limitations of this assay, GenoType NTM-DR had 100% specificity for identifying M. chimaera This novel assay will enable diagnostic laboratories to differentiate species belonging to the Mycobacterium avium complex and to accurately identify M. chimaera It can produce rapid results and is also more cost efficient than gene sequencing methods. Copyright © 2017 American Society for Microbiology.

U.S. uranium supply to the research and test reactor community

International Nuclear Information System (INIS)

Parker, Elaine M.

2002-01-01

From the 1950s through the early 1990s, the U.S. Department of Energy (DOE) was the primary supplier of low enriched uranium (LEU) and highly enriched uranium (HEU) to research and test reactors worldwide. The formerly called Y-12 Plant in Oak Ridge, Tennessee, was put into operational stand down in 1994 due to inadequate safety documentation. This paper will discuss the re-start of the Y-12 Plant and its current capabilities. Additionally, the paper will address recent changes within the DOE, with the creation of the National Nuclear Security Administration (NNSA). It will show how the change to NNSA and an organizational re-alignment has improved efficiencies. NNSA is committed to operate its sales program so that it is complementary to, and in support of, the Reduced Enrichment for Research and Test Reactors (RERTR) and Foreign Research Reactor Spent Nuclear Fuel (FRR SNF) Return Programs. The NNSA is committed to provide an assurance of competitively-priced, high-quality uranium supply to the research and test reactor community under long-term contracts. This paper will discuss some of NNSA's recent successes in long-term contracting and meeting deliveries. (author)

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.

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.

Safe decommissioning of the Romanian VVR-S research reactor

International Nuclear Information System (INIS)

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

2002-01-01

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

Typing for HLA-D/DR associated DP-antigens with the primed lymphocyte typing (PLT) technique

DEFF Research Database (Denmark)

Morling, N; Jakobsen, B K; Platz, P

1980-01-01

A total of 74 healthy unrelated random individuals and 36 patients with juvenile rheumatoid arthritis (JRA) were typed for HLA-D antigens with the homozygous typing cell technique and typed for HLA-D/DR associated DP-antigens with the primed lymphocyte typing (PLT) technique. All patients and some...... of the controls were also HLA-DR typed with a limited battery of anti-DR sera. Selected PLT-cells, specific for the HLA-D/DR antigens D/DRw1-8 and the local specificity D"H" were used. The results of the PLT-experiments were evaluated with the Normalized Median Response (NMR) method and the further procedure...

Development of the IAEA’s Knowledge Preservation Portals for Fast Reactors and Gas-Cooled Reactors Knowledge Preservation

International Nuclear Information System (INIS)

Batra, C.; Menahem, D. Beraha; Kriventsev, V.; Monti, S.; Reitsma, F.; Grosbois, J. de; Khoroshev, M.; Gladyshev, M.

2016-01-01

Full text: The IAEA has been carrying out a dedicated initiative on fast reactor knowledge preservation since 2003. The main objectives of the Fast Reactor Knowledge Portal (FRKP) initiative are to, a) halt the on-going loss of information related to fast reactors (FR), and b) collect, retrieve, preserve and make accessible existing data and information on FR. This portal will help in knowledge sharing, development, search and discovery, collaboration and communication of fast reactor related information. On similar lines a Gas Cooled Fast Reactor Knowledge Preservation portal project also started in 2013. Knowledge portals are capable to control and manage both publicly available as well as controlled information. The portals will not only incorporate existing set of knowledge and information, but will also provide a systemic platform for further preservation of new developments. It will include fast reactor and gas cooled reactor document repositories, project workspaces for the IAEA’s Coordinated Research Projects (CRPs), Technical Meetings (TMs), forums for discussion, etc. The portal will also integrate a taxonomy based search tool, which will help using new semantic search capabilities for improved conceptual retrieve of documents. The taxonomy complies with international web standards as defined by the W3C (World Wide Web Consortium). (author

Nuclear Reactor RA Safety Report, Vol. 8, Auxiliary system

International Nuclear Information System (INIS)

1986-11-01

This volume describes RA reactor auxiliary systems, as follows: special ventilation system, special drainage system, hot cells, systems for internal transport. Ventilation system is considered as part of the reactor safety and protection system. Its role is eliminate possible radioactive particles dispersion in the environment. Special drainage system includes pipes and reservoirs with the safety role, meaning absorption or storage of possible radioactive waste water from the reactor building. Hot cells existing in the RA reactor building are designed for production of sealed radioactive sources, including packaging and transport [sr

HLA-DR alpha 2 mediates negative signalling via binding to Tirc7 leading to anti-inflammatory and apoptotic effects in lymphocytes in vitro and in vivo.

Directory of Open Access Journals (Sweden)

Grit-Carsta Bulwin

Full Text Available Classically, HLA-DR expressed on antigen presenting cells (APC initiates lymphocyte activation via presentation of peptides to TCR bearing CD4+ T-Cells. Here we demonstrate that HLA-DR alpha 2 domain (sHLA-DRalpha2 also induces negative signals by engaging TIRC7 on lymphocytes. This interaction inhibits proliferation and induces apoptosis in CD4+ and CD8+ T-cells via activation of the intrinsic pathway. Proliferation inhibition is associated with SHP-1 recruitment by TIRC7, decreased phosphorylation of STAT4, TCR-zeta chain & ZAP70, and inhibition of IFN-gamma and FasL expression. HLA-DRalpha2 and TIRC7 co-localize at the APC-T cell interaction site. Triggering HLA-DR - TIRC7 pathway demonstrates that sHLA-DRalpha2 treatment inhibits proinflammatory-inflammatory cytokine expression in APC & T cells after lipopolysaccaride (LPS stimulation in vitro and induces apoptosis in vivo. These results suggest a novel antiproliferative role for HLA-DR mediated via TIRC7, revise the notion of an exclusive stimulatory interaction of HLA-DR with CD4+ T cells and highlights a novel physiologically relevant regulatory pathway.

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.

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

The Mythical, Fantastic and Allegorical Sphere of D.R. Popescu’s Prose

Directory of Open Access Journals (Sweden)

Paul Dugneanu

2016-12-01

Full Text Available The literature belonging to various genres extended mythological narrative, given that in both cases the main focus is on the narrative of events that took place in a past more or less fabulous. The extension of myth in ritual demonstrates that the message sent by the first is a truth. A convincing argument for this assumption is the fact that in traditional societies the life is highly ritualized. The existence, the experiences and pursuits are modeled after the mythical scheme. The only one that could legitimize them and could offer an entire authority is the myth because man follows his behavior revealed by myth but its consequences also. In D.R. Popescu’s prose, the myth descends to human understanding and living the story is much more possible. The true meanings are deep and paradoxically, not only because it offers solutions to various problems but because it calls the archaic man to transform his condition. Hence, the myth represents a human’s dream to transcend the mortal condition and to integrate his existence in a sacred universe. The mythical vitalism takes place in a system of its own affirmation and the human is showcased excessively in multiple perspectives, drawn to thresholds of experiences.

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

International Symposium on Special Topics in Chemical Propulsion (8th): Advancements in Energetic Materials and Chemical Propulsion Held in Cape Town, South Africa on 2-6 November 2009

Science.gov (United States)

2009-11-06

Mark Morgan4 USA Dr. Tam Nguyen9,7,6,1,2 Australia Prof. Takashi Niioka6,8 Japan Prof. Boris V. Novozhilov6,8 Russia Dr. Elaine S. Oran8 USA Dr...predicted to continue for the foreseeable future. The lessons learned from other international peacekeeping forces in foreign countries, has a direct...reprocessing or blending again to meet the specific requirements. Another advantage is that after mixing, the excess product can be reheated and used

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

Lack of death receptor 4 (DR4) expression through gene promoter methylation in gastric carcinoma.

Science.gov (United States)

Lee, Kyung Hwa; Lim, Sang Woo; Kim, Ho Gun; Kim, Dong Yi; Ryu, Seong Yeob; Joo, Jae Kyun; Kim, Jung Chul; Lee, Jae Hyuk

2009-07-01

To determine the underlying mechanism for the differential expression, the extent of promoter methylation in tumor necrosis factor-related apoptosis-inducing ligand (TRAIL)-related genes acting downstream of TRAIL was examined in early and advanced gastric carcinomas. The extent of promoter methylation in the DR4, DR5, DcR1, DcR2, and CASP8 genes was quantified using bisulfite modification and methylation-specific polymerase chain reaction. The promoters for DcR1, DcR2, and CASP8 were largely unmethylated in early gastric carcinoma, advanced gastric carcinoma, and controls, with no significant difference among them. Protein levels of DR4, DcR1, and DcR2 as revealed by immunohistochemistry correlated with the extent of the respective promoter methylation (P < 0.05 in all cases). Hypomethylation, rather than hypermethylation, of the DR4 promoter was noted in invasive gastric malignancies, with statistical significance (P = 0.003). The promoter methylation status of TRAIL receptors in gastric carcinoma may have clinical implications for improving therapeutic strategies in patients with gastric carcinoma.

Application of S-CO{sub 2} Cycle for Small Modular Reactor coupled with Desalination System

Energy Technology Data Exchange (ETDEWEB)

Lee, Won Woong; Bae, Seong Jun; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

2016-10-15

The Korean small modular reactor, SMART (System-integrated Modular Advanced ReacTor, 100MWe), is designed to achieve enhanced safety and improved economics through reliable passive safety systems, a system simplification and component modularization. SMART can generate electricity and provide water by seawater desalination. However, due to the desalination aspect of SMART, the total amount of net electricity generation is decreased from 100MWe to 90MWe. The authors suggest in this presentation that the reduction of electricity generation can be replenished by applying S-CO{sub 2} power cycle technology. The S-CO{sub 2} Brayton cycle, which is recently receiving significant attention as the next generation power conversion system, has some benefits such as high cycle efficiency, simple configuration, compactness and so on. In this study, the cycle performance analysis of the S-CO{sub 2} cycles for SMART with desalination system is conducted. The simple recuperated S-CO{sub 2} cycle is revised for coupling with desalination system. The three revised layout are proposed for the cycle performance comparison. In this results of the 3rd revised layout, the cycle efficiency reached 37.8%, which is higher than the efficiency of current SMART with the conventional power conversion system 30%.

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

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

Energy Technology Data Exchange (ETDEWEB)

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

1996-12-31

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

The Research of Dr. Joanne Simpson: Fifty Years Investigating Hurricanes, Tropical Clouds and Cloud Systems

Science.gov (United States)

Tao, W. -K.; Halverson, J.; Adler, R.; Garstang, M.; Houze, R., Jr.; LeMone, M.; Pielke, R., Sr.; Woodley, W.; O'C.Starr, David (Technical Monitor)

2001-01-01

This AMS Meteorological Monographs is dedicated to Dr. Joanne Simpson for her many pioneering research efforts in tropical meteorology during her fifty-year career. Dr. Simpson's major areas of scientific research involved the "hot tower" hypothesis and its role in hurricanes, structure and maintenance of trade winds, air-sea interaction, and observations and the mechanism for hurricanes and waterspouts. She was also a pioneer in cloud modeling with the first one-dimensional model and had the first cumulus model on a computer. She also played a major role in planning and leading observational experiments on convective cloud systems. The launch of the Tropical Rainfall Measuring Mission (TRMM) satellite, a joint U.S.-Japan project, in November of 1997 made it possible for quantitative measurements of tropical rainfall to be obtained on a continuous basis over the entire global tropics. Dr. Simpson was the TRAM Project Scientist from 1986 until its launch in 1997. Her efforts during this crucial period ensured that the mission was both well planned scientifically and well engineered as well as within budget. In this paper, Dr. J. Simpson's nine specific accomplishments during her fifty-year career: (1) hot tower hypothesis, (2) hurricanes, (3) airflow and clouds over heated islands, (4) cloud models, (5) trade winds and their role in cumulus development, (6) air-sea interaction, (7) cloud-cloud interactions and mergers, (8) waterspouts, and (9) TRMM science, will be described and discussed.

Literature search and review of research involving radioisotopes conducted by Dr. G.E. Burch at Charity Hospital in New Orleans, Louisiana under the auspices of Tulane University during the 1940s,1950s, and 1960s

International Nuclear Information System (INIS)

Brooks, F.; Curtis, E.C.; Forrester, G.; Roth, V.; Spickard, J.; Webster, B.; Engle, J.; Perkins, L.; Powell, S.

1994-01-01

This report presents a synopsis of research performed by Dr. G.E. Burch during the 1940s, 1950s, and 1960s at Charity Hospital in New Orleans, Louisiana. Four technical experts have reviewed twenty-seven research published in peer-reviewed research journals and proceedings by Dr. Burch and his colleagues between the years 1946 and 1968. The papers were grouped prior to the review into three categories represented in this report by the following chapter titles: Studies Involving Human Subjects; Isotopic Studies Not Involving Human or Canine Subjects; and Studies Involving Dogs as Test Models. The experts' reviews addressed five areas. What, if Any, Is the Scientific Value of the Research on Which These Studies Are Based?; Did the Research Provide Medicine with New and Useful Information?; What Contributions Did This Research Make to Patient Care or to the Understanding of the Disease Process?; What Was Known Medically about Matters Addressed by This Research at the Time It Was Being Conducted? and Is There Documentation That Shows Informed Consent?

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.

But They Talk: Historical and Modern Mechanisms Behind the Beast Folk’s Language in The Island of Dr. Moreau

Directory of Open Access Journals (Sweden)

Bonnie Cross

2014-12-01

Full Text Available The Beast Folk in H.G. Wells’ The Island of Dr. Moreau (1896 use language to raise the fear of human degeneration by revealing the inner animal within humanity. Moreau re-creates the physical mechanisms for speech such as the larynx, but is also able to manipulate the brain to create the necessary structures for speech, previously unique to the human brain, into nonhumans. Applying Darwin’s theory that the continued use of speech led to the physical and mental changes of humans, the argument can be made that ceasing to use speech would weaken these structures of speech. After Moreau’s death, the Beast Folk no longer heed the Law and stop speaking, becoming more animalistic through their silence. Prendick also loses his language after the death of Moreau and Montgomery and begins to struggle differentiating the Beast Folk from humans. The Island of Dr. Moreau addresses the Victorian anxiety regarding the use of language as a definite boundary between humans and animals by suggesting that language fails to keep the inner animal of humanity at bay. Neuroscience has linked animal and human sounds revealing the mechanisms responsible for the production and understanding of language creating a new paradigm to explore.

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.

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

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

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.

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

U. S. Utility Leadership in Requirements For Passive Reactors

International Nuclear Information System (INIS)

Kim, Jcng H.; Layman, William H.

1991-01-01

Utility leadership from both U.S. utilities and international utilities, is a key element in the U. S. Advanced Light Water Reactor Program. International utilities have played a very import Design reviews by the utilities participating in the ALRR Program will ensure that all of the utility requirements are met while design work is being carried out. Our mission is to achieve NRC certification of designs that reflect the needs of the utilities and we believe that this will play an important role in the resurgence of nuclear plant construction in the United States. As stated in the Nuclear Power Oversight Committee's Strategic Plan For Building New Nuclear Power Plants : 'The extensive operating experience with today's light water reactors (LWRs), and the promise shown in recent technical developments, leads the industry to the conclusion that the next nuclear plants ordered in the United States will be advanced light water reactors (A LWRs). Two types are under development : units of large output (1300 MW) called 'evolutionary' A LWRs and units of mid-size output (600 MW) called 'Passive' A LWRs. The term 'passive' refers to the safety features which depend more on natural processes such as gravity and buoyancy than on powered equipment such as pumps

FigS8.txt

Data.gov (United States)

U.S. Environmental Protection Agency — This is an ASCII file with georeferencing information containing data plotted in Figure S8 of the supplemental information section of the manuscript. This dataset is...

Implementation of the Total Quality Leadership Process in U.S. Marine Corps Field Contracting Offices

Science.gov (United States)

1993-06-01

8 b. Dr. Joseph M. Juran ... .......... 11 c. Dr. Kaoru Ishikawa .... .......... .. 13 2. TQM in the Department of Defense ..... ... 15 3. TQL in the...qualification, etc. [Ref. 8] 12 c. Dr. Kaoru Ishikawa Japan is often lauded as the world’s leader in the quality movement. To understand how the Japanese view the...34The Real Message of the Quality Movement: Building Learning Organizations", Journal for Quality and Participation, March 1992. 10. Ishikawa , Kaoru

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...

Operational characteristics analysis of a 8 mH class HTS DC reactor for an LCC type HVDC system

International Nuclear Information System (INIS)

Kim, S. K.; Go, B. S.; Dinh, M. C.; Park, M.; Yu, I. K.; Kim, J. H.

2015-01-01

Many kinds of high temperature superconducting (HTS) devices are being developed due to its several advantages. In particular, the advantages of HTS devices are maximized under the DC condition. A line commutated converter (LCC) type high voltage direct current (HVDC) transmission system requires large capacity of DC reactors to protect the converters from faults. However, conventional DC reactor made of copper causes a lot of electrical losses. Thus, it is being attempted to apply the HTS DC reactor to an HVDC transmission system. The authors have developed a 8 mH class HTS DC reactor and a model-sized LCC type HVDC system. The HTS DC reactor was operated to analyze its operational characteristics in connection with the HVDC system. The voltage at both ends of the HTS DC reactor was measured to investigate the stability of the reactor. The voltages and currents at the AC and DC side of the system were measured to confirm the influence of the HTS DC reactor on the system. Two 5 mH copper DC reactors were connected to the HVDC system and investigated to compare the operational characteristics. In this paper, the operational characteristics of the HVDC system with the HTS DC reactor according to firing angle are described. The voltage and current characteristics of the system according to the types of DC reactors and harmonic characteristics are analyzed. Through the results, the applicability of an HTS DC reactor in an HVDC system is confirmed

Operational characteristics analysis of a 8 mH class HTS DC reactor for an LCC type HVDC system

Energy Technology Data Exchange (ETDEWEB)

Kim, S. K.; Go, B. S.; Dinh, M. C.; Park, M.; Yu, I. K. [Changwon National University, Changwon (Korea, Republic of); Kim, J. H. [Daejeon University, Daejeon (Korea, Republic of)

2015-03-15

Many kinds of high temperature superconducting (HTS) devices are being developed due to its several advantages. In particular, the advantages of HTS devices are maximized under the DC condition. A line commutated converter (LCC) type high voltage direct current (HVDC) transmission system requires large capacity of DC reactors to protect the converters from faults. However, conventional DC reactor made of copper causes a lot of electrical losses. Thus, it is being attempted to apply the HTS DC reactor to an HVDC transmission system. The authors have developed a 8 mH class HTS DC reactor and a model-sized LCC type HVDC system. The HTS DC reactor was operated to analyze its operational characteristics in connection with the HVDC system. The voltage at both ends of the HTS DC reactor was measured to investigate the stability of the reactor. The voltages and currents at the AC and DC side of the system were measured to confirm the influence of the HTS DC reactor on the system. Two 5 mH copper DC reactors were connected to the HVDC system and investigated to compare the operational characteristics. In this paper, the operational characteristics of the HVDC system with the HTS DC reactor according to firing angle are described. The voltage and current characteristics of the system according to the types of DC reactors and harmonic characteristics are analyzed. Through the results, the applicability of an HTS DC reactor in an HVDC system is confirmed.

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

Dr. William O. Coffee and his absorption cure for cataract.

Science.gov (United States)

Ferry, A P

1989-08-01

Dr. William O. Coffee was an ophthalmologist who conducted an office and mail-order practice in the Midwest from the 1880s until 1927. His main stock in trade was a self-discovered absorption cure for a variety of ocular diseases, with particular emphasis on the medical cure of cataracts. Dr. Coffee's career was a checkered one, marked by dubious credentials, exuberant self-promotion, unlikely and exaggerated claims of medical successes, plagiarism, and rejection by the medical "establishment." Certain parallels may be drawn between his activities and some currently observed practices in ophthalmology.

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.

The status of the PIK reactor

Energy Technology Data Exchange (ETDEWEB)

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

1992-07-01

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

Gene Expression Ratios Lead to Accurate and Translatable Predictors of DR5 Agonism across Multiple Tumor Lineages.

Directory of Open Access Journals (Sweden)

Anupama Reddy

Full Text Available Death Receptor 5 (DR5 agonists demonstrate anti-tumor activity in preclinical models but have yet to demonstrate robust clinical responses. A key limitation may be the lack of patient selection strategies to identify those most likely to respond to treatment. To overcome this limitation, we screened a DR5 agonist Nanobody across >600 cell lines representing 21 tumor lineages and assessed molecular features associated with response. High expression of DR5 and Casp8 were significantly associated with sensitivity, but their expression thresholds were difficult to translate due to low dynamic ranges. To address the translational challenge of establishing thresholds of gene expression, we developed a classifier based on ratios of genes that predicted response across lineages. The ratio classifier outperformed the DR5+Casp8 classifier, as well as standard approaches for feature selection and classification using genes, instead of ratios. This classifier was independently validated using 11 primary patient-derived pancreatic xenograft models showing perfect predictions as well as a striking linearity between prediction probability and anti-tumor response. A network analysis of the genes in the ratio classifier captured important biological relationships mediating drug response, specifically identifying key positive and negative regulators of DR5 mediated apoptosis, including DR5, CASP8, BID, cFLIP, XIAP and PEA15. Importantly, the ratio classifier shows translatability across gene expression platforms (from Affymetrix microarrays to RNA-seq and across model systems (in vitro to in vivo. Our approach of using gene expression ratios presents a robust and novel method for constructing translatable biomarkers of compound response, which can also probe the underlying biology of treatment response.

Gene Expression Ratios Lead to Accurate and Translatable Predictors of DR5 Agonism across Multiple Tumor Lineages.

Science.gov (United States)

Reddy, Anupama; Growney, Joseph D; Wilson, Nick S; Emery, Caroline M; Johnson, Jennifer A; Ward, Rebecca; Monaco, Kelli A; Korn, Joshua; Monahan, John E; Stump, Mark D; Mapa, Felipa A; Wilson, Christopher J; Steiger, Janine; Ledell, Jebediah; Rickles, Richard J; Myer, Vic E; Ettenberg, Seth A; Schlegel, Robert; Sellers, William R; Huet, Heather A; Lehár, Joseph

2015-01-01

Death Receptor 5 (DR5) agonists demonstrate anti-tumor activity in preclinical models but have yet to demonstrate robust clinical responses. A key limitation may be the lack of patient selection strategies to identify those most likely to respond to treatment. To overcome this limitation, we screened a DR5 agonist Nanobody across >600 cell lines representing 21 tumor lineages and assessed molecular features associated with response. High expression of DR5 and Casp8 were significantly associated with sensitivity, but their expression thresholds were difficult to translate due to low dynamic ranges. To address the translational challenge of establishing thresholds of gene expression, we developed a classifier based on ratios of genes that predicted response across lineages. The ratio classifier outperformed the DR5+Casp8 classifier, as well as standard approaches for feature selection and classification using genes, instead of ratios. This classifier was independently validated using 11 primary patient-derived pancreatic xenograft models showing perfect predictions as well as a striking linearity between prediction probability and anti-tumor response. A network analysis of the genes in the ratio classifier captured important biological relationships mediating drug response, specifically identifying key positive and negative regulators of DR5 mediated apoptosis, including DR5, CASP8, BID, cFLIP, XIAP and PEA15. Importantly, the ratio classifier shows translatability across gene expression platforms (from Affymetrix microarrays to RNA-seq) and across model systems (in vitro to in vivo). Our approach of using gene expression ratios presents a robust and novel method for constructing translatable biomarkers of compound response, which can also probe the underlying biology of treatment response.

A Small Modular Reactor Design for Multiple Energy Applications: HTR50S

Energy Technology Data Exchange (ETDEWEB)

Yan, X.; Tachibana, Y.; Ohashi, H.; Sato, H.; Tazawa, Y.; Kunitomi, K. [Japan Atomic Energy Agency, Ibaraki (Japan)

2013-06-15

HTR50S is a small modular reactor system based on HTGR. It is designed for a triad of applications to be implemented in successive stages. In the first stage, a base plant for heat and power is constructed of the fuel proven in JAEA's 950 .deg. C, 30MWt test reactor HTTR and a conventional steam turbine to minimize development risk. While the outlet temperature is lowered to 750 .deg. C for the steam turbine, thermal power is raised to 50MWt by enabling 40% greater power density in 20% taller core than the HTTR. However the fuel temperature limit and reactor pressure vessel diameter are kept. In second stage, a new fuel that is currently under development at JAEA will allow the core outlet temperature to be raised to 900 .deg. C for the purpose of demonstrating more efficient gas turbine power generation and high temperature heat supply. The third stage adds a demonstration of nuclear-heated hydrogen production by a thermochemical process. A licensing approach to coupling high temperature industrial process to nuclear reactor will be developed. The low initial risk and the high longer-term potential for performance expansion attract development of the HTR50S as a multipurpose industrial or distributed energy source.

Nuclear reactor safety program in U.S. Department of Energy and future perspectives

International Nuclear Information System (INIS)

Song, Y.T.

1987-01-01

The U.S. Department of Energy (DOE) establishes policy, issues orders, and assures compliance with requirements. The contractors who design, construct, modify, operate, maintain and decommission DOE reactors, set forth the assessment of the safety of cognizant reactors and impliment DOE orders. Teams of experts in the Depatment, through scheduled and unscheduled review programs, reassess the safety of reactors in every phases of their lives. As new technology develops, the safety programs are reevaluated and policies are modified to accommodate these new technologies. The diagnostic capabilities of the computer using multiple alarms to enhance detection of defects and control of a reactor have been greatly utilized in reactor operating systems. The application of artificial intelligence (AI) technologies for diagnostic and even for the decision making process in the event of reactor accidents would be one of the future trends in reactor safety programs. (author)

The great neurosis of Dr. Joseph Gerard.

Science.gov (United States)

Lefrère, Jean-Jacques; Rouillon, Frédéric

2013-01-01

The Great Neurosis, of Dr. Joseph Gerard, was published in 1889 in Paris. The book, intended for the general public, shows the different varieties of neuroses through picturesque and instructive examples. Its scientific and medical value is poor, but provides us with the various meanings of the word 'neurosis' in the late nineteenth century. Copyright © 2013 S. Karger AG, Basel.

Preliminary Design of S-CO2 Brayton Cycle for KAIST Micro Modular Reactor

International Nuclear Information System (INIS)

Kim, Seong Gu; Kim, Min Gil; Bae, Seong Jun; Lee, Jeong Ik

2013-01-01

This paper suggests a complete modular reactor with an innovative concept of reactor cooling by using a supercritical carbon dioxide directly. Authors propose the supercritical CO 2 Brayton cycle (S-CO 2 cycle) as a power conversion system to achieve small volume of power conversion unit (PCU) and to contain the core and PCU in one vessel for the full modularization. This study suggests a conceptual design of small modular reactor including PCU which is named as KAIST Micro Modular Reactor (MMR). As a part of ongoing research of conceptual design of KAIST MMR, preliminary design of power generation cycle was performed in this study. Since the targets of MMR are full modularization of a reactor system with S-CO 2 coolant, authors selected a simple recuperated S-CO 2 Brayton cycle as a power conversion system for KAIST MMR. The size of components of the S-CO 2 cycle is much smaller than existing helium Brayton cycle and steam Rankine cycle, and whole power conversion system can be contained with core and safety system in one containment vessel. From the investigation of the power conversion cycle, recompressing recuperated cycle showed higher efficiency than the simple recuperated cycle. However the volume of heat exchanger for recompressing cycle is too large so more space will be occupied by heat exchanger in the recompressing cycle than the simple recuperated cycle. Thus, authors consider that the simple recuperated cycle is more suitable for MMR. More research for the KAIST MMR will be followed in the future and detailed information of reactor core and safety system will be developed down the road. More refined cycle layout and design of turbomachinery and heat exchanger will be performed in the future study

The clustering of the SDSS-IV extended Baryon Oscillation Spectroscopic Survey DR14 quasar sample: structure growth rate measurement from the anisotropic quasar power spectrum in the redshift range 0.8 < z < 2.2

Science.gov (United States)

Gil-Marín, Héctor; Guy, Julien; Zarrouk, Pauline; Burtin, Etienne; Chuang, Chia-Hsun; Percival, Will J.; Ross, Ashley J.; Ruggeri, Rossana; Tojerio, Rita; Zhao, Gong-Bo; Wang, Yuting; Bautista, Julian; Hou, Jiamin; Sánchez, Ariel G.; Pâris, Isabelle; Baumgarten, Falk; Brownstein, Joel R.; Dawson, Kyle S.; Eftekharzadeh, Sarah; González-Pérez, Violeta; Habib, Salman; Heitmann, Katrin; Myers, Adam D.; Rossi, Graziano; Schneider, Donald P.; Seo, Hee-Jong; Tinker, Jeremy L.; Zhao, Cheng

2018-06-01

We analyse the clustering of the Sloan Digital Sky Survey IV extended Baryon Oscillation Spectroscopic Survey Data Release 14 quasar sample (DR14Q). We measure the redshift space distortions using the power-spectrum monopole, quadrupole, and hexadecapole inferred from 148 659 quasars between redshifts 0.8 and 2.2, covering a total sky footprint of 2112.9 deg2. We constrain the logarithmic growth of structure times the amplitude of dark matter density fluctuations, fσ8, and the Alcock-Paczynski dilation scales that allow constraints to be placed on the angular diameter distance DA(z) and the Hubble H(z) parameter. At the effective redshift of zeff = 1.52, fσ8(zeff) = 0.420 ± 0.076, H(z_eff)=[162± 12] (r_s^fid/r_s) {km s}^{-1} Mpc^{-1}, and D_A(z_eff)=[1.85± 0.11]× 10^3 (r_s/r_s^fid) Mpc, where rs is the comoving sound horizon at the baryon drag epoch and the superscript `fid' stands for its fiducial value. The errors take into account the full error budget, including systematics and statistical contributions. These results are in full agreement with the current Λ-Cold Dark Matter cosmological model inferred from Planck measurements. Finally, we compare our measurements with other eBOSS companion papers and find excellent agreement, demonstrating the consistency and complementarity of the different methods used for analysing the data.

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

Multigroup P8 - elastic scattering matrices of main reactor elements

International Nuclear Information System (INIS)

Garg, S.B.; Shukla, V.K.

1979-01-01

To study the effect of anisotropic scattering phenomenon on shielding and neutronics of nuclear reactors multigroup P8-elastic scattering matrices have been generated for H, D, He, 6 Li, 7 Li, 10 B, C, N, O, Na, Cr, Fe, Ni, 233 U, 235 U, 238 U, 239 Pu, 240 Pu, 241 Pu and 242 Pu using their angular distribution, Legendre coefficient and elastic scattering cross-section data from the basic ENDF/B library. Two computer codes HSCAT and TRANS have been developed to complete this task for BESM-6 and CDC-3600 computers. These scattering matrices can be directly used as input to the transport theory codes ANISN and DOT. (auth.)

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

International Nuclear Information System (INIS)

Lee, Byeonghee; Yang, Soohyung

2013-01-01

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

Dr Fabiola Gianotti has been selected by CERN Council to become next CERN Director General

CERN Multimedia

Brice, Maximilien

2014-01-01

With the next Director-General announced, watch the press conference starting in a few minutes via http://cern.ch/webcast/ and send your questions via Twitter to @CERNpressoffice CERN Council selects Italian physicist, Dr Fabiola Gianotti, as CERN’s next Director-General. Dr Gianotti’s mandate will begin on 1 January 2016 and run for a period of five years, read more: http://cern.ch/go/tN09F

Herniated Nucleus Pulposus in Dr. Hasan Sadikin General Hospital Bandung Indonesia

Directory of Open Access Journals (Sweden)

Annisa Ikhsanawati

2015-06-01

Full Text Available Background: Herniated nucleus pulposus (HNP is one of the most common diseases of the spine. For an optimal management and prevention, there’s a need for data on factors related to the onset of complaints because this disease lowers the quality of life and increases morbidity. This study is aimed to see the scale and pattern of the HNP in Dr. Hasan Sadikin General Hospital, Bandung. Methods: This is a descriptive study with the design of case series, data was obtained from medical records of patients with the diagnosis of HNP in the inpatient care of Dr. Hasan Sadikin General Hospital in the period of 2007–2011. Results: According to the study on 79 patients, with 43 men and 36 women, the highest incidence was at the age group of 51–60 years old (31.6% and most common occupation was civil servant (11.4%. The most common clinical symptoms were sciatica (51.9% and low back pain (51.9%. Most frequent location was in the lumbar vertebrae at the level of L5–S1 (58.2%. Trauma was found to be the highest relatable history in the patients (39.2%. Therapy of choice was primarily conservative (58.2% and most patients went home after the progression (84.8%. The year 2007 showed the highest prevalence of HNP at 25.3%. The most common clinical symptoms were sciatica (51.9% and low back pain (51.9% Conclusions: The most common clinical symptoms were sciatica and low back pain. Most frequent location was in the lumbar vertebrae at the level L5–S1.

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.

Načini podpore prevajanju v državah Evropske unije

OpenAIRE

Šimenc, Agata

2017-01-01

Države Evropske unije poznajo različne oblike podpore, ki pomagajo pri spodbujanju in financiranju prevajanja literature v tuje jezike in s tem skrbijo za promocijo države, njene kulture, zlasti pa njene literature in njenih literarnih ustvarjalcev v tujini. Ti sistemi podpore so pomembni predvsem za literature, ki nastajajo v manj razširjenih jezikih in zato težje pridejo do tujih bralcev. Naloga primerja različne podpore prevajanju nacionalnih leposlovij v tuje jezike, ki obstajajo v različ...

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

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

Directory of Open Access Journals (Sweden)

Radouane Oubabi

2014-03-01

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

Biogas Production from Brewer’s Yeast Using an Anaerobic Sequencing Batch Reactor

Directory of Open Access Journals (Sweden)

Gregor Drago Zupančič

2017-01-01

Full Text Available Renewable energy sources are becoming increasingly important in the beverage and food industries. In the brewing industry, a significant percentage of the used raw materials finishes the process as secondary resource or waste. The research on the anaerobic digestion of brewer’s yeast has been scarce until recent years. One of the reasons for this is its use as a secondary resource in the food industry and as cattle feed. Additionally, market value of brewer’s yeast is higher than its energy value. Due to the increase of energy prices, brewer’s yeast has become of interest as energy substrate despite its difficult degradability in anaerobic conditions. The anaerobic co-digestion of brewer’s yeast and anaerobically treated brewery wastewater was studied using a pilot-scale anaerobic sequencing batch reactor (ASBR seeded with granular biomass. The experiments showed very good and stable operation with an organic loading rate of up to 8.0 kg/(m3·day, and with a maximum achieved organic loading rate of 13.6 kg/(m3·day in a single cycle. A specific biogas productivity of over 0.430 m3/kg of the total chemical oxygen demand (COD inserted, and total COD removal efficiencies of over 90 % were achieved. This study suggests that the brewer’s yeast can be successfully digested in an ASBR without adverse effects on the biogas production from brewer’s yeast/wastewater mixtures of up to 8 % (by volume. By using the brewer’s yeast in the ASBR process, the biogas production from brewery wastewater could be increased by 50 %.

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

Operating reactors licensing actions summary. Volume 5, No. 8

International Nuclear Information System (INIS)

1985-10-01

This 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 Resource Management

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

Proceedings of the 8. Brazilian Meeting on Reactor Physics and Thermal Hydraulics

International Nuclear Information System (INIS)

1991-01-01

Some papers about pressurized light water reactors, fast reactors, accident analysis, transients, research reactors, nuclear data collection, thermal hydraulics, reactor monitoring, neutronics are presented. (E.G.)

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.

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

Paul S Follansbee

Indian Academy of Sciences (India)

Home; Journals; Resonance – Journal of Science Education. Paul S Follansbee. Articles written in Resonance – Journal of Science Education. Volume 11 Issue 6 June 2006 pp 8-25 General Article. Dr Smith goes to Los Alamos - Cyril Stanley Smith, Plutonium Metallurgy, and the Manhattan Project · Srivilliputhur G ...

U.S. Non-proliferation policy and programs regarding use of high-enriched uranium in research reactors

International Nuclear Information System (INIS)

Lewis, R.A.

1993-01-01

Uranium enriched to 90-93%, supplied by the U.S., is now used in 141 research and test reactors in 35 countries around the world with a cumulative power of 1714 mw. Since of the order of 3 kg of 235 U is involved annually in fuel fabrication, fresh fuel transport and storage, reactor operation, and spent fuel cooling and return per megawatt of research reactor power, it is estimated that more than 5000 kg of very high-enriched uranium is handled each year to operate these reactors. Recent U.S. assessments have led to the tentative conclusion that in only approximately 11 of these reactors, generally those of highest power or power density, is the use of 90-93% enriched uranium currently a technical necessity. Universal use of the best state-of-the-art fuel technology would permit an estimated 90 of these reactors to use 20% enriched fuel, and estimated 40 others to use 45% enriched fuel, without significant performance degradation. If advanced research reactor fuel development programs currently under way in the U.S. and elsewhere are successful, it may, in fact, be possible to operate virtually all of these reactors on less than 20% enriched uranium in the longer term. The physical and economic practicality of these developmental fuels must, of course, await future assessments

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.

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

International Nuclear Information System (INIS)

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

2009-01-01

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

Demonstration of automated price response in large customers in New York City using Auto-DR and OpenADR

Energy Technology Data Exchange (ETDEWEB)

Kim, Joyce Jihyun [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Schetrit, Oren [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Yin, Rongxin [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States); Kiliccote, Sila [Lawrence Berkeley National Lab. (LBNL), Berkeley, CA (United States)

2014-05-01

Demand response (DR) – allowing customers to respond to reliability requests and market prices by changing electricity use from their normal consumption pattern – continues to be seen as an attractive means of demand-side management and a fundamental smart-grid improvement that links supply and demand. From October 2011 to December 2013, the Demand Response Research Center at Lawrence Berkeley National Laboratory, the New York State Energy Research and Development Authority, and partners Honeywell and Akuacom, have conducted a demonstration project enabling Automated Demand Response (Auto-DR) in large commercial buildings located in New York City using Open Automated Demand Response (OpenADR) communication protocols. In particular, this project focuses on demonstrating how the OpenADR platform, enabled by Akuacom, can automate and simplify interactions between buildings and various stakeholders in New York State and enable the automation of customers’ price response to yield bill savings under dynamic pricing. In this paper, the cost control opportunities under day-ahead hourly pricing and Auto-DR control strategies are presented for four demonstration buildings; present the breakdown of Auto-DR enablement costs; summarize the field test results and their load impact; and show potential bill savings by enabling automated price response under Consolidated Edison’s Mandatory Hourly Pricing (MHP) tariff. For one of the sites, the potential bill savings at the site’s current retail rate are shown. Facility managers were given granular equipment-level opt-out capability to ensure full control of the sites during the Auto-DR implementation. The expected bill savings ranged from 1.1% to 8.0% of the total MHP bill. The automation and enablement costs ranged from $70 to $725 per kW shed. The results show that OpenADR can facilitate the automation of price response, deliver savings to the customers and opt-out capability of the implementation retains control of the

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.

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.

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.

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.

Reactor Neutrino Oscillations: KamLAND and KASKA

International Nuclear Information System (INIS)

Suekane, F.

2006-01-01

Nuclear reactors generate a huge number of low energy ν-bar e 's. The reactor neutrinos have been used to study properties of neutrinos since its discovery a half century ago. Recently, KamLAND group finally discovered reactor neutrino oscillation with average baseline 180 km. According to the 3 flavor scheme of standard theory and measured oscillation parameters so far, the reactor neutrino is expected to perform another type of small oscillation at a baseline 1.8 km. KASKA experiment is a project to detect this small oscillation and to measure the last neutrino mixing angle θ 13 by using the world most powerful reactor complex, Kashiwazaki-Kariwa nuclear power station. In this proceedings, phenomena of neutrino oscillation and the two reactor oscillation experiments, KamLAND and KASKA, are introduced

Advanced liquid metal reactor development at Argonne National Laboratory during the 1980s

International Nuclear Information System (INIS)

Wade, D.C.

1990-01-01

Argonne National Laboratory's (ANL'S) effort to pursue the exploitation of liquid metal cooled reactor (LMR) characteristics has given rise to the Integral Fast Reactor (IFR) concept, and has produced substantial technical advancement in concept implementation which includes demonstration of high burnup capability of metallic fuel, demonstration of injection casting fabrication, integral demonstration of passive safety response, and technical feasibility of pyroprocessing. The first half decade of the 90's will host demonstration of the IFR closed fuel cycle technology at the prototype scale. The EBR-II reactor will be fueled with ternary alloy fuel in HT-9 cladding and ducts, and pyroprocessing and injection casting refabrication of EBR-II fuel will be conducted using near-commercial sized equipment at the Fuel cycle Facility (FCF) which is co-located adjacent to EBR-II. Demonstration will start in 1992. The demonstration of passive safety response achievable with the IFR design concept, (already done in EBR-II in 1986) will be repeated in the mid 90's using the IFR prototype recycle fuel from the FCF. The demonstration of scrubbing of the reprocessing fission product waste stream, with recycle of the transuranics to the reactor for consumption, will also occur in the mid 90's. 30 refs

Inflammation and pancreatic cancer: molecular and functional interactions between S100A8, S100A9, NT-S100A8 and TGFβ1.

Science.gov (United States)

Basso, Daniela; Bozzato, Dania; Padoan, Andrea; Moz, Stefania; Zambon, Carlo-Federico; Fogar, Paola; Greco, Eliana; Scorzeto, Michele; Simonato, Francesca; Navaglia, Filippo; Fassan, Matteo; Pelloso, Michela; Dupont, Sirio; Pedrazzoli, Sergio; Fassina, Ambrogio; Plebani, Mario

2014-03-26

In order to gain further insight on the crosstalk between pancreatic cancer (PDAC) and stromal cells, we investigated interactions occurring between TGFβ1 and the inflammatory proteins S100A8, S100A9 and NT-S100A8, a PDAC-associated S100A8 derived peptide, in cell signaling, intracellular calcium (Cai2+) and epithelial to mesenchymal transition (EMT). NF-κB, Akt and mTOR pathways, Cai2+ and EMT were studied in well (Capan1 and BxPC3) and poorly differentiated (Panc1 and MiaPaCa2) cell lines. NT-S100A8, one of the low molecular weight N-terminal peptides from S100A8 to be released by PDAC-derived proteases, shared many effects on NF-κB, Akt and mTOR signaling with S100A8, but mainly with TGFβ1. The chief effects of S100A8, S100A9 and NT-S100A8 were to inhibit NF-κB and stimulate mTOR; the molecules inhibited Akt in Smad4-expressing, while stimulated Akt in Smad4 negative cells. By restoring Smad4 expression in BxPC3 and silencing it in MiaPaCa2, S100A8 and NT-S100A8 were shown to inhibit NF-κB and Akt in the presence of an intact TGFβ1 canonical signaling pathway. TGFβ1 counteracted S100A8, S100A9 and NT-S100A8 effects in Smad4 expressing, not in Smad4 negative cells, while it synergized with NT-S100A8 in altering Cai2+ and stimulating PDAC cell growth. The effects of TGFβ1 on both EMT (increased Twist and decreased N-Cadherin expression) and Cai2+ were antagonized by S100A9, which formed heterodimers with TGFβ1 (MALDI-TOF/MS and co-immuno-precipitation). The effects of S100A8 and S100A9 on PDAC cell signaling appear to be cell-type and context dependent. NT-S100A8 mimics the effects of TGFβ1 on cell signaling, and the formation of complexes between TGFβ1 with S100A9 appears to be the molecular mechanism underlying the reciprocal antagonism of these molecules on cell signaling, Cai2+ and EMT.

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...

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)

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

[Psychoanalysis in Buchenwald. Conversations between Bruno Bettelheim, Dr. Brief and Ernst Federn].

Science.gov (United States)

Federn, E

1988-01-01

Ernst Federn met in the concentration camp Buchenwald Bruno Bettelheim and the Chechoslovakian psychoanalyst Dr. Brief. They discussed the application of psychoanalytic knowledge to the situation in the camp, particularly the defense mechanism of "identification with the aggressor". Of the three, Bettelheim was released after one year, Dr. Brief died in Ausschwitz and Ernst Federn was liberated by the U.S.A. Army. How he could use his psychoanalytic knowledge to survive but also to help fellow prisoners is demonstrated.

Dr. Nele Karajlić in the framework of the “Mew primitives”

Directory of Open Access Journals (Sweden)

Vučković Borislava

2017-01-01

Full Text Available The “New Primitives” is an alternative, and later, a cultural movement that emerged in Sarajevo in the late 1970s and early 1980s; the movement officially ceased to exist in 1987. The most substantial cultural capital of the movement relates to “Zabranjeno pušenje” (“No Smoking” band and the radio and television show Top lista nadrealista (Top List of Surrealists, while the biggest individual cultural capital lies with Nenad Janković, a phony doctor with the “erotic” pseudonym of Dr. Nele Karajlić. The subject matter of this article is the authorship and co-authorship of Dr. Nele Karajlić within the “No Smoking” band and the television show Top List of Surrealists in the cultural space of the socialist Yugoslavia during the 1980s.

Dr. von Braun With a Model of a Launch Vehicle

Science.gov (United States)

1950-01-01

Dr. von Braun stands beside a model of the upper stage (Earth-returnable stage) of the three-stage launch vehicle built for the series of the motion picture productions of space flight produced by Walt Disney in the mid-1950's.

Experimental validation of TASS/SMR-S critical flow model for the integral reactor SMART

Energy Technology Data Exchange (ETDEWEB)

Seo, Si Won; Ra, In Sik; Kim, Kun Yeup [ACT Co., Daejeon (Korea, Republic of); Chung, Young Jong [Korea Atomic Energy Research Institute, Daejeon (Korea, Republic of)

2011-05-15

An advanced integral PWR, SMART (System- Integrated Modular Advanced ReacTor) is being developed in KAERI. It has a compact size and a relatively small power rating (330MWt) compared to a conventional reactor. Because new concepts are applied to SMART, an experimental and analytical validation is necessary for the safety evaluation of SMART. The analytical safety validation is being accomplished by a safety analysis code for an integral reactor, TASS/SMR-S developed by KAERI. TASS/SMR-S uses a lumped parameter one dimensional node and path modeling for the thermal hydraulic calculation and it uses point kinetics for the reactor power calculation. It has models for a general usage such as a core heat transfer model, a wall heat structure model, a critical flow model, component models, and it also has many SMART specific models such as an once through helical coiled steam generator model, and a condensate heat transfer model. To ensure that the TASS/SMR-S code has the calculation capability for the safety evaluation of SMART, the code should be validated for the specific models with the separate effect test experimental results. In this study, TASS/SMR-S critical flow model is evaluated as compared with SMD (Super Moby Dick) experiment

Electronic properties of GaV 4 S 8

Indian Academy of Sciences (India)

... different in GaV4S8-1 and GaV4S8-2. This statement is strongly supported by the calculated bandwidth per cluster in GaV4S8 (∼0.342 eV in GaV4S8-1 and ∼0.374 eV in GaV4S8-2). A negative magnetoresistance (MR) is also found around 43 K in GaV4S8-2 at 6.0 T magnetic field associated with structural transition.

N2R vs. DR Network Infrastructure Evaluation

DEFF Research Database (Denmark)

Pedersen, Jens Myrup; Roost, Lars Jessen; Toft, Per Nesager

2007-01-01

Recent development of Internet-based services has set higher requirements to network infrastructures in terms of more bandwidth, lower delays and more reliability. Theoretical research within the area of Structural Quality of Service (SQoS) has introduced a new type of infrastructure which meet...... these requirements: N2R infrastructures. This paper contributes to the ongoing research with a case study from North Jutland. An evaluation of three N2R infrastructures compared to a Double Ring (DR) infrastructure will provide valuable information of the practical applicability of N2R infrastructures. In order...... to study if N2R infrastructures perform better than the DR infrastructure, a distribution network was established based on geographical information system (GIS) data. Nodes were placed with respect to demographic and geographical factors. The established distribution network was investigated with respect...

Nurses Caring and Patient’s Satisfaction at Internal Medicine Unit of Dr. Soetomo Hospital, Surabaya

Directory of Open Access Journals (Sweden)

Nur Hasanah

2017-06-01

Full Text Available Patient’s satisfaction is crucial for a hospital, and nursing as an integral part of health care in hospitals also determine the level of patient’s satisfaction. At the order of the clinic nurses deal directly with the public as their client. A direct relationship between the nurse and the client need a behaviour that can be accepted by the whole society. Caring as one of the basic values of nursing, is a phenomenon that affects the way to think, feel and relate to others. This study aimed to analyze the relationship between the nurses caring with patient’s satisfaction by using cross sectional design. Population of this study was patients who were treated in Internal Medicine Unit of Dr. Soetomo Hospital in November 2015. The sample size was 75 people, who were selected  by simple random sampling technique. Data collection was done by filling out the questionnaire, then anayzed by using Chi-square test. Results showed 57.33% of the patients gave judgment of satisfactory to nurse caring behaviour and 42.67% gave a good assessment. 62.67% of the patients said they were satisfied with the caring services. There was a significant relationship between nurses caring with patient satisfaction.

A neutronic feasibility study for LEU conversion of the IR-8 research reactor

International Nuclear Information System (INIS)

Deen, J.R.; Hanan, N.A.; Matos, J.E.; Egorenkov, P.M.; Nasonov, V.A.

1998-01-01

Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU (90%), HEU (36%), and LEU (19.75%) fuel assembly (FA) designs using three dimensional multi-group diffusion theory models benchmarked to detailed Monte Carlo models of the reactor. Comparisons were made of changes in reactivity, cycle length, average 235 U discharge burnup, thermal neutron flux, and control rod worths for the 90% and 36% enriched IRT-3M fuel assembly and the 19.75% enriched IRT-4M fuel assembly with the same fuel management strategy. The results of these comparisons showed that a uranium density of 3.5 g/cm 3 in the fuel meat would be required in the LEU IRT-4M fuel assembly to match the cycle length of the HEU (90%) IRT-3M FA and an LEU density of 3.7 g/cm 3 is needed to match the cycle length of the HEU (36%) IRT-3M FA. (author)

Elektrische apparaten van de ‘Nederlandsche Optiek- en Instrumentenfabriek Dr. C.E. Bleeker’

Directory of Open Access Journals (Sweden)

Kees Ruitenbeek

2015-02-01

Full Text Available Bleeker’s Electrical Instruments Mrs. Dr. C.E. Bleeker (1897–1985 led a company in optical and electrical instruments since 1932. While her optical instruments – including Prof. Frits Zernike’s Nobel Prize-winning phase contrast microscope – are well known, she also made a name in electrical devices. In addition to a series of highly accurate resistors – normal resistors, precision resistors and resistor banks – a range of electrical instruments were developed, such as Wheatstone bridges and compensators. In 1963, Dr Bleeker retired, but her firm continued until 1978, when nearly all activities ceased. Only the interests in Bleeker’s range of resistors continued. The current manufacturer still refers to ‘Bleeker’s principle’ in rela- tion to the quality of the resistors.

Comparison of the parameters of the IR-8 reactor with different fuel assembly designs with LEU fuel

International Nuclear Information System (INIS)

Vatulin, A.; Stetsky, Y.; Dobrikova, I.

1999-01-01

The estimation of neutron-physical, heat and hydraulic parameters of the IR-8 research reactor with low enriched uranium (LEU) fuel was performed. Two fuel assembly (FA) designs were reviewed: IRT-4M with the tubular type fuel elements and IRT-MR with the rod type fuel elements. UO 2 -Al dispersion 19.75% enrichment fuel is used in both cases. The results of the calculations were compared with main parameters of the reactor, using the current IRT-3M FA with 90% high enriched uranium (HEU) fuel. The results of these comparisons showed that during the LEU conversion of the reactor the cycle length, excess reactivity and peak power of the IRT-MR type FA are higher than for the IRT-3M type FA and IRT-4M type FA. (author)

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...

Eugene P. Wigner’s Visionary Contributions to Generations-I through IV Fission Reactors

Directory of Open Access Journals (Sweden)

Carré Frank

2014-01-01

Full Text Available Among Europe’s greatest scientists who fled to Britain and America in the 1930s, Eugene P. Wigner made instrumental advances in reactor physics, reactor design and technology, and spent nuclear fuel processing for both purposes of developing atomic weapons during world-war II and nuclear power afterwards. Wigner who had training in chemical engineering and self-education in physics first gained recognition for his remarkable articles and books on applications of Group theory to Quantum mechanics, Solid state physics and other topics that opened new branches of Physics.

FIRST INTERFEROMETRIC IMAGES OF THE 36 GHz METHANOL MASERS IN THE DR21 COMPLEX

International Nuclear Information System (INIS)

Fish, Vincent L.; Muehlbrad, Talitha C.; Pratap, Preethi; Sjouwerman, Lorant O.; Strelnitski, Vladimir; Pihlstroem, Ylva M.; Bourke, Tyler L.

2011-01-01

Class I methanol masers are believed to be produced in the shock-excited environment around star-forming regions. Many authors have argued that the appearance of various subsets of class I masers may be indicative of specific evolutionary stages of star formation or excitation conditions. Until recently, however, no major interferometer was capable of imaging the important 36 GHz transition. We report on Expanded Very Large Array observations of the 36 GHz methanol masers and Submillimeter Array observations of the 229 GHz methanol masers in DR21(OH), DR21N, and DR21W. The distribution of 36 GHz masers in the outflow of DR21(OH) is similar to that of the other class I methanol transitions, with numerous multitransition spatial overlaps. At the site of the main continuum source in DR21(OH), class I masers at 36 and 229 GHz are found in virtual overlap with class II 6.7 GHz masers. To the south of the outflow, the 36 GHz masers are scattered over a large region but usually do not appear coincident with 44 GHz masers. In DR21W, we detect an 'S-curve' signature in Stokes V that implies a large value of the magnetic field strength if interpreted as due to Zeeman splitting, suggesting either that class I masers may exist at higher densities than previously believed or that the direct Zeeman interpretation of S-curve Stokes V profiles in class I masers may be incorrect. We find a diverse variety of different maser phenomena in these sources, suggestive of differing physical conditions among them.

Nuclear science. U.S. electricity needs and DOE's civilian reactor development program

International Nuclear Information System (INIS)

England-Joseph, Judy; Allen, Robert E. Jr.; Fitzgerald, Duane; Young, Edward E. Jr.; Leavens, William P.; Bell, Jacqueline

1990-05-01

Electricity projections developed by the North American Electric Reliability Council (NERC) appear to be the best available estimates of future U.S. electricity needs. NERC, which represents all segments of the utility industry, forecasts that before 1998 certain regions of the country, particularly in the more heavily populated eastern half of the United States, may experience shortfalls during summer peak demand periods. These forecasts considered the utility companies' plans, as of 1989, to meet electricity needs during the period; these plans include such measures as constructing additional generators and conducting demand management programs. Working closely with the nuclear industry, DOE is supporting the development of several reactor technologies to ensure that nuclear power remains a viable electricity supply option. In fiscal year 1990, DOE's Civilian Reactor Development Program was funded at $253 million. DOE is using these funds to support industry-led efforts to develop light water reactors (LWR), advanced liquid-metal reactors (LMR), and modular high-temperature gas-cooled reactors (MHTGR) that are safe, environmentally acceptable, and economically competitive. The utility company officials we spoke with, all of whom were in the Southeast, generally supported DOE's efforts in developing these technologies. However, most of the officials do not plan to purchase nuclear reactors until after 2000 because of the high costs of constructing nuclear reactors and current public opposition to nuclear power

Evolution and current status of demand response (DR) in electricity markets: Insights from PJM and NYISO

International Nuclear Information System (INIS)

Walawalkar, Rahul; Fernands, Stephen; Thakur, Netra; Chevva, Konda Reddy

2010-01-01

In electricity markets, traditional demand side management programs are slowly getting replaced with demand response (DR) programs. These programs have evolved since the early pilot programs launched in late 1990s. With the changes in market rules the opportunities have generally increased for DR for participating in emergency, economic and ancillary service programs. In recent times, various regulators have suggested that DR can also be used as a solution to meet supply - demand fluctuations in scenarios with significant penetration of variable renewable sources in grid. This paper provides an overview of the evolution of the DR programs in PJM and NYISO markets as well as analyzes current opportunities. Although DR participation has grown, most of the current participation is in the reliability programs, which are designed to provide load curtailment during peak days. This suggests that there is a significant gap between perception of ability of DR to mitigate variability of renewables and reality of current participation. DR in future can be scaled to play a more dynamic role in electricity markets, but that would require changes both on technology as well as policy front. Advances in building technologies and energy storage combined with appropriate price signals can lead to enhanced DR participation. (author)

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...

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 ...

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.

Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

International Nuclear Information System (INIS)

Bonin, H.W.; Hilborn, J.W.; Carlin, G.E.; Gagnon, R.; Busatta, P.

2014-01-01

Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as 99 Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as 99 Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO 2 SO 4 ) with 994.2 g of 235 U (enrichment at 20%) providing an excess reactivity at operating temperature (40 o C) of 3.8 mk for a molality determined as 1.46 mol kg -1 for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 o C. Peak temperature and power were determined as 83 o C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the temperature and void coefficients are

Homogeneous SLOWPOKE reactors for replacing SLOWPOKE-2 research reactors and the production of radioisotopes

Energy Technology Data Exchange (ETDEWEB)

Bonin, H.W., E-mail: bonin-h@rmc.ca [Royal Military College of Canada, Kingston, Ontario (Canada); Hilborn, J.W. [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada); Carlin, G.E. [Ontario Power Generation, Toronto, Ontario (Canada); Gagnon, R.; Busatta, P. [Canadian Forces (Canada)

2014-07-01

Inspired from the inherently safe SLOWPOKE-2 research reactor, the Homogeneous SLOWPOKE reactor was conceived with a double goal: replacing the heterogeneous SLOWPOKE-2 reactors when they reach end-of-core life to continue their missions of neutron activation analysis and neutron radiography at universities, and to produce radioisotopes such as {sup 99}Mo for medical applications. A homogeneous reactor core allows a much simpler extraction of radioisotopes (such as {sup 99}Mo) for applications in industry and nuclear medicine. The 20 kW Homogeneous SLOWPOKE reactor was modelled using both the deterministic WIMS-AECL and the probabilistic MCNP 5 reactor simulation codes. The homogeneous fuel mixture was a dilute aqueous solution of Uranyl Sulfate (UO{sub 2}SO{sub 4}) with 994.2 g of {sup 235}U (enrichment at 20%) providing an excess reactivity at operating temperature (40 {sup o}C) of 3.8 mk for a molality determined as 1.46 mol kg{sup -1} for a Zircaloy-2 reactor vessel. Because this reactor is intended to replace the core of SLOWPOKE-2 reactors, the Homogeneous SLOWPOKE reactor core had a height about twice its diameter. The reactor could be controlled by mechanical absorber rods in the beryllium reflector, chemical control in the core, or a combination of both. The safety of the Homogeneous SLOWPOKE reactor was analysed for both normal operation and transient conditions. Thermal-hydraulics calculations used COMSOL Multiphysics and the results showed that natural convection was sufficient to ensure adequate reactor cooling in all situations. The most severe transient simulated resulted from a 5.87 mk step positive reactivity insertion to the reactor in operation at critical and at steady state at 20 {sup o}C. Peak temperature and power were determined as 83 {sup o}C and 546 kW, respectively, reached 5.1 s after the reactivity insertion. However, the power fell rapidly to values below 20 kW some 35 s after the peak and remained below that value thereafter. Both the

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

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)

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

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.

76 FR 44964 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on U.S...

Science.gov (United States)

2011-07-27

... Subcommittee on U.S. Evolutionary Power Reactor; Notice of Meeting The ACRS Subcommittee on U.S. Evolutionary Power Reactor (U.S. EPR) will hold a meeting on August 18, 2011, Room T-2B3, 11545 Rockville Pike... the meeting, if possible, so that appropriate arrangements can be made. Thirty-five hard copies of...

Reference reactor module for NASA's lunar surface fission power system

Energy Technology Data Exchange (ETDEWEB)

Poston, David I [Los Alamos National Laboratory; Kapernick, Richard J [Los Alamos National Laboratory; Dixon, David D [Los Alamos National Laboratory; Werner, James [INL; Qualls, Louis [ORNL; Radel, Ross [SNL

2009-01-01

Surface fission power systems on the Moon and Mars may provide the first US application of fission reactor technology in space since 1965. The Affordable Fission Surface Power System (AFSPS) study was completed by NASA/DOE to determine the cost of a modest performance, low-technical risk surface power system. The AFSPS concept is now being further developed within the Fission Surface Power (FSP) Project, which is a near-term technology program to demonstrate system-level TRL-6 by 2013. This paper describes the reference FSP reactor module concept, which is designed to provide a net power of 40 kWe for 8 years on the lunar surface; note, the system has been designed with technologies that are fully compatible with a Martian surface application. The reactor concept uses stainless-steel based. UO{sub 2}-fueled, pumped-NaK fission reactor coupled to free-piston Stirling converters. The reactor shielding approach utilizes both in-situ and launched shielding to keep the dose to astronauts much lower than the natural background radiation on the lunar surface. The ultimate goal of this work is to provide a 'workhorse' power system that NASA can utilize in near-term and future Lunar and Martian mission architectures, with the eventual capability to evolve to very high power, low mass systems, for either surface, deep space, and/or orbital missions.

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,...

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 ...

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.

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 ...

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2002-04-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the 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 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

Study of the U3O8-Al thermite reaction and strength of reactor fuel tubes

International Nuclear Information System (INIS)

Peacock, H.B.

1984-01-01

Research and test reactors are presently operated with aluminum-clad fuel elements containing highly enriched uranium-aluminum alloy cores. To lower the enrichment and still maintain reactivity, the uranium content of the fuel element will need to be higher than currently achievable with alloy fuels. This will necessitate conversion to other forms such as U 3 O 8 -aluminum cermets. Above the aluminum melting point, U 3 O 8 and aluminum undergo an exothermic thermite reaction and cermet fuel cores tend to keep their original shape. Both factors could affect the course and consequences of a reactor accident, and therefore prompted an investigation of the behavior of cermet fuels at elevated temperatures. Tests were carried out using pellets and extruded tube sections with 53 wt % U 3 O 8 in aluminum. This content corresponds to a theoretical uranium density of 1.9 g/cc. Results indicate that the thermite reaction occurs at about 900 0 C in air without a violent effect. The heat of reaction was approximately 123 cal/g of U 3 O 8 -aluminum fuel. Tensile and compressive strength of the fuel tube section is low above 660 0 C. In tension, sections failed at about the aluminum melting point. In compression with 2 psi average axial stress, failure occurred at 917 0 C, while 7 psi average axial stress produced failure at 669 0 C. (author)

Study of the U3O8-Al thermite reaction and strength of reactor fuel tubes

International Nuclear Information System (INIS)

Peacock, H.B.

1983-01-01

Research and test reactors are presently operated with aluminum-clad fuel elements containing highly enriched uranium-aluminum alloy cores. To lower the enrichment and still maintain reactivity, the uranium content of the fuel element will need to be higher than currently achievable with alloy fuels. This will necessitate conversion to other forms such as U 3 O 8 -aluminum cermets. Above the aluminum melting point, U 3 O 8 and aluminum undergo an exothermic thermite reaction and cermet fuel cores tend to keep their original shape. Both factors could affect the course and consequences of a reactor accident, and prompted an investigation of the behavior of cermet fuels at elevated temperatures. Tests were carried out using pellets and extruded tube-sections with 53 wt % U 3 O 8 in aluminum. This content corresponds to a theoretical uranium density of 1.9 g/cc. Results indicate that the thermite reaction occurs at about 900 0 C in air without a violent effect. The heat of reaction was approximately 123 cal/g of U 3 O 8 -aluminum fuel. Tensile and compressive strength of the fuel tube section is low above 660 0 C. In tension, sections failed at about the aluminum melting point. In compression with 2-psi average axial stress, failure occurred at 917 0 C, while 7 psi average axial stress produced failure at 669 0 C

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

ASN’s actions in GEN IV reactors and Sodium Fast Reactors (SFR)

International Nuclear Information System (INIS)

Belot, Clotilde

2013-01-01

The ASN is involved in 3 actions concerning GEN IV: • Overview of nuclear reactor GEN IV systems; • Specific analysis about transmutation; • Prototype reactor ASTRID (SFR). Furthermore theses actions are in the beginning (no conclusions or results available)

Dual combination therapy targeting DR5 and EMMPRIN in pancreatic adenocarcinoma.

Science.gov (United States)

Kim, Hyunki; Zhai, Guihua; Samuel, Sharon L; Rigell, Christopher J; Umphrey, Heidi R; Rana, Samir; Stockard, Cecil R; Fineberg, Naomi S; Zinn, Kurt R

2012-02-01

The goal of the study was to assess the efficacy of combined extracellular matrix metalloprotease inducer (EMMPRIN)- and death receptor 5 (DR5)-targeted therapy for pancreatic adenocarcinoma in orthotopic mouse models with multimodal imaging. Cytotoxicity of anti-EMMPRIN antibody and anti-DR5 antibody (TRA-8) in MIA PaCa-2 and PANC-1 cell lines was measured by ATPlite assay in vitro. The distributions of Cy5.5-labeled TRA-8 and Cy3-labeled anti-EMMPRIN antibody in the 2 cell lines were analyzed by fluorescence imaging in vitro. Groups 1 to 12 of severe combined immunodeficient mice bearing orthotopic MIA PaCa-2 (groups 1-8) or PANC-1 (groups 9-12) tumors were used for in vivo studies. Dynamic contrast-enhanced-MRI was applied in group 1 (untreated) or group 2 (anti-EMMPRIN antibody). The tumor uptake of Tc-99m-labeled TRA-8 was measured in group 3 (untreated) and group 4 (anti-EMMPRIN antibody). Positron emission tomography/computed tomography imaging with (18)F-FDG was applied in groups 5 to 12. Groups 5 to 8 (or groups 9 to 12) were untreated or treated with anti-EMMPRIN antibody, TRA-8, and combination, respectively. TRA-8 showed high killing efficacy for both MIA PaCa-2 and PANC-1 cells in vitro, but additional anti-EMMPRIN treatment did not improve the cytotoxicity. Cy5.5-TRA-8 formed cellular caps in both the cell lines, whereas the maximum signal intensity was correlated with TRA-8 cytotoxicity. Anti-EMMPRIN therapy significantly enhanced the tumor delivery of the MR contrast agent, but not Tc-99m-TRA-8. Tumor growth was significantly suppressed by the combination therapy, and the additive effect of the combination was shown in both MIA PaCa-2 and PANC-1 tumor models.

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

Science.gov (United States)

2012-12-17

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

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 ...

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, ...

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, ...

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, ...

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: ...

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, ...

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 ...

Editing for performance: Dr Johnson and the stage Editing for performance: Dr Johnson and the stage

Directory of Open Access Journals (Sweden)

Peter Hollland

2008-04-01

Full Text Available I want to begin by quoting one of Dr Johnson’s notes on Hamlet, a passage that, though entirely characteristic, may be less than familiar to many. Johnson is commenting on the punctuation of a passage and is concerned about a sequence of dashes towards the end of the play: To a literary friend of mine I am indebted for the following very acute observation: “Throughout this play,” says he, “there is nothing more beautiful than these dashes; by their gradual elongation, they distinctly mark the balbuciation and the increasing difficulty of utterance observable in a dying man.” To which let me add, that, although dashes are in frequent use with our tragic poets, yet they are seldom introduced with so good an effect as in the present instance. (qtd. in Wells 1: 69 Johnson’s reliance on others—and their cloaked identity—is something we are used to. So too Johnson’s yearning here both to generalize about tragic practice and to praise the particular local effect in Shakespeare can be paralleled frequently elsewhere. I want to begin by quoting one of Dr Johnson’s notes on Hamlet, a passage that, though entirely characteristic, may be less than familiar to many. Johnson is commenting on the punctuation of a passage and is concerned about a sequence of dashes towards the end of the play: To a literary friend of mine I am indebted for the following very acute observation: “Throughout this play,” says he, “there is nothing more beautiful than these dashes; by their gradual elongation, they distinctly mark the balbuciation and the increasing difficulty of utterance observable in a dying man.” To which let me add, that, although dashes are in frequent use with our tragic poets, yet they are seldom introduced with so good an effect as in the present instance. (qtd. in Wells 1: 69 Johnson’s reliance on others—and their cloaked identity—is something we are used to. So too Johnson’s yearning here both to

Karakteristik Penderita Penyakit Jantung Bawaan pada Anak di RSUP Dr. M. Djamil Padang Periode Januari 2010 – Mei 2012

Directory of Open Access Journals (Sweden)

Nur Ain

2015-09-01

Full Text Available Abstrak Penyakit jantung bawaan (PJB merupakan defek lahir yang sering ditemukan dan merupakan penyebab kematian terbanyak dari semua jenis kelainan bawaan. Banyak penelitian yang menunjukkan bahwa adanya variasi secara geografik yang penting pada insiden PJB. Tujuan penelitian ini adalah untuk mengetahui variasi karakteristik dari penderita PJB anak di RSUP Dr. M. Djamil Padang. Jenis penelitian yang digunakan adalah penelitian deskriptif dengan melihat karakteristik penderita anak dengan PJB pada data rekam medik. Sampel penelitian ini adalah 55pasien anak yang menderita penyakit jantung bawaan di RSUP Dr. M. Djamil Padang dari Januari 2010 sampai Mei 2012. Mayoritas penderita adalah perempuan (61,8%, dan mayoritas umur sampel terdapat pada kelompok umur kurang dari 1 tahun (56.4%. Jenis PJB terbanyak adalah TF (21,8% dan gejala yang paling sering dijumpai adalah sesak nafas (50,9%. Sebanyak (34,5% penderita memiliki penyakit kongenital lain, dengan penyakit nonsindroma terbanyak adalah atresia ani dan omfalokel dengan masing-masing (22,2% dan penyakit sindroma terbanyak adalahsindroma Down (40%. Gagal tumbuh terdapat pada (49,1% penderita. Nilai Hb PJB sianotik lebih tinggi berbanding asianotik. Tingkat tindakan operatif kasus PJB anak di RSUP Dr. M. Djamil Padang adalah 1,8%. Terdapat variasi karakteristik dari penderita PJB yang ada di RSUP Dr. M. Djamil Padang.Kata kunci: penyakit jantung bawaan, anak, variasi karakteristik Abstract Congenital heart disease (CHD is a common birth defect, and a leading cause of deaths linked to birth defects. Many studies show that the presence of significant geographic variation in the incidence of CHD. The objective of this study was to determine the variation of the characteristics of patients with CHD in Dr. M. Djamil Hospital Padang. This research is a descriptive research by observing at the characteristics of children with CHD using the medical record data. The total sample of this study was 55

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...

Local bifurcation analysis in nuclear reactor dynamics by Sotomayor’s theorem

International Nuclear Information System (INIS)

Pirayesh, Behnam; Pazirandeh, Ali; Akbari, Monireh

2016-01-01

Highlights: • When the feedback reactivity is considered as a nonlinear function some complex behaviors may emerge in the system such as local bifurcation phenomenon. • The qualitative behaviors of a typical nuclear reactor near its equilibrium points have been studied analytically. • Comprehensive analytical bifurcation analyses presented in this paper are transcritical bifurcation, saddle- node bifurcation and pitchfork bifurcation. - Abstract: In this paper, a qualitative approach has been used to explore nuclear reactor behaviors with nonlinear feedback. First, a system of four dimensional ordinary differential equations governing the dynamics of a typical nuclear reactor is introduced. These four state variables are the relative power of the reactor, the relative concentration of delayed neutron precursors, the fuel temperature and the coolant temperature. Then, the qualitative behaviors of the dynamical system near its equilibria have been studied analytically by using local bifurcation theory and Sotomayor’s theorem. The results indicated that despite the uncertainty of the reactivity, we can analyze the qualitative behavior changes of the reactor from the bifurcation point of view. Notably, local bifurcations that were considered in this paper include transcritical bifurcation, saddle-node bifurcation and pitchfork bifurcation. The theoretical analysis showed that these three types of local bifurcations may occur in the four dimensional dynamical system. In addition, to confirm the analytical results the numerical simulations are given.

Floating nuclear heat. And power station 'Pevec' with KLT-40S type reactor plant for remote regions of Russia

International Nuclear Information System (INIS)

Veshnyakov, K.B.; Kiryushin, A.I.; Panov, Yu.K.; Polunichev, V.I.

2000-01-01

Floating small nuclear power plants power for local energy systems of littoral regions of Russia, located far from central energy system, open a new line in nuclear power development. Designing a floating power unit of a lead nuclear heat and power generating station for port Pevec at the Chuckchee national district is currently nearing completion. Most labor-intensive components are being manufactured. The co-generation NPP Pevec is to be created on the basis of a floating power unit with KLT-40S type reactor plant. KLT-40S reactor plant is based on similar propulsion plants, verified at operation of Russia's nuclear-powered civil ships, evolutionary improved by elimination of 'weak points' revealed during its prototypes operation or on the basis of safety analysis. KLT-40S reactor plant uses the most wide-spread and developed in the world practice PWR-type reactor. KLT-40S meets contemporary national and international requirements imposed to future reactor plants. The NHPS description, its main technical-economic data, environmental safety indices, basic characteristics of KLT-40S reactor plant are presented. Prospects of small NPPs utilization outside Russia, particularly as an energy source for sea water desalination, are considered. (author)

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.

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

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 ...

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 ...

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

A small research reactor for the 1980's

International Nuclear Information System (INIS)

Baglin, C.; Collis-Smith, J.A.; Mitchell, B.; Roskilly, T.

1978-01-01

In 1960, GEC together with Imperial College, designed and built the Consort reactor which is still in daily use at the London University Reactor Centre, Silwood Park. In 1977, GEC-REL chose the Consort reactor as a prototype for the development of a modern swimming pool research reactor, designed to meet the needs of countries or organisations starting in the field of Nuclear Technology. This paper outlines some of the topics which arose in the course of this project. (author)

U.S. Department of Energy operational experience with shipments of foreign research reactor spent nuclear fuel

International Nuclear Information System (INIS)

Messick, Charles E.; Massey, Charles D.; Mustin, Tracy P.

1998-01-01

On May 13, 1996, the U.S. Department of Energy issued a Record of Decision on a Nuclear Weapons Nonproliferation Policy Concerning Foreign Research Reactor Spent Nuclear Fuel. The goal of the long-term policy is to recover enriched uranium exported from the United States, while giving foreign research reactor operators sufficient time to develop their own long-term solutions for storage and disposal of spent fuel. The spent fuel accepted by the U.S. DOE under the policy must be out of the research reactors by May 12, 2006 and returned to the United States by May 12, 2009. (author)

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.

Kepler’s DR25 Most Earth-like Planet Candidates: What To Know Before You Go

Science.gov (United States)

Thompson, Susan E.; Kepler Team

2018-01-01

The Kepler mission’s latest catalog of planet candidates (data release 25 KOI catalog at the NASA exoplanet archive) was released in June of 2017. The catalog contains 4034 candidates including a significant population of terrestrial-size planets in the habitable zone of FGK dwarf stars. I will highlight what we know about these planet candidates in the DR25 catalog and discuss some of the caveats when working with these detections. Specifically, I will discuss how the noise in the Kepler light curves (from both the instrument and the stars) is known to occasionally produce weak, transit-like signals. We use simulations of this noise to measure how often these signals sneak into the catalog. I will also demonstrate ways to select a high-reliability sample using information available in the catalog. Such considerations may prove useful for anyone planning to use these planet candidates for occurrence rate calculations, choosing targets for follow-up, or deciding which planet to visit on his/her next holiday.

In-situ stripping of H{sub 2}S in gasoil hydrodesulphurization - reactor design considerations

Energy Technology Data Exchange (ETDEWEB)

Nava, J.A.O.; Krishna, R. [Amsterdam Univ., Dept. of Chemical Engineering, Amsterdam (Netherlands)

2004-02-01

In order to meet future diesel specifications the sulphur content of diesel would need to be reduced to below 50 ppm. This requirement would require improved reactor configurations. In this study we examine the benefits of counter-current contacting of gas oil with H{sub 2}, over conventional co-current contacting in a trickle bed hydrodesulphurization (HDS) reactor. In counter-current contacting, we achieve in-situ stripping of H{sub 2}S from the liquid phase; this is beneficial to the HDS kinetics. A comparison simulation study shows that counter-current contacting would require about 20% lower catalyst load than co-current contacting. However, counter-current contacting of gas and liquid phases in conventionally used HDS catalysts, of 1.5 mm sizes, is not possible due to flooding limitations. The catalysts need to be housed in special wire gauze envelopes as in the catalytic bales or KATAPAK-S configurations. A preliminary hardware design of a counter-current HDS reactor using catalytic bales was carried out in order to determine the technical feasibility. Using a realistic sulphur containing feedstock, the target of 50 ppm S content of desulphurized oil could be met in a reactor of reasonable dimensions. The study also underlines the need for accurate modelling of thermal effects during desulphurization. Our study also shows that interphase mass transfer is unlikely to be a limiting factor and there is a need to develop improved reactor configurations allowing for increased catalyst loading, at the expense of gas-liquid interfacial area. (Author)

The Xanthophyceae and Chlorophyceae of the Western Ross Sea, Victoria Land, Antarctica and Macquarie Island collected under the direction of Prof. Dr. J. S. Zaneveld (1963—1967)

NARCIS (Netherlands)

Wagner, H.P.; Zaneveld, J.S.

1988-01-01

During the austral summer seasons of 1963-1964 and 1964-1965, and during the austral winter season of 1967 Prof. Dr. J.S. Zaneveld made collection expeditions to the western Ross Sea. In 1965 collections were also made from the U.S.C.G. icebreaker ‘Glacier’, around the western Ross Sea and around

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)

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....

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.

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.

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)

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.

Predicted irradiation behavior of U3O8-Al dispersion fuels for production reactor applications

International Nuclear Information System (INIS)

Cronenberg, A.W.; Rest, J.

1990-01-01

Candidate fuels for the new heavy-water production reactor include uranium/aluminum alloy and U 3 O 8 -Al dispersion fuels. The U 3 O 8 -Al dispersion fuel would make possible higher uranium loadings and would facilitate uranium recycle. Research efforts on U 3 O 8 -Al fuel include in-pile irradiation studies and development of analytical tools to characterize the behavior of dispersion fuels at high-burnup. In this paper the irradiation performance of U 3 O 8 -Al is assessed using the mechanistic Dispersion Analysis Research Tool (DART) code. Predictions of fuel swelling and alteration of thermal conductivity are presented and compared with experimental data. Calculational results indicate good agreement with available data where the effects of as-fabricated porosity and U 3 O 8 -Al oxygen exchange reactions are shown to exert a controlling influence on irradiation behavior. The DART code is judged to be a useful tool for assessing U 3 O 8 -Al performance over a wide range of irradiation conditions

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 ...

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.

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, ...

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 ...

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

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.

The U.S. DOE new production reactor/heavy water reactor facility pollution prevention/waste minimization program

International Nuclear Information System (INIS)

Kaczmarsky, Myron M.; Tsang, Irving; Stepien, Walter P.

1992-01-01

A Pollution Prevention/Waste Minimization Program was established during the early design phase of the U.S. DOE's New Production Reactor/Heavy Water Reactor Facility (NPR/HWRF) to encompass design, construction, operation and decommissioning. The primary emphasis of the program was given to waste elimination, source reduction and/or recycling to minimize the quantity and toxicity of material before it enters the waste stream for treatment or disposal. The paper discusses the regulatory and programmatic background as it applies to the NPR/HWRF and the waste assessment program developed as a phased approach to pollution prevention/waste minimization for the NPR/HWRF. Implementation of the program will be based on various factors including life cycle cost analysis, which will include costs associated with personnel, record keeping, transportation, pollution control equipment, treatment, storage, disposal, liability, compliance and oversight. (author)

Fissile fuel production and usage of thermal reactor waste fueled with UO2 by means of hybrid reactor system

International Nuclear Information System (INIS)

Ipek, O.

1997-01-01

The use of Fast Breeder Reactors to produce fissile fuel from nuclear waste and the operation of these reactors with a new neutron source are becoming today' topic. In the thermonuclear reactors, it is possible to use 2.45-14.1 MeV - neutrons which can be obtained by D-T, D-D Semicatalyzed (D-D) and other fusion reactions. To be able to do these, Hybrid Reactor System, which still has experimental and theoretical studies, have to be taken into consideration.In this study, neutronic analysis of hybrid blanket with grafit reflector, is performed. D-T driven fusion reaction is surrounded by UO 2 fuel layer and the production of ''2''3''9Pu fissile fuel from waste ''2''3''8U is analyzed. It is also compared to the other possible fusion reactions. The results show that 815.8 kg/year ''2''3''8Pu with D-T reaction and 1431.6 kg/year ''2''3''8Pu with semicatalyzed (D-D) reaction can be produced for 1000 MW fusion power. This means production of 2.8/ year and 4.94/ year LWR respectively. In addition, 1000 MW fusion flower is is multiplicated to 3415 MW and 4274 MW for D-T and semicatalyzed (D-D) reactions respectively. The system works subcritical and these values are 0.4115 and 0.312 in order. The calculations, ANISN-ORNL code, S 16 -P 3 approach and DLC36 data library are used

Prony's method application for BWR instabilities characterization

Energy Technology Data Exchange (ETDEWEB)

Castillo, Rogelio, E-mail: rogelio.castillo@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Ramírez, J. Ramón, E-mail: ramon.ramirez@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Alonso, Gustavo, E-mail: gustavo.alonso@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico); Instituto Politecnico Nacional, Unidad Profesional Adolfo Lopez Mateos, Ed. 9, Lindavista, D.F. 07300 (Mexico); Ortiz-Villafuerte, Javier, E-mail: javier.ortiz@inin.gob.mx [Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca s/n, La Marquesa, Ocoyoacac, Estado de México 52750 (Mexico)

2015-04-01

Highlights: • Prony's method application for BWR instability events. • Several BWR instability benchmark are assessed using this method. • DR and frequency are obtained and a new parameter is proposed to eliminate false signals. • Adequate characterization of in-phase and out-of-phase events is obtained. • The Prony's method application is validated. - Abstract: Several methods have been developed for the analysis of reactor power signals during BWR power oscillations. Among them is the Prony's method, its application provides the DR and the frequency of oscillations. In this paper another characteristic of the method is proposed to determine the type of oscillations that can occur, in-phase or out-of-phase. Prony's method decomposes a given signal in all the frequencies that it contains, therefore the DR of the fundamental mode and the first harmonic are obtained. To determine the more dominant pole of the system a normalized amplitude W of the system is calculated, which depends on the amplitude and the damping coefficient. With this term, it can be analyzed which type of oscillations is present, if W of the fundamental mode frequency is the greater, the type of oscillations is in-phase, if W of the first harmonic frequency is the greater, the type of oscillations is out-of-phase. The method is applied to several stability benchmarks to assess its validity. Results show the applicability of the method as an alternative analysis method to determine the type of oscillations occurred.

Prony's method application for BWR instabilities characterization

International Nuclear Information System (INIS)

Castillo, Rogelio; Ramírez, J. Ramón; Alonso, Gustavo; Ortiz-Villafuerte, Javier

2015-01-01

Highlights: • Prony's method application for BWR instability events. • Several BWR instability benchmark are assessed using this method. • DR and frequency are obtained and a new parameter is proposed to eliminate false signals. • Adequate characterization of in-phase and out-of-phase events is obtained. • The Prony's method application is validated. - Abstract: Several methods have been developed for the analysis of reactor power signals during BWR power oscillations. Among them is the Prony's method, its application provides the DR and the frequency of oscillations. In this paper another characteristic of the method is proposed to determine the type of oscillations that can occur, in-phase or out-of-phase. Prony's method decomposes a given signal in all the frequencies that it contains, therefore the DR of the fundamental mode and the first harmonic are obtained. To determine the more dominant pole of the system a normalized amplitude W of the system is calculated, which depends on the amplitude and the damping coefficient. With this term, it can be analyzed which type of oscillations is present, if W of the fundamental mode frequency is the greater, the type of oscillations is in-phase, if W of the first harmonic frequency is the greater, the type of oscillations is out-of-phase. The method is applied to several stability benchmarks to assess its validity. Results show the applicability of the method as an alternative analysis method to determine the type of oscillations occurred

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

International Nuclear Information System (INIS)

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

1990-01-01

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

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...

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...

IAEA activities in the field of research reactors safety

International Nuclear Information System (INIS)

Ciuculescu, C.; Boado Magan, H.J.

2004-01-01

IAEA activities in the field of research reactor safety are included in the programme of the Division of Nuclear Installations Safety. Following the objectives of the Division, the results of the IAEA missions and the recommendations from International Advisory Groups, the IAEA has conducted in recent years a certain number of activities aiming to enhance the safety of research reactors. The following activities will be presented: (a) the new Requirements for the Safety of Research Reactors, main features and differences with previous standards (SS-35-S1 and SS-35-S2) and the grading approach for implementation; (b) new documents being developed (safety guides, safety reports and TECDOC's); (c) activities related to the Incident Reporting System for Research Reactor (IRSRR); (d) the new features implemented for the INSARR missions; (e) the Code of Conduct on the Safety of Research Reactors adopted by the Board of Governors on 8 March 2004, following the General Conference Resolution GC(45)/RES/10; and (f) the survey on the safety of research reactors published on the IAEA website on February 2003 and the results obtained. (author)

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 ...

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

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

Dr Michaels® product family (also branded as Soratinex®) versus Methylprednisolone aceponate - a comparative study of the effectiveness for the treatment of plaque psoriasis.

Science.gov (United States)

Hercogovấ, J; Fioranelli, M; Gianfaldoni, S; Chokoeva, A A; Tchernev, G; Wollina, U; Tirant, M; Novotny, F; Roccia, M G; Maximov, G K; França, K; Lotti, T

2016-01-01

As one of the most common dermatologic chronic-recurrent disease, variable therapeutic options are available today for management of psoriasis. Although topical high potency corticosteroids, alone or in association with salicylic acid or vitamin D analogues, are still considered the best treatment, they do not seem to possess the capability for a long-term control of the disease or prevent recurrences, as their side effects are major contraindications for continuative use. The aim of this study was to investigate whether Dr. Michaels® product family is comparable to methylprednisolone aceponate (MPA) as a viable alternative treatment option for the treatment and management of stable chronic plaque psoriasis. Thirty adults (13 male, 17 female, mean age 40 years) with mild to severe stable chronic plaque psoriasis, were included in the study. Patients were advised to treat the lesions of the two sides of their body (left and right) with two different unknown modalities for 8 weeks; the pack of Dr. Michaels® products on the left side (consisting of a cleansing gel, an ointment and a skin conditioner) and a placebo pack on the right side, consisting of a cleansing gel, methylprednisolone ointment and a placebo conditioner. Assessment was done using the Psoriasis Activity Severity Index (PASI) scores before treatment and after 2, 4, 6 and 8 weeks. The results achieved with the Dr. Michaels® (Soratinex®) product family for the treatment of chronic plaque psoriasis were better than the results achieved with methylprednisolone aceponate (MPA), even though quicker resolution was achieved with the steroid with 45% of patients achieving resolution within 8-10 days in comparison to 5-6 weeks in the Dr. Michaels® (Soratinex®) group. Before therapy, the mean PASI score of the LHS in Dr. Michaels® (Soratinex®) group was 13.8±4.1 SD and 14.2±4.2 SD in the RHS methylprednisolone aceponate (MPA) group. After 8 weeks of treatment 62% of the Dr. Michaels® (Soratinex

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

International Nuclear Information System (INIS)

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

1970-08-01

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

THE ZEEMAN EFFECT IN THE 44 GHZ CLASS I METHANOL MASER LINE TOWARD DR21(OH)

Energy Technology Data Exchange (ETDEWEB)

Momjian, E. [National Radio Astronomy Observatory, P.O. Box O, Socorro, NM 87801 (United States); Sarma, A. P., E-mail: emomjian@nrao.edu, E-mail: asarma@depaul.edu [Physics Department, DePaul University, 2219 N. Kenmore Avenue, Byrne Hall 211, Chicago, IL 60614 (United States)

2017-01-10

We report detection of the Zeeman effect in the 44 GHz Class I methanol maser line, toward the star-forming region DR21(OH). In a 219 Jy beam{sup −1} maser centered at an LSR velocity of 0.83 km s{sup −1}, we find a 20- σ detection of zB {sub los} = 53.5 ± 2.7 Hz. If 44 GHz methanol masers are excited at n ∼ 10{sup 7–8} cm{sup −3}, then the B versus n {sup 1/2} relation would imply, from comparison with Zeeman effect detections in the CN(1 − 0) line toward DR21(OH), that magnetic fields traced by 44 GHz methanol masers in DR21(OH) should be ∼10 mG. Combined with our detected zB {sub los} = 53.5 Hz, this would imply that the value of the 44 GHz methanol Zeeman splitting factor z is ∼5 Hz mG{sup −1}. Such small values of z would not be a surprise, as the methanol molecule is non-paramagnetic, like H{sub 2}O. Empirical attempts to determine z , as demonstrated, are important because there currently are no laboratory measurements or theoretically calculated values of z for the 44 GHz CH{sub 3}OH transition. Data from observations of a larger number of sources are needed to make such empirical determinations robust.

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.

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).

The regulation on commercial reactors and the management of high-level radioactive wastes in U.S

International Nuclear Information System (INIS)

Shimomura, Hidetsugu

2013-01-01

This article shows U.S. NRC's substantial and procedural regulations regarding commercial reactors and radioactive wastes. The commercial reactor's regulations are analyzed from an ensuring safety, and the radioactive waste' management is done from a locating a disposal site. (author)

According to German Finance Minister Dr. Theodor Karl Helfferich “The Causes of of The First World War”

Directory of Open Access Journals (Sweden)

Mustafa ÇOLAK

2015-12-01

Full Text Available In history mankind has experienced the most devastating experience during the years of the First World War. This pre-war and war in the later stages of a decision taken individually, even thousands, even millions of lives have been directly or indirectly affected. Experiencing the process and outcome of the war rather than the causes of human history has so much more busy. Therefore, the cause of the war which works popularity continues even today. Concerning the reasons for the war period, written by the German Finance Minister Dr. Helfferich especially in England, including working with its allies in the war of public opinion in the state has led to many discussions concerning the reasons. Dr. Helfferich’s “The Beginning of Great War”; “German’s Case in The Supreme Court of Civilization”; was published under the title of The New York Times by the Fatherland company in 1915. Dr. Karl Helfferich’s study has been translated in different languages in following period. Keywords: Dr. Theodor Karl Helfferich, The First World War, Reşid Safvet Atabinen, Ottoman Empire, Germany.

Site Investigation for Detection of KIJANG Reactor Core Center

Energy Technology Data Exchange (ETDEWEB)

Kwon, Tae-Hyun; Kim, Jun Yeon; Kim, Jeeyoung [KAERI, Daejeon (Korea, Republic of)

2015-05-15

It was planned for the end of March 2017 and extended to April 2018 according to the government budget adjustment. The KJRR project is intended for filling the self-sufficiency of RI demand including Mo-99, increasing the NTD capacity and developing technologies related to the research reactor. In project, site investigation is the first activity that defines seismologic and related geologic aspects of the site. Site investigation was carried out from Oct. 2012 to Jan. 2014 and this study is intended to describe detail procedures in locating the reactor core center. The location of the reactor core center was determined by collectively reviewing not only geological information but also information from architects engineering. EL 50m was selected as ground level by levering construction cost. Four recommended locations (R-1a - R-1d) are displayed for the reactor core center. R-1a was found optimal in consideration of medium rock contour, portion of medium rock covering reactor buildings, construction cost, physical protection and electrical resistivity. It is noted that engineering properties of the medium rock is TCR/RQD 100/53, elastic modulus 7,710 - 8,720MPa, permeability coefficient 2.92E-06cm/s, and S-wave velocity 1,380m/s, sound for foundations of reactor buildings.

Management of the radioactive waste resulting from the Romanian VVR-S research reactor decommissioning

International Nuclear Information System (INIS)

Ene, D.; Cepraga, D.G.

2002-01-01

The paper consists in a waste study of the Romanian VVR-S reactor which will be prepared for decommissioning operations after the permanent shutdown (23.12.1997). Calculations were carried out to determine the activity arising from neutron activation of structural materials inside the reactor, considering the design of the facility and its operating rules. To this end, the following method was used: i) Neutron flux distribution within the reactor was calculated using the DORT transport code, based on DLC23 shielding library relating to three cylindrical reference systems of the reactor structure: reactor core, horizontal tube and thermal column; ii) Calculation of the activity of each reactor component at different cooling times was performed by the ANITA2000 code, using the neutron flux, compositional data for each material and the power history of the reactor; iii) Unconditional clearance indexes for all material at various cooling times were calculated using the clearance levels defined in IAEA-TECDOC-855; iv) Total activities and masses by material type, within the waste category and for each decay time were calculated by summation of the data previously classified for each reactor component. The resulting activation inventory and waste masses, falling in IAEA defined waste categories are presented in the paper at periods of 100 days, and 6, 10, 25, and 50 years after reactor the shutdown. For some components of the reactor as: aluminum central vessel, the central iron shielding ring, the time behaviour of both the fin spatial activity distribution and the radionuclide contributions to the total activity are plotted in the paper. (author)

Integral Inherently Safe Light Water Reactor (I2S-LWR)

International Nuclear Information System (INIS)

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

2017-01-01

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

The CEA research reactors

International Nuclear Information System (INIS)

Schwartz, J.P.

1993-01-01

Two main research reactors, specifically designed, PEGASE reactor and Laue-Langevin high flux reactor, are presented. The PEGASE reactor was designed at the end of the 50s for the study of the gas cooled reactor fuel element behaviour under irradiation; the HFR reactor, was designed in the late 60s to serve as a high yield and high level neutron source. Historical backgrounds, core and fuel characteristics and design, flux characteristics, etc., are presented. 5 figs

Obstetric patients admitted to the intensive care unit of Dr George ...

African Journals Online (AJOL)

require ICU level of care. S Afr J Crit Care 2017;33(1):12-14. ... at Dr George Mukhari Academic Hospital (DGMAH), Ga-Rankuwa,. SA. DGMAH is a ... day. The median length of ICU stay was 24 hours (range 1 - 17 days). Eighty-seven percent ...

U.S. Department of Energy Program of International Technical Cooperation for Research Reactor Utilization

International Nuclear Information System (INIS)

Chong, D.; Manning, M.; Ellis, R.; Apt, K.; Flaim, S.; Sylvester, K.

2004-01-01

The U.S. Department of Energy, National Nuclear Security Administration (DOE/NNSA) has initiated collaborations with the national nuclear authorities of Egypt, Peru, and Romania for the purpose of advancing the commercial potential and utilization of their respective research reactors. Under its Office of International Safeguards ''Sister Laboratory'' program, DOE/NNSA has undertaken numerous technical collaborations over the past decade intended to promote peaceful applications of nuclear technology. Among these has been technical assistance in research reactor applications, such as neutron activation analysis, nuclear analysis, reactor physics, and medical radioisotope production. The current collaborations are intended to provide the subject countries with a methodology for greater commercialization of research reactor products and services. Our primary goal is the transfer of knowledge, both in administrative and technical issues, needed for the establishment of an effective business plan and utilization strategy for the continued operation of the countries' research reactors. Technical consultation, cooperation, and the information transfer provided are related to: identification, evaluation, and assessment of current research reactor capabilities for products and services; identification of opportunities for technical upgrades for new or expanded products and services; advice and consultation on research reactor upgrades and technical modifications; characterization of markets for reactor products and services; identification of competition and estimation of potential for market penetration; integration of technical constraints; estimation of cash flow streams; and case studies

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…

The Waste Management Plan integration into Decommissioning Plan of the WWR-S research reactor from Romania

International Nuclear Information System (INIS)

Barariu, Gheorghe; Oprescu, Theodor; Filip, Mihaela; Sociu, Florin

2008-01-01

The paper presents the progress of the Radioactive Waste Management Plan which accompanies the Decommissioning Plan for research reactor WWR-S located in Magurele, Ilfov, near Bucharest, Romania. The new variant of the Decommissioning Plan was elaborated taking into account the IAEA recommendation concerning radioactive waste management. A new feasibility study for WWR-S decommissioning was also developed. The preferred safe management strategy for radioactive wastes produced by reactor decommissioning is outlined. The strategy must account for reactor decommissioning, as well as rehabilitation of the existing Radioactive Waste Treatment Plant and the upgrade of the Radioactive Waste Disposal Facility at Baita-Bihor. Furthermore, the final rehabilitation of the laboratories and reusing of cleaned reactor building is envisaged. An inventory of each type of radioactive waste is presented. The proposed waste management strategy is selected in accordance with the IAEA assistance. Environmental concerns are part of the radioactive waste management strategy. (authors)

Data-to-Decisions S&T Priority Initiative

Science.gov (United States)

2011-11-08

Decisions S&T Priority Initiative Dr. Carey Schwartz PSC Lead Office of Naval Research NDIA Disruptive Technologies Conference November 8-9, 2011...DISTRIBUTION/AVAILABILITY STATEMENT Approved for public release; distribution unlimited 13. SUPPLEMENTARY NOTES Presented at the NDIA Disruptive ... Technologies Conference, November 8,-9, 2011,Washington, DC 14. ABSTRACT 15. SUBJECT TERMS 16. SECURITY CLASSIFICATION OF: 17. LIMITATION OF ABSTRACT

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.

Children’s Psychiatric Hospital Dr. Juan N. Navarro: 50 years of attention to the mental health of children and adolescents in Mexico

OpenAIRE

María Elena Márquez-Caraveo; Eduardo Arroyo-García; Armida Granados-Rojas; Angélica Ángeles-Llerenas

2017-01-01

The activities concerning mental health care of psychiatric disorders during more than 50 years of service (1966-2016) at the Children’s Psychiatric Hospital “Dr. Juan N. Navarro”(HPI), as well as the progressive development of teaching and research, have contributed to its positioning as a leading institution in medical care of high specialization. This has been possible through the training of human resources that focus the quality of care to the children and their families. The hospital ha...

Computational modeling and experimental studies on NO{sub x} reduction under pulverized coal combustion conditions. Third quarterly technical progress report, July 1, 1995--September 30, 1995

Energy Technology Data Exchange (ETDEWEB)

Kumpaty, S.K.; Subramanian, K.

1995-12-31

An experimental plan outlining the first year`s activity was sent to Dr. Lori Gould, Project Officer/Contracting Officer`s Technical Representative on April 24, 1995. An approval was received with some questions on June 15, 1995. However, with some foresight of the director of the in-house combustion group of the PETC, Dr. Ekmann, a tentative hold-off on the purchase of the equipment was requested by the project officer on June 29, 1995. Enclosed with that request were some of Dr. Ekmann`s concerns. The research team spent the month of July in study of pertinent literature as well as in the preparation of the responses to Dr. Gould`s comments and Dr. Ekmann`s concerns. These responses included the choice of the reactor, reactor design, rate of gas heating, detailed test matrix and answers to host of other comments. Upon review of the above information submitted on July 24, 1995 by the Rust research team, the project officer called for a conference call on September 6, 1995 which involved the PI (Dr. Kumpaty), the research consultant (Mr. Subramanian), Dr. Gould and Dr. Ekmann. Dr. Ekmann insisted that further calculations be made on the rate of gas heating without taking radiation into account. Accordingly, calculations pertaining to the rate of gas heating based on convection were performed and submitted to Dr. Ekmann on September 13, 1995. This report contains the information emerged through the dialogue between the Rust College research team and the PETC represented by Dr. Gould and Dr. Ekmann during this quarter.

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.

ORAC-DR: A generic data reduction pipeline infrastructure

Science.gov (United States)

Jenness, Tim; Economou, Frossie

2015-03-01

ORAC-DR is a general purpose data reduction pipeline system designed to be instrument and observatory agnostic. The pipeline works with instruments as varied as infrared integral field units, imaging arrays and spectrographs, and sub-millimeter heterodyne arrays and continuum cameras. This paper describes the architecture of the pipeline system and the implementation of the core infrastructure. We finish by discussing the lessons learned since the initial deployment of the pipeline system in the late 1990s.

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

Energy Technology Data Exchange (ETDEWEB)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-15

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

V.S.O.P. (99/09) computer code system for reactor physics and fuel cycle simulation. Version 2009

International Nuclear Information System (INIS)

Ruetten, H.J.; Haas, K.A.; Brockmann, H.; Ohlig, U.; Pohl, C.; Scherer, W.

2010-07-01

V.S.O.P. (99/ 09) represents the further development of V.S.O.P. (99/ 05). Compared to its precursor, the code system has been improved again in many details. The main motivation for this new code version was to update the basic nuclear libraries used by the code system. Thus, all cross section libraries involved in the code have now been based on ENDF/B-VII. V.S.O.P. is a computer code system for the comprehensive numerical simulation of the physics of thermal reactors. It implies the setup of the reactor and of the fuel element, processing of cross sections, neutron spectrum evaluation, neutron diffusion calculation in two or three dimensions, fuel burnup, fuel shuffling, reactor control, thermal hydraulics and fuel cycle costs. The thermal hydraulics part (steady state and time-dependent) is restricted to gas-cooled reactors and to two spatial dimensions. The code can simulate the reactor operation from the initial core towards the equilibrium core. This latest code version was developed and tested under the WINDOWS-XP - operating system. (orig.)

Passive Decay Heat Removal System Options for S-CO2 Cooled Micro Modular Reactor

International Nuclear Information System (INIS)

Moon, Jangsik; Jeong, Yong Hoon; Lee, Jeong Ik

2014-01-01

To achieve modularization of whole reactor system, Micro Modular Reactor (MMR) which has been being developed in KAIST took S-CO 2 Brayton power cycle. The S-CO 2 power cycle is suitable for SMR due to high cycle efficiency, simple layout, small turbine and small heat exchanger. These characteristics of S-CO 2 power cycle enable modular reactor system and make reduced system size. The reduced size and modular system motived MMR to have mobility by large trailer. Due to minimized on-site construction by modular system, MMR can be deployed in any electricity demand, even in isolated area. To achieve the objective, fully passive safety systems of MMR were designed to have high reliability when any offsite power is unavailable. In this research, the basic concept about MMR and Passive Decay Heat Removal (PDHR) system options for MMR are presented. LOCA, LOFA, LOHS and SBO are considered as DBAs of MMR. To cope with the DBAs, passive decay heat removal system is designed. Water cooled PDHR system shows simple layout, but has CCF with reactor systems and cannot cover all DBAs. On the other hand, air cooled PDHR system with two-phase closed thermosyphon shows high reliability due to minimized CCF and is able to cope with all DBAs. Therefore, the PDHR system of MMR will follows the air-cooled PDHR system and the air cooled system will be explored

U.S. activities related to fast reactors and ADS

International Nuclear Information System (INIS)

Finck, Phillip J.

2001-01-01

The U.S. nuclear power industry achieved its second straight year of record power generation levels during 2000. Total power generated was 753.9 billion kWh, 3.5 percent above the previous record of 728.1 billion kWh set in 1999. Recent years of reliable service and declining production costs have led to increased industry interest in nuclear power plant license renewal. The Nuclear Regulatory Commission approved the license renewal applications for five U.S. nuclear power plants in 2000. Five additional applications were received and 28 more are planned to be submitted by 2004. Concerns over energy resource availability, climate change, air quality, and energy security suggest an important role for nuclear power in future energy supplies. While the current Generation II and III nuclear power plant designs provide an economically, technically, and publicly acceptable electricity supply in many markets, further advances in nuclear energy system design can broaden the opportunities for the use of nuclear energy. To explore these opportunities, the U. S. Department of Energy's Office of Nuclear Energy, Science and Technology has engaged governments, industry, and the research community worldwide in a wide-ranging discussion on the development of next-generation nuclear energy systems known as 'Generation IV'. The I-NERI program has the following objectives: Develop advanced concepts and scientific breakthroughs in nuclear fission and reactor technology to address and overcome the principal technical and scientific obstacles to the expanded use of nuclear energy worldwide; Promote bilateral and multilateral collaboration with international agencies and research organizations to improve development of nuclear energy; and Promote and maintain nuclear science and engineering infrastructure to meet future technical challenges. I-NERI will sponsor innovative research and development in the following areas: Next-generation nuclear energy plant designs with higher efficiency

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 ...

The Hopf fibration over S8 admits no S1-subfibration

International Nuclear Information System (INIS)

Loo, B.; Verjovsky, A.

1990-10-01

It is shown that there does not exist a PL-bundle over S 8 with fibre and total space PL-manifolds homotopy equivalent to CP 3 and CP 7 respectively. Consequently, the Hopf fibration over S 8 admits no subfibration by PL-circles. (author). 27 refs

The Hopf fibration over S8 admits no S1-subfibration

International Nuclear Information System (INIS)

Loo, B.; Verjovsky, A.

1990-05-01

It is shown that there does not exist a PL-bundle over S 8 with fibre and total space PL-manifolds homotopy equivalent to CP 3 and CP 7 respectively. Consequently, the Hopf fibration over S 8 admits no subfibration by PL-circles. (author). 27 refs

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, ...

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, ...

Safety evaluation report by the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission for U.S. Energy Research and Development Administration Light Water Breeder Reactor. Special project No. 561

International Nuclear Information System (INIS)

1976-07-01

The Safety Evaluation Report is presented for the Light Water Breeder Reactor (LWBR). The LWBR core is to be installed in the Shippingport reactor at the Shippingport Atomic Power Station. The Safety Evaluation Report is the result of an NRC staff review of the LWBR Safety Analysis Report submitted by the Division of Naval Reactors, U. S. Energy Research and Development Administration. As a result of its review, the NRC staff has recommended that: (1) a diverse trip signal, such as containment high pressure, be included in a 2-out-of-3 logic for initiation of safety injection; (2) power be locked out from the pressurizer surge isolation valve during normal operation; and (3) a chlorine monitor be installed in the main control room

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)

Dr. House: Patología dual en el médico

Directory of Open Access Journals (Sweden)

Mariano A. BELLINA

2016-09-01

Full Text Available Dr. House es una serie dramática estadounidense cuyo personaje central es el Dr. Gregory House, médi? co que dirige una unidad de diagnóstico (con otros tres doctores en el Hospital Universitario Princeton? Plainsboro, en Nueva Jersey. Dr. House utiliza un proceso lógico especial como base para llegar al diagnóstico. La Unidad que dirige el Dr. House trata pacientes que han sido evaluados previamente por otros doctores sin haber alcanzado un diagnóstico. Los diagnósticos oscilan desde algunos muy comunes a enfermedades raras. House no respeta las reglas y procedimientos comunes en la Medicina tradicional, tiene conflictos interpersonales graves (así como falta de empatía y no muestra interés por otras prácticas clínicas que no sean las suyas. Sufre un dolor crónico intenso en la pierna derecha por el que comienza a prescribirse Vicodin® (hidrocodona, al que acaba haciéndose dependiente. Nuestra hipótesis es que House es un caso típico de patología dual, PD (coexistencia de trastorno por uso de sustancias y otra enfermedad mental, en concreto: de dependencia de opiáceos y trastorno mixto de personalidad (comparte rasgos del trastorno de la personalidad antisocial y narcisista. La PD no es infrecuente en médicos dada la demora en pedir ayuda y la fácil accesibilidad a algunas sustancias.

An other-typological illustration of the Exodus story according to Dr King’s perception of universal reconciliation in his sermon on Exodus 14:30

Directory of Open Access Journals (Sweden)

Sunggu Yang

2016-11-01

Full Text Available The article contends that Dr King makes an other-typological illustrative use of the Exodus story in his preaching – one of the most significant biblical narratives that the Black church in the US holds dear. This peculiar use of the Exodus story differentiates itself from the conventional typological understanding and use of the same story in the Black church’s history. While in the latter the Exodus story has a symbolic meaning of the irreconcilable conflict between the oppressed and the oppressing reality, in the former the same story contains a spiritual lesson that what is really hoped for in the midst of the seemingly irreconcilable racial and social conflict is compassion, liberation, and reconciliation for both parties involved. This article, by examining a representative sermon of Dr King on the Exodus story, shows that his other-typological illustrative approach originates from his fundamental theological ideal of universal reconciliation.

Fabrication of zero power reactor fuel elements containing 233U3O8 powder

International Nuclear Information System (INIS)

Nicol, R.G.; Parrott, J.R.; Krichinsky, A.M.; Box, W.D.; Martin, C.W.; Whitson, W.R.

1982-05-01

Oak Ridge National Laboratory, under contract with Argonne National Laboratory, completed the fabrication of 1743 fuel elements for use in their Zero Power Reactor. The contract also included recovery of 20 kg of 233 U from rejected elements. This report describes the steps associated with conversion of purified uranyl nitrate (as solution) to U 3 O 8 powder (suitable for fuel) and subsequent charging, sealing, decontamination, and testing of the fuel elements (packets) preparatory to shipment. The nuclear safety, radiation exposures, and quality assurance aspects of the program are discussed

International Fusion Energy Act of 1993. Hearing before the Committee on Energy and Natural Resources, United States Senate, One Hundred Third Congress, First Session on S. 646, May 6, 1993

International Nuclear Information System (INIS)

Anon.

1993-01-01

The text of the bill, International Fusion Energy Act of 1993, is included along with statements from the following: B. Bradley, Senator, NJ; Dr. J. Decker, DOE Office of Energy Research; J. Gavin; Dr. R. Hirsch, Electric Power Research Institute; B. Johnston, Senator, LA; Dr. D. Overskei, General Atomics; Dr. P. Rebut, International Thermonuclear Experimental Reactor; M. Wallop, Senator, WY

The pro-apoptotic effects of TIPE2 on AA rat fibroblast-like synoviocytes via regulation of the DR5–caspase–NF-κB pathway in vitro

Directory of Open Access Journals (Sweden)

Shi C

2016-02-01

Full Text Available Chunyan Shi,1,2,* Shifeng Zhang,1,3,* Shifu Hong,1 Jinglong Pang,1 Yeletai Yesibulati,1 Ping Yin,4 Guohong Zhuang1 1Organ Transplantation Institute, Anti-Cancer Research Center, Medical College, Xiamen University, Xiamen, Fujian, 2The Department of Oncology, Jiujiang No.1 People’s Hospital, Jiujiang, Jiangxi City, 3Division of Gastroenterology Surgery, Zhongshan Hospital, Gastroenterology Institute of Xiamen University, Gastroenterology Center of Xiamen, 4The Department of Pathology, Zhongshan Hospital, Xiamen University, Xiamen, Fujian, People’s Republic of China *These authors contributed equally to this work Abstract: TIPE2, also known as TNFAIP8L2, a member of the tumor necrosis factor- alpha-induced protein-8 (TNFAIP8 family, is known as an inhibitor in inflammation and cancer, and its overexpression induces cell death. We examined the role of TIPE2 with respect to adjuvant arthritis (AA-associated pathogenesis by analyzing the TIPE2 regulation of death receptor (DR5-mediated apoptosis in vitro. The results showed that TIPE2 was detected in normal fibroblast-like synoviocytes (FLSs, but scarcely observed in AA-FLSs. Therefore, recombinant MIGR1/TIPE2+/+ and control MIGR1 lentivirus vectors were transfected to AA-FLSs, which were denoted as TIPE2+/+-FLSs and MIGR1-FLSs, respectively. Our results showed that TIPE2+/+-FLSs were highly susceptible to ZF1-mediated apoptosis, and ZF1 was our own purification of an anti-DR5 single chain variable fragment antibody. Under the presence of TIPE2, the expression of DR5 was significantly increased compared with that of the MIGR1-FLS group. In contrast, the level of phosphorylated nuclear factor-kappa B (pNF-κB was lower in the TIPE2+/+-FLS group treated with ZF1, whereas the activity of caspase was higher. Moreover, the rate of apoptosis in the TIPE2+/+-FLS group, which was pretreated with caspase inhibitor Z-VAD-FMK, was significantly decreased. In contrast, the apoptosis occurrence in the MIGR1

Improving U.S.-India HA/DR Coordination in the Indian Ocean

Science.gov (United States)

2014-07-01

Indian Navy’s amphibious ships—INS Gharial, INS Mahish, INS Cheetah , and INS Kumbhir—shipped rice and other relief materials to Chittagong. Of the four...ships, INS Cheetah arrived first, on December 8, with 250 tons of rice. The tank-landing ship INS Gharial transported 4,000 tons of rice to

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 ...

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 ...

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 ...

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:

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

Computation of nuclear reactor parameters using a stretch Kalman filtering

International Nuclear Information System (INIS)

Zwingelstein, G.; Poujol, A.

1976-01-01

A method of nonlinear stochastic filtering, the stretched Karman filter, is used for the estimation of two basic parameters involved in the control of nuclear reactor start-up. The corresponding algorithm is stored in a small Multi-8 computer and tested with data recorded for the Ulysse reactor (I.N.S.T.N.). The various practical problems involved in using the algorithm are examined: filtering initialization, influence of the model... The quality and time saving obtained in the computation make it possible for a real time operation, the computer being connected with the reactor [fr

Nuclear cycle of thorium and molt salts reactors. PE 5.8

International Nuclear Information System (INIS)

Doubre, H.

2004-01-01

In the framework of the nuclear industry development, many scenario are studied from the standard reactors using enriched uranium to the IV generation reactors. The study of new systems for the future of the nuclear needs to develop new simulation tools. The research programs of the IPN of Orsay are presented. (A.L.B.)

Transactions of the 8th International Conference on Structure Mechanics in Reactor Technology

International Nuclear Information System (INIS)

Browzin, B.S.

1985-06-01

These Transactions of the JK-panel session include preprints of papers or abstracts which are listed in Volume A, ''Introduction, General Contents, Authors Index,'' Proceedings of the 8th International Conference on Structural Mechanics in Reactor Technology. These papers represent the body of the JK-panel session, ''Status of Research in Structural and Mechanical Engineering for Nuclear Power Plants,'' sponsored by the US Nuclear Regulatory Commission. Additional papers are expected at this session, which will be available at the session. The purpose of publishing these Transactions is to inform the participants of the JK-panel session in advance on the papers to be presented and discussed at the session

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

U.S. Research Program to Support Advanced Reactors and Fuel Cycle Options

International Nuclear Information System (INIS)

Lyons, Peter

2013-01-01

• In recognition of possible future needs, the U.S. will perform R&D on advanced reactor and fuel cycle technologies that could dramatically improve nuclear energy safety and performance; • Multifaceted approach to support R&D: - National labs; - Universities; - Industry; - International partners

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, ...

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.

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 ...

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:

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, ...

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

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

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

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 ...

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, ...

Neutronic feasibility studies using U-Mo dispersion fuel (9 Wt % Mo, 5.0 gU/cm3) for LEU conversion of the MARIA (Poland), IR-8 (Russia), and WWR-SM (Uzbekistan) research reactors

International Nuclear Information System (INIS)

Bretscher, M.M.; Deen, J.R.; Hanan, N.A.; Matos, E.

2000-01-01

U-Mo alloys dispersed in an Al matrix offer the potential for high-density uranium fuels needed for the LEU conversion of many research reactors. On-going fuel qualification tests by the US RERTR Program show good irradiation properties of U-Mo alloy dispersion fuel containing 7-10 weight percent molybdenum. For the neutronic studies in this paper the alloy was assumed to contain 9 wt % Mo (U-9Mo) with a uranium density in the fuel meat of 5.00 gU/cm 3 which corresponds to 32.5 volume % U-9Mo. Fuels containing U-9Mo have been used in Russian reactors since the 1950's. For the three research reactors analyzed here, LEU fuel element thicknesses are the same as those for the Russian-fabricated HEU reference fuel elements. Relative to the reference fuels containing 80-90% enriched uranium, LEU U-9Mo Al-dispersion fuel with 5.00 gU/cm 3 doubles the cycle length of the MARIA reactor and increases the IR-8 cycle length by about 11%. For the WWR-SM reactor, the cycle length, and thus the number of fuel assemblies used per year, is nearly unchanged. To match the cycle length of the 36% enriched fuel currently used in the WWR-SM reactor will require a uranium density in the LEU U-9Mo Al-dispersion fuel of about 5.4 gU/cm 3 . The 5.00 gU/cm 3 LEU fuel causes thermal neutron fluxes in water holes near the edge of the core to decrease by (6-8)% for all three reactors. (author)

V.S.O.P.-computer code system for reactor physics and fuel cycle simulation

International Nuclear Information System (INIS)

Teuchert, E.; Hansen, U.; Haas, K.A.

1980-03-01

V.S.O.P. (Very Superior Old Programs) is a system of codes linked together for the simulation of reactor life histories. It comprises neutron cross section libraries and processing routines, repeated neutron spectrum evaluation, 2-D diffusion calculation based on neutron flux synthesis with depletion and shutdown features, incore and out-of-pile fuel management, fuel cycle cost analysis, and thermal hydraulics (at present restricted to Pebble Bed HTRs). Various techniques have been employed to accelerate the iterative processes and to optimize the internal data transfer. A limitation of the storage requirement to 360 K-bites is achieved by an overlay structure. The code system has been used extensively for comparison studies of reactors, their fuel cycles, and related detailed features. Beside its use in research and development work for the high temperature reactor the system has been applied successfully to LWR and Heavy Water Reactors. (orig.) [de

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.

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.

Reactor coolant pump seal issues and their applicability to new reactor designs

International Nuclear Information System (INIS)

Ruger, C.J.; Higgins, J.C.

1993-01-01

Reactor Coolant Pumps (RCPs) of various types are used to circulate the primary coolant through the reactor in most reactor designs. RCPs generally contain mechanical seals to limit the leakage of pressurized reactor coolant along the pump drive shaft into the containment. The relatively large number of RCP seal and seal auxiliary system failures experienced at U.S. operating plants during the 1970's and early 1980's raised concerns from the U.S. Nuclear Regulatory Commission (NRC) that gross failures may lead to reactor core uncovery and subsequent core damage. Some seal failure events resulted in a loss of primary coolant to the containment at flow rates greater than the normal makeup capacity of Pressurized Water Reactor (PWR) plants. This is an example of RCP seal failures resulting in a small Loss of Coolant Accident (LOCA). This paper discusses observed and potential causes of RCP seal failure and the recommendations for limiting the likelihood of a seal induced small LOCA. Issues arising out of the research supporting these recommendations and subsequent public comments by the utility industry on them, serve as lessons learned, which are applicable to the design of new reactor plants

Nuclear non-proliferation: the U.S. obligation to accept spent fuel from foreign research reactors

International Nuclear Information System (INIS)

Shapar, Howard K.; Egan, Joseph R.

1995-01-01

The U.S. Department of Energy (DOE) had a 35-year program for the sale and receipt (for reprocessing) of high-enriched research reactor fuel for foreign research reactors, executed pursuant to bilateral agreements with nuclear trading partners. In 1988, DOE abruptly let this program lapse, citing environmental obstacles. DOE promised to renew the program upon completion of an environmental review which was to take approximately six months. After three and a half years, an environmental assessment was finally produced.Over a year and half elapsed since publication of the assessment before DOE finally took action to renew the program. The paper sets forth the nuclear non-proliferation and related foreign policy considerations which support renewal of the program. It also summarized the contractual and other commitments made to foreign research reactors and foreign governments and aspects of U.S. environmental law as they apply to continuation of the program. (author)

Finanční analýza podniku Drůbežářský závod Klatovy a.s.

OpenAIRE

Kohoutová, Kateřina

2010-01-01

This bachelor thesis deals with the financial analysis of Drůbežářský závod Klatovy a.s. during the period 2005-2009. The goal of the thesis is to evaluate the economic situation of the corporation and find out its competitive strength. A part of the project is the methodology which qualifies concepts and indicators and creates bases for the practical part. In the practical part of the project horizontal and vertical analysis of balance sheet and profit and loss statement with comments are pe...

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 ...

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, ...

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 ...

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 ...

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

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

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 ...

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, ...

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, ...

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

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.

Terrestrial Energy bets on molten salt reactors

International Nuclear Information System (INIS)

Anon.

2015-01-01

Terrestrial Energy is a Canadian enterprise, founded in 2013, for marketing the integral molten salt reactor (IMSR). A first prototype (called MSRE and with an energy output of 8 MW) was designed and operated between 1965 and 1969 by the Oak Ridge National Laboratory. IMSR is a small, modular reactor with a thermal energy output of 400 MW. According to Terrestrial Energy the technology of conventional power reactors is too complicated and too expensive. On the contrary IMSR's technology appears to be simple, easy to operate and affordable. With a staff of 30 people Terrestrial Energy appears to be a start-up in the nuclear sector. A process of pre-licensing will be launched in 2016 with the Canadian nuclear safety authority. (A.C.)

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.

Dr. Shi Hanzhang's Experience in Treating Andropathy

Institute of Scientific and Technical Information of China (English)

无

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.

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.)

Grantee Spotlight: Dr. Meena Jaggi - Investigating Curcumin (Turmeric) as HPV Repressor for Native A

Science.gov (United States)

Dr. Meena Jaggi’s research, funded by an NCI/CRCHD U01 grant, involves the use of curcumin (commonly known as turmeric) to inhibit human papillomavirus (HPV) infection among Native American (NA) women.

Calibration of RB reactor power

International Nuclear Information System (INIS)

Sotic, O.; Markovic, H.; Ninkovic, M.; Strugar, P.; Dimitrijevic, Z.; Takac, S.; Stefanovic, D.; Kocic, A.; Vranic, S.

1976-09-01

The first and only calibration of RB reactor power was done in 1962, and the obtained calibration ratio was used irrespective of the lattice pitch and core configuration. Since the RB reactor is being prepared for operation at higher power levels it was indispensable to reexamine the calibration ratio, estimate its dependence on the lattice pitch, critical level of heavy water and thickness of the side reflector. It was necessary to verify the reliability of control and dosimetry instruments, and establish neutron and gamma dose dependence on reactor power. Two series of experiments were done in June 1976. First series was devoted to tests of control and dosimetry instrumentation and measurements of radiation in the RB reactor building dependent on reactor power. Second series covered measurement of thermal and epithermal neuron fluxes in the reactor core and calculation of reactor power. Four different reactor cores were chosen for these experiments. Reactor pitches were 8, 8√2, and 16 cm with 40, 52 and 82 fuel channels containing 2% enriched fuel. Obtained results and analysis of these results are presented in this document with conclusions related to reactor safe operation

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. ...

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.

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

Biological perchlorate reduction in packed bed reactors using elemental sulfur.

Science.gov (United States)

Sahu, Ashish K; Conneely, Teresa; Nüsslein, Klaus R; Ergas, Sarina J

2009-06-15

Sulfur-utilizing perchlorate (ClO4-)-reducing bacteria were enriched from a denitrifying wastewater seed with elemental sulfur (S0) as an electron donor. The enrichment was composed of a diverse microbial community, with the majority identified as members of the phylum Proteobacteria. Cultures were inoculated into bench-scale packed bed reactors (PBR) with S0 and crushed oyster shell packing media. High ClO4-concentrations (5-8 mg/L) were reduced to PBR performance decreased when effluent recirculation was applied or when smaller S0 particle sizes were used, indicating that mass transfer of ClO4- to the attached biofilm was not the limiting mechanism in this process, and that biofilm acclimation and growth were key factors in overall reactor performance. The presence of nitrate (6.5 mg N/L) inhibited ClO4- reduction. The microbial community composition was found to change with ClO4- availability from a majority of Beta-Proteobacteria near the influent end of the reactor to primarily sulfur-oxidizing bacteria near the effluent end of the reactor.

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 ...

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 ...

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

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:

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, ...

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2001-04-01

The Reactor Physics and MYRRHA 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 of reactor fuel. This expertise is applied in the 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 by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

GAMBARAN KEPUASAN PASIEN KANKER STADIUM LANJUT TERHADAP PERAWATAN PALIATIF DI RSUP DR. SARDJITO YOGYAKARTA

Directory of Open Access Journals (Sweden)

Dwi Susanti

2017-09-01

Full Text Available Background: Patient satisfaction in palliative care is an important dimension that can describe a patient’s experience acceptable of care. Patient satisfaction is used to evaluate performance and improve the quality of palliative care. Objective: This study aimed to know the description of patient satisfaction of palliative cancer against palliative care which has been given in IRNA I RSUP Dr.Sardjito Yogyakarta based on a ranking that includes 5 subscales of satisfaction in palliative care. Method: Type of research was mixed methods with sequential explanatory design, collecting data began from collecting quantitative data and followed by collecting qualitative data. Subject of study involved cancer patient in Central Hospital of Dr. Sardjito Yogyakarta during September and October 2016 number of respondent was 48 patients and 8 participants. Sampling technique in quantitative research used purposive sampling, while the qualitative research used the techniques sampling criterion. Instrument used FAMCARE-P to measure satisfaction and the interview based on interview guideline. Quantitative data analysis used descriptive analysis and analysis of qualitative data used the content analysis. Integration of the results of quantitative research and qualitative used the joint displays. Results: Cancer patients have a high satisfaction on the subscale of support in decision-making with a mean Conclusion: Cancer patient satisfaction on palliative care was high with score on every subscales above mean score.

Application of direct passive residual heat removal system to the SMART reactor

International Nuclear Information System (INIS)

Kim, Yeon-Sik; Bae, Sung-Won; Cho, Seok; Kang, Kyoung-Ho; Park, Hyun-Sik

2016-01-01

Highlights: • An applicability study of the DRHRS to the SMART reactor was conducted. • Evaluations were performed for a station blackout scenario. • The adoption of the DRHRS in the SMART reactor was found feasible. - Abstract: A feasibility study on the application of the DRHRS to the SMART reactor was performed, using the MARS code. As a limiting event for the evaluation, an SBO event was used. From the MARS analysis on the DRHRS evaluation, most of the thermal hydraulic behaviors showed reasonable trends in pressure, temperature, and water levels. During the simulation, it was found out that mass transfer takes place between regions in the reactor vessel, especially from 2500 s to 11,000 s. Most of the mass transfer occurred from the outer regions in the reactor vessel, e.g., RV-outer1 and RV-outer2 regions, to the RV-inner region. The cooling flowrate in the CHX of the DRHRS was maintained between 7 and 8 kg/s for the simulation time. From this feasibility study, it can be concluded that the adoption of the DRHRS to the SMART reactor is reasonable at least from the view point of an SBO event.

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.

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

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.

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, ...

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 ...

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:

Dr. Stefan Ambs: Increasing Diversity in Cancer Research: One Lab at a Time

Science.gov (United States)

As part of the series “Increasing Diversity in Cancer Research,” CRCHD interviewed Dr. Stefan Ambs, an investigator at NCI’s Center for Cancer Research, who is using novel approaches to discover gene differences in the tumors of African American patients.

Project requirements for reconstruction of the RA reactor ventilation system, Task 2.8. Measurement of radioactive iodine and other isotopes contents in the gas system of the RA reactor, Annex of the task

International Nuclear Information System (INIS)

Vujisic, Lj. et al

1981-01-01

This report is a supplement to the task 2.8. When planning and constructing the ventilation system, it was found that it is necessary to perform additional experiments during RA reactor operation at 2 MW power level for a longer period. In addition to the helium system, the potential source of radioactive pollutants is the space below the upper water shielding of the reactor. All the experimental and fuel channels are ending in this space. During repair and fuel exchange radioactivity can be released in this space. For that reason this space is important when planing and designing the filtration system for incidental conditions or planned dehermetisation of the reactor. The third point where radioactive isotope identification was done, was the entrance into the chimney during steady state operation and planned dehermetisation of the reactor. The following samples were measured: gas system during reactor operation at 2 MW power; entrance into the chimney during last 48 hours of reactor operation at 2 MW power; sample on the platform under the upper water shield with the opened fuel channel after the reactor shutdown; and simultaneously with the latter, measurement at the entrance to the chimney. This annex contains the list of identified radioactive isotopes, volatile and gaseous as well as concentration of volatile 131 I on the adsorbents [sr

Aspects of 17th century Binding Medium: inclusions in Rembrandt’s Anatomy Lesson of Dr Nicolaes Tulp

DEFF Research Database (Denmark)

Noble, Petria; Wadum, Jørgen; Groen, Karin

2000-01-01

During the recent restoration of Rembrandt's Anatomy Lesson of Dr. Nicolaes Tulp minuscule crater-like holes, which cover the surface of the painting, were studied. Whitish material within the holes was identified as lead chloride hydroxide and a variety of lead soaps. These inclusions, which...

Licensed operating reactors. Status summary report, data as of 8-31-82

International Nuclear Information System (INIS)

1982-09-01

The US Nuclear Regulatory Commission's monthly LICENSED OPERATING REACTORS Status Summary Report provides data on the operation of nuclear units as timely and accurately as possible. This report is divided into three sections: the first contains monthly highlights and statistics for commercial operating units, and errata from previously reported data; the second is a compilation of detailed information on each unit, provided by NRC Regional Offices, IE Headquarters and the Utilities; and the third section is an appendix for miscellaneous information such as spent fuel storage capability, reactor years of experience and non-power reactors in the United States

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.

The corpus-driven revolution in Polish Sign Language: the interview with Dr. Paweł Rutkowski

Directory of Open Access Journals (Sweden)

Iztok Kosem

2018-02-01

Full Text Available Dr. Paweł Rutkowski is head of the Section for Sign Linguistics at the University of Warsaw. He is a general linguist and a specialist in the field of syntax of natural languages, carrying out research on Polish Sign Language (polski język migowy — PJM. He has been awarded a number of prizes, grants and scholarships by such institutions as the Foundation for Polish Science, Polish Ministry of Science and Higher Education, National Science Centre, Poland, Polish–U.S. Fulbright Commission, Kosciuszko Foundation and DAAD. Dr. Rutkowski leads the team developing the Corpus of Polish Sign Language and the Corpus-based Dictionary of Polish Sign Language, the first dictionary of this language prepared in compliance with modern lexicographical standards. The dictionary is an open-access publication, available freely at the following address: http://www.slownikpjm.uw.edu.pl/en/. This interview took place at eLex 2017, a biennial conference on electronic lexicography, where Dr. Rutkowski was awarded the Adam Kilgarriff Prize and gave a keynote address entitled Sign language as a challenge to electronic lexicography: The Corpus-based Dictionary of Polish Sign Language and beyond. The interview was conducted by Dr. Victoria Nyst from Leiden University, Faculty of Humanities, and Dr. Iztok Kosem from the University of Ljubljana, Faculty of Arts.

[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.

Analysis of gamma dose for 4,8 gU/cm3 density silicide core at the RSG-GAS reactor using MCNP code

International Nuclear Information System (INIS)

Ardani

2011-01-01

Radiation safety analysis should be done following of substitution of fuel density of 2.96 gU/cc to density of 4,8 gU/cc silicide fuels for the RSG-GAS reactor. MCNP-5 code has been used to perform gamma dose calculation of the RSG-GAS reactor. Gamma radiation source at reactor consists of capture gamma rays, prompt fission gamma rays, and gamma rays of decay of fission and activation products. The strength of the prompt fission gamma rays is obtained by gamma releases of fission process of U-235 and reactor power of 30 MWt., during 46,6 days operation. Radiation dose is calculated at the experimental hall by detection point at the surface of outer of biological shielding and the operation hall by detection point at the top of the pool. The calculation is conducted at reactor on the normal operation and on the worst postulated accident causing the water level at the pool decreases. Calculation result shows that the biggest source strength of gamma rays come from the decay process. The highest calculated dose at the experiment hall is 4,07x10 -3 μSv/h, far from the maximum external dose permitted 25 μSv/h. The highest calculated dose at the operation hall is 19.98 μSv/h. Even though the calculated dose is still acceptable but this is close to the maximum permitted dose for worker. It concluded that loading of 4,8 gU/cc silicide fuel for the RSG-GAS still safe. (author)

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

International Nuclear Information System (INIS)

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

2007-01-01

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

Computational and Experimental Investigations of the Coolant Flow in the Cassette Fissile Core of a KLT-40S Reactor

Science.gov (United States)

Dmitriev, S. M.; Varentsov, A. V.; Dobrov, A. A.; Doronkov, D. V.; Pronin, A. N.; Sorokin, V. D.; Khrobostov, A. E.

2017-07-01

Results of experimental investigations of the local hydrodynamic and mass-exchange characteristics of a coolant flowing through the cells in the characteristic zones of a fuel assembly of a KLT-40S reactor plant downstream of a plate-type spacer grid by the method of diffusion of a gas tracer in the coolant flow with measurement of its velocity by a five-channel pneumometric probe are presented. An analysis of the concentration distribution of the tracer in the coolant flow downstream of a plate-type spacer grid in the fuel assembly of the KLT-40S reactor plant and its velocity field made it possible to obtain a detailed pattern of this flow and to determine its main mechanisms and features. Results of measurement of the hydraulic-resistance coefficient of a plate-type spacer grid depending on the Reynolds number are presented. On the basis of the experimental data obtained, recommendations for improvement of the method of calculating the flow rate of a coolant in the cells of the fissile core of a KLT-40S reactor were developed. The results of investigations of the local hydrodynamic and mass-exchange characteristics of the coolant flow in the fuel assembly of the KLT-40S reactor plant were accepted for estimating the thermal and technical reliability of the fissile cores of KLT-40S reactors and were included in the database for verification of computational hydrodynamics programs (CFD codes).

Assessment of torsatrons as reactors

International Nuclear Information System (INIS)

Lyon, J.F.; Painter, S.L.

1992-12-01

Stellarators have significant operational advantages over tokamaks as ignited steady-state reactors because stellarators have no dangerous disruptions and no need for continuous current drive or power recirculated to the plasma, both easing the first wall, blanket, and shield design; less severe constraints on the plasma parameters and profiles; and better access for maintenance. This study shows that a reactor based on the torsatron configuration (a stellarator variant) could also have up to double the mass utilization efficiency (MUE) and a significantly lower cost of electricity (COE) than a conventional tokamak reactor (ARIES-I) for a range of assumptions. Torsatron reactors can have much smaller coil systems than tokamak reactors because the coils are closer to the plasma and they have a smaller cross section (higher average current density because of the lower magnetic field). The reactor optimization approach and the costing and component models are those used in the current stage of the ARIES-I tokamak reactor study. Typical reactor parameters for a 1-GW(e) Compact Torsatron reactor example are major radius R 0 = 6.6-8.8 m, on-axis magnetic field B 0 = 4.8-7.5 T, B max (on coils) = 16 T, MUE 140-210 kW(e)/tonne, and COE (in constant 1990 dollars) = 67-79 mill/kW(e)h. The results are relatively sensitive to assumptions on the level of confinement improvement and the blanket thickness under the inboard half of the helical windings but relatively insensitive to other assumptions

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.

A high intensity positron beam at the Brookhaven reactor

International Nuclear Information System (INIS)

Weber, M.; Lynn, K.G.; Roellig, L.O.; Mills, A.P. Jr.; Moodenbaugh, A.R.

1987-01-01

We describe a high intensity, low energy positron beam utilizing high specific activity /sup 64/Cu sources (870 Ci/g) produced in a reactor with high thermal neutron flux. Fast-to-slow moderation can be performed in a self moderation mode or with a transmission moderator. Slow positron rates up to 1.6 x 10/sup 8/ e/sup +//s with a half life of 12.8 h are calculated. Up to 1.0 x 10/sup 8/ e/sup +//s have been observed. New developments including a Ne moderator and an on-line isotope separation process are discussed. 21 refs., 9 figs