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

Energy Technology Data Exchange (ETDEWEB)

1993-05-01

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

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.

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

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)

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

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

Directory of Open Access Journals (Sweden)

Visentainer J.E.L.

1997-01-01

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

DR2DI: a powerful computational tool for predicting novel drug-disease associations

Science.gov (United States)

Lu, Lu; Yu, Hua

2018-05-01

Finding the new related candidate diseases for known drugs provides an effective method for fast-speed and low-risk drug development. However, experimental identification of drug-disease associations is expensive and time-consuming. This motivates the need for developing in silico computational methods that can infer true drug-disease pairs with high confidence. In this study, we presented a novel and powerful computational tool, DR2DI, for accurately uncovering the potential associations between drugs and diseases using high-dimensional and heterogeneous omics data as information sources. Based on a unified and extended similarity kernel framework, DR2DI inferred the unknown relationships between drugs and diseases using Regularized Kernel Classifier. Importantly, DR2DI employed a semi-supervised and global learning algorithm which can be applied to uncover the diseases (drugs) associated with known and novel drugs (diseases). In silico global validation experiments showed that DR2DI significantly outperforms recent two approaches for predicting drug-disease associations. Detailed case studies further demonstrated that the therapeutic indications and side effects of drugs predicted by DR2DI could be validated by existing database records and literature, suggesting that DR2DI can be served as a useful bioinformatic tool for identifying the potential drug-disease associations and guiding drug repositioning. Our software and comparison codes are freely available at https://github.com/huayu1111/DR2DI.

DR2DI: a powerful computational tool for predicting novel drug-disease associations

Science.gov (United States)

Lu, Lu; Yu, Hua

2018-04-01

Finding the new related candidate diseases for known drugs provides an effective method for fast-speed and low-risk drug development. However, experimental identification of drug-disease associations is expensive and time-consuming. This motivates the need for developing in silico computational methods that can infer true drug-disease pairs with high confidence. In this study, we presented a novel and powerful computational tool, DR2DI, for accurately uncovering the potential associations between drugs and diseases using high-dimensional and heterogeneous omics data as information sources. Based on a unified and extended similarity kernel framework, DR2DI inferred the unknown relationships between drugs and diseases using Regularized Kernel Classifier. Importantly, DR2DI employed a semi-supervised and global learning algorithm which can be applied to uncover the diseases (drugs) associated with known and novel drugs (diseases). In silico global validation experiments showed that DR2DI significantly outperforms recent two approaches for predicting drug-disease associations. Detailed case studies further demonstrated that the therapeutic indications and side effects of drugs predicted by DR2DI could be validated by existing database records and literature, suggesting that DR2DI can be served as a useful bioinformatic tool for identifying the potential drug-disease associations and guiding drug repositioning. Our software and comparison codes are freely available at https://github.com/huayu1111/DR2DI.

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)

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.)

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...

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

Science.gov (United States)

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

2018-06-01

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

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.

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

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-05-01

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

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)

Data of evolutionary structure change: 1DR0A-2DHTB [Confc[Archive

Lifescience Database Archive (English)

Full Text Available 1DR0A-2DHTB 1DR0 2DHT A B ------------------------MKVAVLPGDGIGPEV...tryChain> 2DHT B 2DHT...95 HIS CA 348 VAL CA 450 VAL CA 478 2DHT... B 2DHTB YAIEHKRKKVT GLY CA 354 GLU CA 281 PHE CA 323 2DHT

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

Data of evolutionary structure change: 1DR8A-2DHTB [Confc[Archive

Lifescience Database Archive (English)

Full Text Available 1DR8A-2DHTB 1DR8 2DHT A B ------------------------MKVAVLPGDGIGPEV...Chain> 2DHT B 2DHT...50 VAL CA 456 VAL CA 489 SER CA 527 2DHT... B 2DHTB AIEHKRKKVTI GLY CA 352 GLU CA 281 PHE CA 327

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

Science.gov (United States)

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

2014-03-01

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

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

International Nuclear Information System (INIS)

Rodovsky, T. J.

1999-01-01

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

Decommissioning of DR 2. Experiences learnt from the completion

International Nuclear Information System (INIS)

Strufe, N.

2009-10-01

The report describes experiences gathered from the decommissioning of DR 2. The experiences encompasses planning and management of the project, methods of accomplishment, and various materials categories. Additionally, the report describes the experience with specific tools used in the project

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

Science.gov (United States)

Gaia Collaboration

2018-04-01

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

Reactor BR2

Energy Technology Data Exchange (ETDEWEB)

Gubel, P

2000-07-01

The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported.

Reactor BR2

International Nuclear Information System (INIS)

Gubel, P.

2000-01-01

The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. Various aspects concerning the operation of the BR2 Reactor, the utilisation of the CALLISTO loop and the irradiation programme, the BR2 R and D programme and the production of isotopes and of NTD-silicon are discussed. Progress and achievements in 1999 are reported

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

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

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

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

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.

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

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

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)

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

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)

Using DR52c/Ni2+ mimotope tetramers to detect Ni2+ reactive CD4+ T cells in patients with joint replacement failure.

Science.gov (United States)

Zhang, Yan; Wang, Yang; Anderson, Kirsten; Novikov, Andrey; Liu, Zikou; Pacheco, Karin; Dai, Shaodong

2017-09-15

T cell mediated hypersensitivity to nickel (Ni 2+ ) is one of the most common causes of allergic contact dermatitis. Ni 2+ sensitization may also contribute to the failure of Ni 2+ containing joint implants, and revision to non-Ni 2+ containing hardware can be costly and debilitating. Previously, we identified Ni 2+ mimotope peptides, which are reactive to a CD4 + T cell clone, ANi2.3 (Vα1, Vβ17), isolated from a Ni 2+ hypersensitive patient with contact dermatitis. This T cell is restricted to the major histocompatibility complex class II (MHCII) molecule, Human Leukocyte Antigen (HLA)-DR52c (DRA, DRB3*0301). However, it is not known if Ni 2+ induced T cell responses in sensitized joint replacement failure patients are similar to subjects with Ni 2+ induced contact dermatitis. Here, we generated DR52c/Ni 2+ mimotope tetramers, and used them to test if the same Ni 2+ T cell activation mechanism could be generalized to Ni 2+ sensitized patients with associated joint implant failure. We confirmed the specificity of these tetramers by staining of ANi2.3T cell transfectomas. The DR52c/Ni 2+ mimotope tetramer detected Ni 2+ reactive CD4 + T cells in the peripheral blood mononuclear cells (PBMC) of patients identified as Ni 2+ sensitized by patch testing and a positive Ni 2+ LPT. When HLA-typed by a DR52 specific antibody, three out of four patients were DR52 positive. In one patient, Ni 2+ stimulation induced the expansion of Vβ17 positive CD4 + T cells from 0.8% to 13.3%. We found that the percentage of DR52 positivity and Vβ17 usage in Ni 2+ sensitized joint failure patients are similar to Ni sensitized skin allergy patients. Ni 2+ independent mimotope tetramers may be a useful tool to identify the Ni 2+ reactive CD4 + T cells. Copyright © 2017 Elsevier Inc. All rights reserved.

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

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)

PARR-2: reactor description and experiments

International Nuclear Information System (INIS)

Wyne, M.F.; Meghji, J.H.

1990-12-01

PARR-2 is a miniature neutron source reactor (MNSR) research reactor has been designed at the rate of 27 kW. Reactor assembly comprises of peaking characteristics with a self limiting flux. In this report reactor description with its assembly and instrumentation control system has been explained. The reactor engineering and physics experiments which can be performed on this reactor are explained in this report. PARR-2 is fueled with HEU fuel pins which are about 90% enriched in U-235. Specific requirements for the safety of the reactor, its building and the personnel, normal instrumentation as required in an industrial environment is sufficient. (A.B.)

Reactor BR2: Introduction

International Nuclear Information System (INIS)

Gubel, P.

2000-01-01

The BR2 reactor is still SCK-CEN's most important nuclear facility. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. A safety audit was conduced by the IAEA, the conclusions of which demonstrated the excellent performance of the plant in terms of operational safety. In 1999, the CALLISTO facility was extensively used for various programmes involving LWR pressure vessel materials, IASCC of LWR structural materials, fusion reactor materials and martensic steels for use in ADS systems. In 1999, BR2's commercial programmes were further developed

Material test reactor fuel research at the BR2 reactor

Energy Technology Data Exchange (ETDEWEB)

Dyck, Steven Van; Koonen, Edgar; Berghe, Sven van den [Institute for Nuclear Materials Science, SCK-CEN, Boeretang, Mol (Belgium)

2012-03-15

The construction of new, high performance material test reactor or the conversion of such reactors' core from high enriched uranium (HEU) to low enriched uranium (LEU) based fuel requires several fuel qualification steps. For the conversion of high performance reactors, high density dispersion or monolithic fuel types are being developed. The Uranium-Molybdenum fuel system has been selected as reference system for the qualification of LEU fuels. For reactors with lower performance characteristics, or as medium enriched fuel for high performance reactors, uranium silicide dispersion fuel is applied. However, on the longer term, the U-Mo based fuel types may offer a more efficient fuel alternative and-or an easier back-end solution with respect to the silicide based fuels. At the BR2 reactor of the Belgian nuclear research center, SCK-CEN in Mol, several types of fuel testing opportunities are present to contribute to such qualification process. A generic validation test for a selected fuel system is the irradiation of flat plates with representative dimensions for a fuel element. By flexible positioning and core loading, bounding irradiation conditions for fuel elements can be performed in a standard device in the BR2. For fuel element designs with curved plates, the element fabrication method compatibility of the fuel type can be addressed by incorporating a set of prototype fuel plates in a mixed driver fuel element of the BR2 reactor. These generic types of tests are performed directly in the primary coolant flow conditions of the BR2 reactor. The experiment control and interpretation is supported by detailed neutronic and thermal-hydraulic modeling of the experiments. Finally, the BR2 reactor offers the flexibility for irradiation of full size prototype fuel elements, as 200mm diameter irradiation channels are available. These channels allow the accommodation of various types of prototype fuel elements, eventually using a dedicated cooling loop to provide the

EBR-2 [Experimental Breeder Reactor-2], IFR [Integral Fast Reactor] prototype testing programs

International Nuclear Information System (INIS)

Lehto, W.K.; Sackett, J.I.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.

1990-01-01

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development. (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

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"...

Reactor BR2. Introduction

International Nuclear Information System (INIS)

Gubel, P.

2001-01-01

The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given

Reactor BR2. Introduction

Energy Technology Data Exchange (ETDEWEB)

Gubel, P

2001-04-01

The BR2 is a materials testing reactor and is still one of SCK-CEN's important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. During the last three years, the availability of the installation was maintained at an average level of 97.6 percent. In the year 2000, the reactor was operated for a total of 104 days at a mean power of 56 MW. In 2000, most irradiation experiments were performed in the CALLISTO PWR loop. The report describes irradiations achieved or under preparation in 2000, including the development of advanced facilities and concept studies for new programmes. An overview of the scientific irradiation programmes as well as of the R and D programme of the BR2 reactor in 2000 is given.

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.

Gaia DR2 documentation Chapter 3: Astrometry

Science.gov (United States)

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

2018-04-01

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

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

Safety features of TR-2 reactor

International Nuclear Information System (INIS)

Tuerker, T.

2001-01-01

TR-2 is a swimming pool type research reactor with 5 MW thermal power and uses standard MTR plate type fuel elements. Each standard fuel element consist of 23 fuel plates with a meat + cladding thickness of 0.127 cm, coolant channel clearance is 0.21 cm. Originally TR-2 is designed for %93 enriched U-Al. Alloy fuel meat.This work is based on the preparation of the Final Safety Analyses Report (FSAR) of the TR-2 reactor. The main aspect is to investigate the behaviour of TR-2 reactor under the accident and abnormal operating conditions, which cowers the accident spectrum unique for the TR-2 reactor. This presentation covers some selected transient analyses which are important for the safety aspects of the TR-2 reactor like reactivity induced startup accidents, pump coast down (Loss of Flow Accident, LOFA) and other accidents which are charecteristic to the TR-2

Association of differentiated thyroid carcinoma with HLA-DR7

International Nuclear Information System (INIS)

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

1985-01-01

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

Shepard Award Winners, Part 2: Dr. Tracie Williams

Centers for Disease Control (CDC) Podcasts

2009-07-29

This podcast highlights the accomplishments of Dr. Tracie Williams, recipient of the prestigious 2009 CDC Charles C. Shepard Award.  Created: 7/29/2009 by Centers for Disease Control and Prevention (CDC).   Date Released: 7/29/2009.

Reactor BR2. Introduction

International Nuclear Information System (INIS)

Gubel, P.

2002-01-01

The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system

Reactor BR2. Introduction

Energy Technology Data Exchange (ETDEWEB)

Gubel, P

2002-04-01

The BR2 materials testing reactor is one of SCK-CEN's most important nuclear facilities. After an extensive refurbishment to compensate for the ageing of the installation, the reactor was restarted in April 1997. In 2001, the reactor was operated for a total of 123 days at a mean power of 59 MW in order to satisfy the irradiation conditions of the internal and external programmes using mainly the CALLISTO PWR loop. The mean consumption of fresh fuel elements was 5.26 per 1000 MWd. Main achievements in 2001 included the development of a three-dimensional full-scale model of the BR2 reactor for simulation and prediction of irradiation conditions for various experiments; the construction of the FUTURE-MT device designed for the irradiation of fuel plates under representative conditions of geometry, neutron spectrum, heat flux and thermal-hydraulic conditions and the development of in-pile instrumentation and a data acquisition system.

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.

BR2 Reactor: Introduction

International Nuclear Information System (INIS)

Moons, F.

2007-01-01

The irradiations in the BR2 reactor are in collaboration with or at the request of third parties such as the European Commission, the IAEA, research centres and utilities, reactor vendors or fuel manufacturers. The reactor also contributes significantly to the production of radioisotopes for medical and industrial applications, to neutron silicon doping for the semiconductor industry and to scientific irradiations for universities. Along the ongoing programmes on fuel and materials development, several new irradiation devices are in use or in design. Amongst others a loop providing enhanced cooling for novel materials testing reactor fuel, a device for high temperature gas cooled fuel as well as a rig for the irradiation of metallurgical samples in a Pb-Bi environment. A full scale 3-D heterogeneous model of BR2 is available. The model describes the real hyperbolic arrangement of the reactor and includes the detailed 3-D space dependent distribution of the isotopic fuel depletion in the fuel elements. The model is validated on the reactivity measurements of several tens of BR2 operation cycles. The accurate calculations of the axial and radial distributions of the poisoning of the beryllium matrix by 3 He, 6 Li and 3T are verified on the measured reactivity losses used to predict the reactivity behavior for the coming decades. The model calculates the main functionals in reactor physics like: conventional thermal and equivalent fission neutron fluxes, number of displacements per atom, fission rate, thermal power characteristics as heat flux and linear power density, neutron/gamma heating, determination of the fission energy deposited in fuel plates/rods, neutron multiplication factor and fuel burn-up. For each reactor irradiation project, a detailed geometry model of the experimental device and of its neighborhood is developed. Neutron fluxes are predicted within approximately 10 percent in comparison with the dosimetry measurements. Fission rate, heat flux and

Description of work for 100-DR-2 Operable Unit Vadose Drilling/test pits

International Nuclear Information System (INIS)

Naiknimbalkar, N.

1993-01-01

This report describes the scope of work for the boreholes/test pits of the 100-DR-2 Operable Unit. Sampling and field activities include: Soil screening; geologic sampling; soil sampling (physical property); analytical sampling and depths; and geophysical logging

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)

Web-nyheder og tv-nyheder på DR og TV2

DEFF Research Database (Denmark)

Bang, Jørgen

2008-01-01

Artiklen undersøger forholdet med web-nyheder og tv-nyheder i danske public service (DR1 og TV2). Ud fra analyser af web-nyhederne og og tv-nyhederne i uge 4 og 17 sammenholdt med analyser af net-brugerne og tv-seerene i samme tidsrum påpeger artiklen at net-brugerne på de to stationer kun udgør ca...

A Gaia DR2 Confirmation that 2MASS J12074836–3900043 is a Member of the TW HYA Association

Science.gov (United States)

Gagné, Jonathan; Gonzales, Eileen C.; Faherty, Jacqueline K.

2018-05-01

We use new data from Gaia DR2 to confirm that the young L1 $\\gamma$ candidate member of the TW Hya association (TWA) is now a bona fide member with a model-dependent mass estimate of ~15 $M_{Jup}$. The ambiguous M9 $\\gamma$ candidate member 2MASS J12474428---3816464 also gets a higher Bayesian membership probability for TWA membership as a result of Gaia DR2 data and a new radial velocity measurement, but it remains unclear whether it is a true member of TWA or if it is an unrelated young interloper, because it is separated by 4.6 km/s from the locus of TWA members in UVW space.

Predominant antitumor effects by fully human anti-TRAIL-receptor2 (DR5) monoclonal antibodies in human glioma cells in vitro and in vivo

Science.gov (United States)

Nagane, Motoo; Shimizu, Saki; Mori, Eiji; Kataoka, Shiro; Shiokawa, Yoshiaki

2010-01-01

Tumor necrosis factor–related apoptosis-inducing ligand (TRAIL/Apo2 L) preferentially induces apoptosis in human tumor cells through its cognate death receptors DR4 or DR5, thereby being investigated as a potential agent for cancer therapy. Here, we applied fully human anti-human TRAIL receptor monoclonal antibodies (mAbs) to specifically target one of death receptors for TRAIL in human glioma cells, which could also reduce potential TRAIL-induced toxicity in humans. Twelve human glioma cell lines treated with several fully human anti-human TRAIL receptor mAbs were sensitive to only anti-DR5 mAbs, whereas they were totally insensitive to anti-DR4 mAb. Treatment with anti-DR5 mAbs exerted rapid cytotoxicity and lead to apoptosis induction. The cellular sensitivity was closely associated with cell-surface expression of DR5. Expression of c-FLIPL, Akt, and Cyclin D1 significantly correlated with sensitivity to anti-DR5 mAbs. Primary cultures of glioma cells were also relatively resistant to anti-DR5 mAbs, exhibiting both lower DR5 and higher c-FLIPL expression. Downregulation of c-FLIPL expression resulted in the sensitization of human glioma cells to anti-DR5 mAbs, whereas overexpression of c-FLIPL conferred resistance to anti-DR5 mAb. Treatment of tumor-burden nude mice with the direct agonist anti-DR5 mAb KMTR2 significantly suppressed growth of subcutaneous glioma xenografts leading to complete regression. Similarly, treatment of nude mice bearing intracerebral glioma xenografts with KMTR2 significantly elongated lifespan without tumor recurrence. These results suggest that DR5 is the predominant TRAIL receptor mediating apoptotic signals in human glioma cells, and sensitivity to anti-DR5 mAbs was determined at least in part by the expression level of c-FLIPL and Akt. Specific targeting of death receptor pathway through DR5 using fully human mAbs might provide a novel therapeutic strategy for intractable malignant gliomas. PMID:20511188

Application of MCNPX 2.7.D for reactor core management at the research reactor BR2

International Nuclear Information System (INIS)

Kalcheva, Silva; Koonen, Edgar

2011-01-01

The paper discusses application of the Monte Carlo burn up code MCNPX 2.7.D for whole core criticality and depletion analysis of the Material Testing Research Reactor BR2 at SCK-CEN in Mol, Belgium. Two different approaches in the use of MCNPX 2.7.D are presented. The first methodology couples the evolution of fuel depletion, evaluated by MCNPX 2.7.D in an infinite lattice with a steady-state 3-D power distribution in the full core model. The second method represents fully automatic whole core depletion and criticality calculations in the detailed 3-D heterogeneous geometry model of the BR2 reactor. The accuracy of the method and computational time as function of the number of used unique burn up materials in the model are being studied. The depletion capabilities of MCNPX 2.7.D are compared vs. the developed at the BR2 reactor department MCNPX & ORIGEN-S combined method. Testing of MCNPX 2.7.D on the criticality measurements at the BR2 reactor is presented. (author)

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

Site-Specific Waste Management Instruction - 100-DR-1 Group 2 Sites

International Nuclear Information System (INIS)

Jackson, R.W.

1998-01-01

This site-specific waste management instruction (SSWMI) provides guidance for the management of wastes that may be generated during the excavation and remediation of the 100-DR-1 Group 2 sites. The management of waste generated as a result of these activities will be as directed in this SSWMI. This SSWMI will be revised to incorporate guidance for management of wastes encountered that are not addressed in this SSWMI

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)

Very Large Array H I Zeeman Observations of the Cygnus X Region: DR 22 and ON 2

Science.gov (United States)

Mayo, E. A.; Troland, T. H.

2012-02-01

We have used the Very Large Array to study the Zeeman effect in 21 cm H I absorption lines from two star-forming regions in the Cygnus X complex, DR 22 and ON 2. We measure the line-of-sight magnetic field toward these regions, finding B los = -84 ± 11 μG toward the DR 22 H II region and B los < 50 μG toward each of the two H II regions in ON 2. We interpret these results in terms of two different models. In one model, we assume that the H I Zeeman effect is a measure of magnetic fields in the associated molecular clouds. If so, then the DR 22 molecular cloud is magnetically subcritical, that is, magnetically dominated. The ON 2 molecular clouds are magnetically supercritical. In a second model, we assume that the H I Zeeman effect is a measure of magnetic fields in photon-dominated regions where the gas has been compressed (and the field amplified) by absorption of stellar radiation. We find that this second model, where the measured field strength has been affected by star formation, accounts well for the DR 22 H I Zeeman effect. This same model, however, overpredicts the magnetic field in ON 2. ON 2 may be a region where the magnetic field is energetically insignificant or where the field happens to lie nearly in the plane of the sky.

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)

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...

Core monitoring at the WNP-2 reactor

International Nuclear Information System (INIS)

Skeen, D.R.; Torres, R.H.; Burke, W.J.; Jenkins, I.; Jones, S.W.

1992-01-01

The WNP-2 reactor is a 3,323-MW(thermal) boiling water reactor (BWR) that is operated by the Washington Public Power Supply System. The WNP-2 reactor began commercial operation in 1984 and is currently in its eighth cycle. The core monitoring system used for the first cycle of operation was supplied by the reactor vendor. Cycles 2 through 6 were monitored with the POWERPLEX Core Monitoring Software System (CMSS) using the XTGBWR simulation code. In 1991, the supply system upgraded the core monitoring system by installing the POWERPLEX 2 CMSS prior to the seventh cycle of operation for WNP-2. The POWERPLEX 2 CMSS was developed by Siemens Power Corporation (SPC) and is based on SPC's advanced state-of-the-art reactor simulator code MICROBURN-B. The improvements in the POWERPLEX 2 system are possible as a result of advances in minicomputer hardware

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, ...

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

TA-2 Water Boiler Reactor Decommissioning Project

International Nuclear Information System (INIS)

Durbin, M.E.; Montoya, G.M.

1991-06-01

This final report addresses the Phase 2 decommissioning of the Water Boiler Reactor, biological shield, other components within the biological shield, and piping pits in the floor of the reactor building. External structures and underground piping associated with the gaseous effluent (stack) line from Technical Area 2 (TA-2) Water Boiler Reactor were removed in 1985--1986 as Phase 1 of reactor decommissioning. The cost of Phase 2 was approximately $623K. The decommissioning operation produced 173 m 3 of low-level solid radioactive waste and 35 m 3 of mixed waste. 15 refs., 25 figs., 3 tabs

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:

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

International Nuclear Information System (INIS)

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

2011-01-01

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

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

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.

EBR-2 [Experimental Breeder Reactor-2] test programs

International Nuclear Information System (INIS)

Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

1990-01-01

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

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

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....

BR2 Reactor: Irradiation of fuels

International Nuclear Information System (INIS)

Verwimp, A.

2005-01-01

Safe, reliable and economical operation of reactor fuels, both UO 2 and MOX types, requires in-pile testing and qualification up to high target burn-up levels. In-pile testing of advanced fuels for improved performance is also mandatory. The objectives of research performed at SCK-CEN are to perform Neutron irradiation of LWR (Light Water Reactor) fuels in the BR2 reactor under relevant operating and monitoring conditions, as specified by the experimenter's requirements and to improve the on-line measurements on the fuel rods themselves

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...

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)

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.

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

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

Ageing management of the BR2 research reactor

International Nuclear Information System (INIS)

Verpoortem, J. R.; Van Dyck, S.

2014-01-01

At the Belgian nuclear research centre (SCK.CEN) several test reactors are operated. Among these, Belgian Reactor 2 (BR2) is the largest Material Test Reactor (MTR). This water-cooled, beryllium moderated reactor with a maximum thermal power of 100 MW became operational in 1962. Except for two major refurbishment campaigns of one year each, this reactor has been operated continuously over the past 50 years, with a frequency of 5-12 cycles per year. At present, BR2 is used for different research activities, the production of medical isotopes, the production of n-doped silicon and various training and education activities. (Author)

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

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.

Vascular endothelial growth factor (VEGF-related single nucleotide polymorphisms rs10738760 and rs6921438 are not associated with diabetic retinopathy (DR in Slovenian patients with type 2 diabetes mellitus (T2DM

Directory of Open Access Journals (Sweden)

Rifet Terzić

2017-11-01

Full Text Available Diabetic retinopathy (DR is a complication of diabetes characterized by vascular permeability, increased tissue ischemia, and angiogenesis. One of the most important proteins involved in angiogenesis is vascular endothelial growth factor (VEGF, also known as VEGFA. A previous study demonstrated that two single nucleotide polymorphisms (SNPs, rs6921438 and rs10738760, account for nearly half the variation in circulating VEGF levels. The aim of our study was to assess the association between rs6921438 and rs10738760 and DR in Slovenian patients with type 2 diabetes mellitus (T2DM. This case-control study enrolled 1037 unrelated Slovenian individuals (Caucasians with T2DM. DR group included 415 T2DM patients with DR, while control group included 622 T2DM patients with no clinical signs of DR. The clinical and laboratory data were obtained from the medical records of the patients. The genotyping of rs6921438 and rs10738760 SNPs was carried out with real-time PCR assays. Significant differences were observed between patients with DR and controls in the duration of diabetes (p < 0.001, insulin therapy (p < 0.001, glycated hemoglobin (p = 0.001, body mass index (p = 0.002, total cholesterol (p = 0.002, and low-density lipoprotein cholesterol (p < 0.001. However, we did not observe significant differences in the genotype and allele distribution of the two SNPs, between DR and control group (p < 0.05. Logistic regression analysis showed that rs6921438 and rs10738760 were not independent genetic risk factors for DR in the co-dominant model adjusted for the above-mentioned clinical and laboratory data. In conclusion, VEGF-related SNPs rs10738760 and rs6921438 are not associated with DR in our group of Slovenian patients (Caucasians with T2DM.

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 theory and power reactors. 1. Calculational methods for reactors. 2. Reactor kinetics

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

Various methods for calculation of neutron flux in power reactors are discussed. Some mathematical models used to describe transients in nuclear reactors and techniques for the reactor kinetics' relevant equations solution are also presented

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)

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)

BR2 reactor neutron beams

International Nuclear Information System (INIS)

Neve de Mevergnies, M.

1977-01-01

The use of reactor neutron beams is becoming increasingly more widespread for the study of some properties of condensed matter. It is mainly due to the unique properties of the ''thermal'' neutrons as regards wavelength, energy, magnetic moment and overall favorable ratio of scattering to absorption cross-sections. Besides these fundamental reasons, the impetus for using neutrons is also due to the existence of powerful research reactors (such as BR2) built mainly for nuclear engineering programs, but where a number of intense neutron beams are available at marginal cost. A brief introduction to the production of suitable neutron beams from a reactor is given. (author)

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

International Nuclear Information System (INIS)

Chu, Steven

2012-01-01

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

Fission product release from SLOWPOKE-2 reactors

Energy Technology Data Exchange (ETDEWEB)

Harnden-Gillis, A M.C. [Queen` s Univ., Kingston, ON (Canada). Dept. of Physics

1994-12-31

Increasing radiation fields at several SLOWPOKE-2 reactors fuelled with highly enriched uranium aluminum alloy fuel have begun to interfere with the daily operation of these reactors. To investigate this phenomenon, samples of reactor container water and gas from the headspace were obtained at four SLOWPOKE-2 reactor facilities and examined by gamma ray spectroscopy methods. These radiation fields are due to the circulation of fission products within the reactor container vessel. The most likely source of the fission product release is an area of uranium-bearing material exposed to the coolant at the end weld line which originated at the time of fuel fabrication. The results of this study are compared with observations from an underwater visual examination of one core and the metallographic examination of archived fuel elements. 19 refs., 4 tabs., 8 figs.

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)

Pressurized water reactor simulator. Workshop material. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development. And the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA Training Course Series No. 12, 'Reactor Simulator Development' (2001). Course material for workshops using a WWER- 1000 reactor department simulator from the Moscow Engineering and Physics Institute, the Russian Federation is presented in the IAEA Training Course Series No. 21, 2nd edition, 'WWER-1000 Reactor Simulator' (2005). Course material for workshops using a boiling water reactor simulator developed for the IAEA by Cassiopeia Technologies Incorporated of Canada (CTI) is presented in the IAEA publication: Training Course Series No.23, 2nd edition, 'Boiling Water Reactor Simulator' (2005). This report consists of course material for workshops using a pressurized water reactor simulator

TMI-2 lessons have been learned

International Nuclear Information System (INIS)

Long, R.L.

1994-01-01

This paper is an introduction to the more detailed papers which are presented in this session titled ''Advanced Light Water Reactors -- 15 Years After TMI.'' Many of the advances in the design, operation and maintenance of nuclear power plants are the direct result of applying lessons learned from the 1979 TMI-2 accident. The authors believe the ''reality awakening'' which occurred following the accident should never be forgotten. Thus, this paper briefly reviews the TMI-2 accident and identifies the broad lessons learned following the accident. Then it describes briefly some indicators which show the very impressive improvements in nuclear power plant performance that have occurred over the past 10-15 years. This sets the stage for Dr. Ransom's paper which shows the continuing need for nuclear power, Dr. Beckjord's paper which describes the ''final'' TMI-2 research project and the subsequent papers which focus on advanced light water reactor developments

Modelling surface hydrology with DR2-SAGA 1.0: development of a user-friendly interface for hillslope water balance assessments

Science.gov (United States)

López-Montero, Teresa; López-Vicente, Manuel; Navas, Ana

2013-04-01

Soil moisture variability and the depth of water stored in the arable layer of the soil are important topics in agricultural research and rangeland management. Additionally, runoff triggers soil detachment and sediment delivery, and thus is one of the most important factors in the soil erosion dynamic. Overland flow generation and accumulation are non-linear and scale-dependent processes and the development of prediction models helps researchers evaluate different scenarios at different temporal and spatial scales. In this study, we present the DR2-SAGA 1.0 module to the scientific community. The DR2 (Distributed Rainfall-Runoff) water balance model computes the depth of water stored within the soil profile (Waa) distinguishing five scenarios of the upslope contributing area, infiltration processes and climatic parameters, and assesses the soil moisture status (SMS) throughout the year for an average monthly rainfall event. The SAGA program is a free Geographical Information System (GIS) with support for vector and, specially, raster data. Its foundation is its Application Programming Interface (API), which provides data object models and basic definitions for the programming of scientific modules. Module libraries contain the scientific methods and are developed using C++ code. The new module was run in a medium size mountain Mediterranean catchment (246 ha; Spanish Central Pre-Pyrenees) at high spatial resolution (5 x 5 meters of cell size). The Estaña Lakes Catchment is affected by karstic processes which explain the presence of 15 endorheic sub-catchments and three fresh-water lakes. Additionally, this area is ungauged and offers the opportunity to test the performance of the new module in a non-conventional landscape. DR2-SAGA 1.0 demands 16 inputs and generates monthly and annual maps of initial and effective runoff depth, Waa and SMS. One user-friendly tab was created with SAGA 2.0.8 for each input and output file. The new module also includes a water

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

Advances in Reactor Physics, Mathematics and Computation. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1987-01-01

These proceedings of the international topical meeting on advances in reactor physics, mathematics and computation, Volume 2, are divided into 7 sessions bearing on: - session 7: Deterministic transport methods 1 (7 conferences), - session 8: Interpretation and analysis of reactor instrumentation (6 conferences), - session 9: High speed computing applied to reactor operations (5 conferences), - session 10: Diffusion theory and kinetics (7 conferences), - session 11: Fast reactor design, validation and operating experience (8 conferences), - session 12: Deterministic transport methods 2 (7 conferences), - session 13: Application of expert systems to physical aspects of reactor design and operation.

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

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

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

Neutron transport. Physics and calculation of nuclear reactors with applications to pressurized water reactors and fast neutron reactors. 2 ed.

International Nuclear Information System (INIS)

Bussac, J.; Reuss, P.

1985-01-01

This book presents the main physical bases of neutron theory and nuclear reactor calculation. 1) Interactions of neutrons with matter and basic principles of neutron transport; 2) Neutron transport in homogeneous medium and the neutron field: kinetic behaviour, slowing-down, resonance absorption, diffusion equation, processing methods; 3) Theory of a reactor constituted with homogeneous zones: critical condition, kinetics, separation of variables, calculation and neutron balance of the fundamental mode, one-group and multigroup theories; 4) Study of heterogeneous cell lattices: fast fission factor, resonance absorption, thermal output factor, diffusion coefficient, computer codes; 5) Operation and control of reactors: perturbation theory, reactivity, fuel properties evolution, poisoning by fission products, calculation of a reactor and fuel management; 6) Study of some types of reactors: PWR and fast breeder reactors, the main reactor types of the present French program [fr

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.

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

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

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

Science.gov (United States)

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

2008-01-17

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

Dr. John Marburger visits DESY

CERN Multimedia

2003-01-01

Dr. John Marburger, Director of the United States Office of Science and Technology Policy, visited the research center DESY in Hamburg. The American physicist wanted to inform himself about the status of the TESLA X-ray laser and the TESLA linear collider as well as the international collaboration at DESY (1/2 page).

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...

TPDWR2: thermal power determination for Westinghouse reactors, Version 2. User's guide

International Nuclear Information System (INIS)

Kaczynski, G.M.; Woodruff, R.W.

1985-12-01

TPDWR2 is a computer program which was developed to determine the amount of thermal power generated by any Westinghouse nuclear power plant. From system conditions, TPDWR2 calculates enthalpies of water and steam and the power transferred to or from various components in the reactor coolant system and to or from the chemical and volume control system. From these results and assuming that the reactor core is operating at constant power and is at thermal equilibrium, TPDWR2 calculates the thermal power generated by the reactor core. TPDWR2 runs on the IBM PC and XT computers when IBM Personal Computer DOS, Version 2.00 or 2.10, and IBM Personal Computer Basic, Version D2.00 or D2.10, are stored on the same diskette with TPDWR2

Once-through CANDU reactor models for the ORIGEN2 computer code

International Nuclear Information System (INIS)

Croff, A.G.; Bjerke, M.A.

1980-11-01

Reactor physics calculations have led to the development of two CANDU reactor models for the ORIGEN2 computer code. The model CANDUs are based on (1) the existing once-through fuel cycle with feed comprised of natural uranium and (2) a projected slightly enriched (1.2 wt % 235 U) fuel cycle. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN2 flux parameters THERM, RES, and FAST, are given

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

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.

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.

Radiation protection at the RA Reactor in 1988, Part -2, RA reactor annual report

International Nuclear Information System (INIS)

Ninkovic, M.; Ajdacic, N.; Zaric, M.; Vukovic, Z.

1988-01-01

Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor and radiation protection; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Decontamination and relevant actions, collecting and treatment of fluid effluents; and and solid radioactive wastes [sr

Irradiation effects on Zr-2.5Nb in power reactors

Energy Technology Data Exchange (ETDEWEB)

Song, C., E-mail: Carol.Song@cnl.ca [Canadian Nuclear Laboratories, Chalk River, Ontario (Canada)

2016-06-15

Zirconium alloys are widely used as structural materials in nuclear applications because of their attractive properties such as a low absorption cross-section for thermal neutrons, excellent corrosion resistance in water, and good mechanical properties at reactor operating temperatures. Zr-2.5Nb is one of the most commonly used zirconium alloys and has been used for pressure tube materials in CANDU (Canada Deuterium Uranium) and RBMK (Reaktor Bolshoy Moshchnosti Kanalnyy, 'High Power Channel-type Reactor') reactors for over 40 years. In a recent report from the Electric Power Research Institute, Zr-2.5Nb was identified as one of the candidate materials for use in normal structural applications in light-water reactors owing to its increased resistance to irradiation-induced degradation as compared with currently used materials. Historically, the largest program of in-reactor tests on zirconium alloys was performed by Atomic Energy of Canada Limited. Over many years of in-reactor testing and CANDU operating experience with Zr- 2.5Nb, extensive research has been conducted on the irradiation effects on its microstructures, mechanical properties, deformation behaviours, fracture toughness, delayed hydride cracking, and corrosion. Most of the results on Zr-2.5Nb obtained from CANDU experience could be used to predict the material performance under light water reactors. This paper reviews the irradiation effects on Zr-2.5Nb in power reactors (including heavy-water and light-water reactors) and summarizes the current state of knowledge. (author)

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.

IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1992-07-01

The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1.

IGORR 2: Proceedings of the 2. meeting of the International Group On Research Reactors

International Nuclear Information System (INIS)

1992-01-01

The International group on Research Reactors was formed to facilitate the sharing of knowledge and experience among those institutions and individuals who are actively working to design, build, and promote new research reactors or to make significant upgrades to existing facilities. Sessions during this second meeting were devoted to research reactor reports (GRENOBLE reactor, FRM-II, HIFAR, PIK, reactors at JAERI, MAPLE, ANS, NIST, MURR, TRIGA, BR-2, SIRIUS 2); other neutron sources; and two workshops were dealing with research and development results and needs and reports on progress in needed of R and D areas identified at IGORR 1

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.

Characterization of the Three Mile Island Unit-2 reactor building atmosphere prior to the reactor building purge

International Nuclear Information System (INIS)

Hartwell, J.K.; Mandler, J.W.; Duce, S.W.; Motes, B.G.

1981-05-01

The Three Mile Island Unit-2 reactor building atmosphere was sampled prior to the reactor building purge. Samples of the containment atmosphere were obtained using specialized sampling equipment installed through penetration R-626 at the 358-foot (109-meter) level of the TMI-2 reactor building. The samples were subsequently analyzed for radionuclide concentration and for gaseous molecular components (O 2 , N 2 , etc.) by two independent laboratories at the Idaho National Engineering Laboratory (INEL). The sampling procedures, analysis methods, and results are summarized

Radiation protection at the RA Reactor in 1998, RA reactor annual report, Part -2

International Nuclear Information System (INIS)

Ninkovic, M.; Pavlovic, R.; Mandic, M.; Pavlovic, S.; Grsic, Z.

1998-01-01

Radiation protection tasks which enable safe operation of the RA reactor, and are defined according the the legal regulations and IAEA safety recommendations are sorted into four categories in this report: (1) Control of the working environment, dosimetry at the RA reactor; (2) Radioactivity control in the vicinity of the reactor and meteorology measurements; (3) Collecting and treatment of fluid effluents; and (4) radioactive wastes, decontamination and actions. Each of the category is described as a separate annex of this report [sr

Active species in a large volume N2-O2 post-discharge reactor

International Nuclear Information System (INIS)

Kutasi, K; Pintassilgo, C D; Loureiro, J; Coelho, P J

2007-01-01

A large volume post-discharge reactor placed downstream from a flowing N 2 -O 2 microwave discharge is modelled using a three-dimensional hydrodynamic model. The density distributions of the most populated active species present in the reactor-O( 3 P), O 2 (a 1 Δ g ), O 2 (b 1 Σ g + ), NO(X 2 Π), NO(A 2 Σ + ), NO(B 2 Π), NO 2 (X), O 3 , O 2 (X 3 Σ g - ) and N( 4 S)-are calculated and the main source and loss processes for each species are identified for two discharge conditions: (i) p = 2 Torr, f = 2450 MHz, and (ii) p = 8 Torr, f = 915 MHz; in the case of a N 2 -2%O 2 mixture composition and gas flow rate of 2 x 10 3 sccm. The modification of the species relative densities by changing the oxygen percentage in the initial gas mixture composition, in the 0.2%-5% range, are presented. The possible tuning of the species concentrations in the reactor by changing the size of the connecting afterglow tube between the active discharge and the large post-discharge reactor is investigated as well

G 2 reactor project; Projet de pile a double fin: G 2

Energy Technology Data Exchange (ETDEWEB)

Ailleret, [Electricite de France (EDF), Dir. General des Etudes de Recherches, 75 - Paris (France); Taranger, P; Yvon, J [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1955-07-01

The CEA actually constructs the G-2 reactor core working with natural uranium, which will use graphite as moderator, and gas under pressure as cooling fluid. This report presents the specificity of the new reactor: - the different elements of the reactor core, - the control and the security of the reactor, - the renewal of the fuel, - the biologic surrounding wall, - and the cooling circuit. (M.B.) [French] le Commissariat a l'Energie Atomique construit actuellement la pile G-2 a Uranium naturel, qui utilisera le graphite comme moderateur, et le gaz sous pression comme fluide de refroidissement. Ce rapport presente les specificite du nouveau reacteur: - les differents elements de la pile, - le controle et la securite du reacteur, - le renouvellement du combustible, - l'enceinte biologique, - et le circuit de refroidissement. (M.B.)

Reactor handbook. 2. rev. ed.

International Nuclear Information System (INIS)

Lederer, B.J.; Wildberg, D.W.

1992-01-01

On the basis of the guidelines on expert knowledge, the book discusses the subjects of atomic physics, heat transfer, nuclear power plants, reactor materials, radiation protection, reactor safety, reactor instrumentation, and reactor operation, with special regard to nuclear power plants with LWR-type reactors. The book is intended for shift personnel, especially gang bosses, reactor operators, and control station operators: for this reason a practical and rather popular style has been chosen. However, the book will also be a manual for other operating personnel, personnel of producer companies, expert organisations, authorities, and students. It can be used as a textbook for staff training, a manual for the practice, and as accompanying book for teaching at nuclear engineering schools. (orig.) With 173 figs [de

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

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

Annual report on JEN-1 and JEN-2 Reactors; Informe periodico de Reactores JEN-1 y JEN-2 correpondiente al ano 1972

Energy Technology Data Exchange (ETDEWEB)

Montes Ponce de Leon, J.

1974-07-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (Author)

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

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.

Optimized Control Rods of the BR2 Reactor

Energy Technology Data Exchange (ETDEWEB)

Kalcheva, Silva; Koonen, E.

2007-09-15

At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

Optimized Control Rods of the BR2 Reactor

International Nuclear Information System (INIS)

Kalcheva, Silva; Koonen, E.

2007-01-01

At the present time the BR-2 reactor uses control elements with cadmium as neutron absorbing part. The lower section of the control element is a beryllium assembly cooled by light water. Due to the burn up of the lower end of the cadmium section during the reactor operation, the presently used rods for reactivity control of the BR-2 reactor have to be replaced by new ones. Considered are various types Control Rods with full active part of the following materials: cadmium (Cd), hafnium (Hf), europium oxide (Eu2O3) and gadolinium (Gd2O3). Options to decrease the burn up of the control rod material in the hot spot, such as use of stainless steel in the lower active part of the Control Rod are discussed. Comparison with the characteristics of the presently used Control Rods types is performed. The changing of the characteristics of different types Control Rods and the perturbation effects on the reactor neutronics during the BR-2 fuel cycle are investigated. The burn up of the Control Rod absorbing material, total and differential control rods worth, macroscopic and effective microscopic absorption cross sections, fuel and reactivity evolution are evaluated during approximately 30 operating cycles.

Upgrading of the research reactors FRG-1 and FRG-2

International Nuclear Information System (INIS)

Krull, W.

1981-01-01

In 1972 for the research reactor FRG-2 we applied for a license to increase the power from 15 MW to 21 MW. During this procedure a public laying out of the safety report and an upgrading procedure for both research reactors - FRG-1 (5 MW) and FRG-2 - were required by the licensing authorities. After discussing the legal background for licensing procedures in the Federal Republic of Germany the upgrading for both research reactors is described. The present status and future licensing aspects for changes of our research reactors are discussed, too. (orig.) [de

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.

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.

Capsaicin sensitizes TRAIL-induced apoptosis through Sp1-mediated DR5 up-regulation: Involvement of Ca2+ influx

International Nuclear Information System (INIS)

Moon, Dong-Oh; Kang, Chang-Hee; Kang, Sang-Hyuck; Choi, Yung-Hyun; Hyun, Jin-Won; Chang, Weon-Young; Kang, Hee-Kyoung; Koh, Young-Sang; Maeng, Young-Hee; Kim, Young-Ree; Kim, Gi-Young

2012-01-01

Although tumor necrosis factor-related apoptosis-inducing ligand (TRAIL) induces apoptosis in various malignant cells, several cancers including human hepatocellular carcinoma (HCC) exhibit potent resistance to TRAIL-induced cell death. The aim of this study is to evaluate the anti-cancer potential of capsaicin in TRAIL-induced cancer cell death. As indicated by assays that measure phosphatidylserine exposure, mitochondrial activity and activation of caspases, capsaicin potentiated TRAIL-resistant cells to lead to cell death. In addition, we found that capsaicin induces the cell surface expression of TRAIL receptor DR5, but not DR4 through the activation Sp1 on its promoter region. Furthermore, we investigated that capsaicin-induced DR5 expression and apoptosis are inhibited by calcium chelator or inhibitors for calmodulin-dependent protein kinase. Taken together, our data suggest that capsaicin sensitizes TRAIL-mediated HCC cell apoptosis by DR5 up-regulation via calcium influx-dependent Sp1 activation. Highlights: ► Capsaicin sensitizes TRAIL-induced apoptosis through activation of caspases. ► Capsaicin induces expression of DR5 through Sp1 activation. ► Capsaicin activates calcium signaling pathway.

Redirecting Therapeutic T Cells against Myelin-Specific T Lymphocytes Using a Humanized Myelin Basic Protein-HLA-DR2-{zeta} Chimeric Receptor

DEFF Research Database (Denmark)

Moisini, Ioana; Nguyen, Phuong; Fugger, Lars

2008-01-01

Therapies that Ag-specifically target pathologic T lymphocytes responsible for multiple sclerosis (MS) and other autoimmune diseases would be expected to have improved therapeutic indices compared with Ag-nonspecific therapies. We have developed a cellular immunotherapy that uses chimeric receptors...... mouse model system. Finally, the chimeric receptor-modified CTL ameliorated or blocked experimental allergic encephalomyelitis (EAE) disease mediated by MBP(84-102)/DR2-specific T lymphocytes. These results provide support for the further development of redirected therapeutic T cells able to counteract...... pathologic, self-specific T lymphocytes, and specifically validate humanized MBP-DR2-zeta chimeric receptors as a potential therapeutic in MS. Udgivelsesdato: 2008-Mar-1...

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)

Annual report on JEN-1 and JEN-2 Reactors

International Nuclear Information System (INIS)

Montes Ponce de Leon, J.

1974-01-01

In the annual report on the JEN-1 and JEN-2 reactors the main fractures of the reactor operations and maintenance are described. The reactor has been in operation for 2188 hours, what means 74% of the total working time. Maintenance and periodical tests have occupied the rest of the time. Maintenance operations are shown according to three main subjects, the main failures so as the reactor scrams are also described. Different date relating with radiation level and health Physics are also included. (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

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.

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.

System Design of a Supercritical CO_2 cooled Micro Modular Reactor

International Nuclear Information System (INIS)

Kim, Seong Gu; Cho, Seongkuk; Yu, Hwanyeal; Kim, Yonghee; Jeong, Yong Hoon; Lee, Jeong Ik

2014-01-01

Small modular reactor (SMR) systems that have advantages of little initial capital cost and small restriction on construction site are being developed by many research organizations around the world. Existing SMR concepts have the same objective: to achieve compact size and a long life core. Most of small modular reactors have much smaller size than the large nuclear power plant. However, existing SMR concepts are not fully modularized. This paper suggests a complete modular reactor with an innovative concept for reactor cooling by using a supercritical carbon dioxide. The 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 reactor core and PCU in one vessel. A conceptual design of the proposed small modular reactor was developed, which is named as KAIST Micro Modular Reactor (MMR). The supercritical CO_2 Brayton cycle for the S-CO_2 cooled reactor core was optimized and the size of turbomachinery and heat exchanger were estimated preliminary. The nuclear fuel composed with UN was proposed and the core lifetime was obtained from a burnup versus reactivity calculation. Furthermore, a system layout with fully passive safety systems for both normal operation and emergency operation was proposed. (author)

The SLOWPOKE-2 reactor with low enrichment uranium oxide fuel

International Nuclear Information System (INIS)

Townes, B.M.; Hilborn, J.W.

1985-06-01

A SLOWPOKE-2 reactor core contains less than 1 kg of highly enriched uranium (HEU) and the proliferation risk is very low. However, to overcome proliferation concerns a new low enrichment uranium (LEU) fuelled reactor core has been designed. This core contains approximately 180 fuel elements based on the Zircaloy-4 clad UOsub(2) CANDU fuel element, but with a smaller outside diameter. The physics characteristics of this new reactor core ensure the inherent safety of the reactor under all conceivable conditions and thus the basic SLOWPOKE safety philosophy which permits unattended operation is not affected

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...

[Preparation and application of monoclonal antibodies against DR region of Na+-K+-ATPase α1 subunit].

Science.gov (United States)

Yan, Xiaofei; Wu, Litao; DU, Xiaojuan; Li, Jing; Zhang, Fujun; Han, Yan; Lyu, Shemin; Li, Dongmin

2016-12-01

Objective To prepare monoclonal antibodies against DR region (897DVEDSYGQQWTYEQR911) of Na + -K + -ATPase α1 subunit and identify their properties. Methods BALB/c mice were immunized with DR-keyholelimpet hemocyanin (KLH). Splenocytes from the immunized mice were collected and subsequently fused with SP2/0 mouse myeloma cells. Positive hybridoma clones were obtained after cell fusion and selection. ELISA was used to detect DR antibody titer in the cell supernatants. DR region-specific monoclonal antibodies were analyzed by dot blotting, Western blotting and immunofluorescence assay. Na + -K + -ATPase activity was detected by SensoLyte R FDP Protein Phosphatase Assay Kit and the protective effect of the monoclonal antibody against high glucose-induced cell injury was assessed in H9c2 cells. Results Three hybridoma cell lines which secreted stable DR monoclonal antibody were obtained. The strongest positive cell line, named DRm217, was selected to prepare ascites. Dot blotting, Western blotting and immunofluorescence assay showed that DRm217 recognized specially DR region of Na + -K + -ATPase and bound on H9c2 cell membranes. DRm217 stimulated Na + -K + -ATPase activity and alleviated high glucose-induced H9c2 cells injury. Conclusion The monoclonal antibodies against DR region of Na + -K + -ATPase α1 subunit is prepared.

Intra HLA-D/DR region recombinant detected by primed lymphocyte typing (PLT)

DEFF Research Database (Denmark)

Jakobsen, B K; Kristensen, T; Lamm, L U

1983-01-01

lymphocyte typing (PLT) for HLA-D/DR region associated DP antigens. None of these studies gave evidence that the recombinations had occurred within the HLA region. Mixed leucocyte culture (MLC) tests within the families showed no detectable stimulation between the HLA identical siblings in two......The chromosome 6 markers, HLA-ABC, D, DR, MT, properdin factor Bf, and complement factors 2 (C2) and 5 (C4), were studied in three families, each of which included two HLA identical siblings, one or both of whom were known to be HLA-B: GLO recombinants. The families were also typed with primed...... to reactive reagents. One of these (GHx), reacted with a determinant which segregated within the GG family as if child G was a paternal recombinant between the HLA-D, DR, DP, and C4 loci, on the one hand, and on the other hand one or more loci governing other HLA-D/DR region controlled lymphocyte activating...

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

Science.gov (United States)

Niu, Zhili; Zhang, Pingan; Tong, Yongqing

2015-01-01

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

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.

Operation of the SLOWPOKE-2 reactor in Jamaica

Energy Technology Data Exchange (ETDEWEB)

Grant, C.N.; Lalor, G.C.; Vuchkov, M.K. [University of the West Indies, Kingston (Jamaica)

2001-07-01

Over the past sixteen years lCENS has operated a SLOWPOKE 2 nuclear reactor almost exclusively for the purpose of neutron activation analysis. During this period we have adopted a strategy of minimum irradiation times while optimizing our output in an effort to increase the lifetime of the reactor core and to maintaining fuel integrity. An inter-comparison study with results obtained with a much larger reactor at IPEN has validated this approach. The parameters routinely monitored at ICENS are also discussed and the method used to predict the next shim adjustment. (author)

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

Energy Technology Data Exchange (ETDEWEB)

1994-08-15

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

Irradiation techniques at BR2 reactor

International Nuclear Information System (INIS)

Hebel, W.

1978-01-01

Since 1963 the material testing reactor BR2 at Mol is operated for the realisation of numerous research programs and experiments on the behavior of materials under nuclear radiation and in particular under intensive neutron exposure. During this period special irradiation techniques and experimental devices were developed according to the desiderata of the different experiments and to the irradiation possibilities offered at BR2. The design and the operating characteristics of quite a number of those irradiation rigs of proven reliability may be used or can be made available for new irradiation experiments. A brief description is given of some typical irradiation devices designed and constructed by CEN/SCK, Technology and Energy Dpt. They are compiled according to their main use for the different research and development programs realized at BR2. Their eventual application however for different objectives could be possible. A final chapter summarizes the principal irradiation conditions offered by BR2 reactor. (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.

TMI-2 reactor vessel head removal

International Nuclear Information System (INIS)

Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

1985-09-01

This report describes the safe removal and storage of the Three Mile Island Unit 2 (TMI-2) reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training, the head was safely removed and stored; and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

TMI-2 reactor vessel plenum final lift

International Nuclear Information System (INIS)

Wilson, D.C.

1986-01-01

Removal of the plenum assembly from the TMI-2 reactor vessel was necessary to gain access to the core region for defueling. The plenum was lifted from the reactor vessel by the polar crane using three specially designed pendant assemblies. It was then transferred in air to the flooded deep end of the refueling canal and lowered onto a storage stand where it will remain throughout the defueling effort. The lift and transfer were successfully accomplished on May 15, 1985 in just under three hours by a lift team located in a shielded area within the reactor building. The success of the program is attributed to extensive mockup and training activities plus thorough preparations to address potential problems. 54 refs

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

The extinction to the H2 line emission in the DR 21 outflow source

International Nuclear Information System (INIS)

Nadeau, D.; Riopel, M.; Geballe, T.R.

1991-01-01

The v = 1-0 S(1) and Q(3) lines of H2 have been measured in four regions of the DR 21 H2 line-emission source, in order to determine whether the observed morphology of the emission represents the distribution of the excited H2 or is modified by nonuniform extinction across the source. The measured lines originate from the same upper level, and their ratio is a direct measure of the reddening. The line ratios show that the extinction is quite uniform across the source and that there is no correlation between the intensity and the extinction. This result implies that the gap between the two lobes of emission is not due to increased extinction but rather is a region where there is little excited H2 gas. 13 refs

Refurbishment programme for the BR2-reactor

Energy Technology Data Exchange (ETDEWEB)

Koonen, E [Centre d' Etude de l' Energie Nucleaire, Studiecentrum voor Kernenergie, BR2 Department, Boeretang, Mol (Belgium)

1992-07-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

Refurbishment programme for the BR2-reactor

International Nuclear Information System (INIS)

Koonen, E.

1992-01-01

BR2 is a high flux engineering test reactor, which differs from comparable material testing reactors by its specific core array (fig. 1). It is a heterogeneous, thermal, tank-in-pool type reactor, moderated by beryllium and light water, which serves also as coolant. The fuel elements consist of cylindrical assemblies loaded in channels materialized by hexagonal beryllium prisms. The central 200 mm channel is vertical, while all others are inclined and form a hyperbolical arrangement around the central one. This feature combines a very compact core with the requirement of sufficient space for individual access to all channels through penetrations in the top cover of the aluminium pressure vessel. Each channel may hold a fuel element, a control rod, an experiment, an irradiation device or a beryllium plug. The refurbishment Program According to the present programme of C.E.N./S.C.K., BR2 will be in operation until 1996. At that time, the beryllium matrix will reach its foreseen end-of-life. In order to continue operation beyond this point, a thorough refurbishment of the reactor is foreseen, in addition to the unavoidable replacement of the matrix, to ensure quality of the installation and compliance with modern standards. Some fundamental options have been taken as a starting point: BR2 will continue to be used as a classical MTR, i.e. fuel and material irradiations and safety experiments with some additional service-activities. The present configuration is optimized for that use and there is no specific experimental requirement to change the basic concepts and performance characteristics. From the customers viewpoint, it is desirable to go ahead with the well-known features of BR2, to maintain a high degree of availability and reliability and to minimize the duration of the long shutdown. It is also important to limit the amount of nuclear liabilities. So the objective of the refurbishment programme is the life extension of BR2 for about 15 years, corresponding to

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: ...

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 ...

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 ...

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

Refurbishing the BR2 materials testing reactor

International Nuclear Information System (INIS)

Baugnet, J.M.; Dekeyser, J.; Gubel, P.

1995-01-01

SCK/CEN is refurbishing its BR2 reactor to allow its further operation during the next 15 years; in doing so, it chooses to keep BR2 available for future scientific and technological irradiation programs within an international context. (author) 2 figs

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, ...

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:

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 ...

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...

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

International Nuclear Information System (INIS)

1966-01-01

This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant

SIRIUS 2: A versatile medium power research reactor

International Nuclear Information System (INIS)

Rousselle, P.

1992-01-01

Most of the Research Reactors in the world have been critical in the Sixties and operated for twenty to thirty years. Some of them have been completely shut down, modified, or simply refurbished; the total number of RR in operation has decreased but there is still an important need for medium power research reactors in order: - to sustain a power program with fuel and material testing for NPP or fusion reactors; - to produce radioisotopes for industrial or medical purposes, doped silicon, NAA or neutron radiography; - to investigate further the condensed matter, with cold neutrons routed through neutron guides to improved equipment; - to develop new technologies and applications such as medical alphatherapy. Hence, taking advantage of nearly hundred reactor x years operation and backed up by the CEA experience, TECHNICATOME assisted by FRAMATOME has designed a new versatile multipurpose Research Reactor (20-30 Mw) SIRIUS 2 taking into account: - more stringent safety rules; - the lifetime; - the flexibility enabling a wide range of experiments and, - the future dismantling of the facility according to the ALARA criteria

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 ...

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.

Sphingoid bases from sea cucumber induce apoptosis in human hepatoma HepG2 cells through p-AKT and DR5.

Science.gov (United States)

Hossain, Zakir; Sugawara, Tatsuya; Hirata, Takashi

2013-03-01

Biofunctional marine compounds have recently received substantial attention for their nutraceutical characteristics. In this study, we investigated the apoptosis-inducing effects of sphingoid bases prepared from sea cucumber using human hepatoma HepG2 cells. Apoptotic effects were determined by cell viability assay, DNA fragmentation assay, caspase-3 and caspase-8 activities. The expression levels of apoptosis-inducing death receptor-5 (DR5) and p-AKT were assayed by western blot analysis, and mRNA expression of bax, GADD45 and PPARγ was assayed by quantitative RT-PCR analysis. Sphingoid bases from sea cucumber markedly reduced the cell viability of HepG2 cells. DNA fragmentation indicative of apoptosis was observed in a dose-dependent manner. The expression levels of the apoptosis inducer protein Bax were increased by the sphingoid bases from sea cucumber. GADD45, which plays an important role in apoptosis-inducing pathways, was markedly upregulated by sphingoid bases from sea cucumber. Upregulation of PPARγ mRNA was also observed during apoptosis induced by the sphingoid bases. The expression levels of DR5 and p-AKT proteins were increased and decreased, respectively, as a result of the effects of sphingoid bases from sea cucumber. The results indicate that sphingoid bases from sea cucumber induce apoptosis in HepG2 cells through upregulation of DR5, Bax, GADD45 and PPARγ and downregulation of p-AKT. Our results show for the first time the functional properties of marine sphingoid bases as inducers of apoptosis in HepG2 cells.

OTUS - Reactor inventory management system based on ORIGEN2

Energy Technology Data Exchange (ETDEWEB)

Poellaenen, R; Toivonen, H; Lahtinen, J; Ilander, T

1995-10-01

ORIGEN2 is a computer code that calculates nuclide composition and other characteristics of nuclear fuel. The use of ORIGEN2 requires good knowledge in reactor physics. However, once the input has been defined for a particular reactor type, the calculations can be easily repeated for any burnup and decay time. This procedure produces large output files that are difficult to handle manually. A new computer code, known as OTUS, was designed to facilitate the postprocessing of the data. OTUS makes use of the inventory files precalculated with ORIGEN2 in a way that enables their versatile treatment for different safety analysis purposes. A data base is created containing a comprehensive set of ORIGEN2 calculations as a function of fuel burnup and decay time. OTUS is a reactor inventory management system for a microcomputer with Windows interface. Four major data operations are available: (1) Build data modifies ORIGEN2 output data into a suitable format, (2) View data enables flexible presentation of the data as such, (3) Different calculations, such as nuclide ratios and hot particle characteristics, can be performed for severe accident analyses, consequence analyses and research purposes, (4) Summary files contain both burnup dependent and decay time dependent inventory information related to the nuclide and the reactor specified. These files can be used for safeguards, radiation monitoring and safety assessment. (orig.) (22 refs., 29 figs.).

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.

The 2nd reactor core of the NS Otto Hahn

International Nuclear Information System (INIS)

Manthey, H.J.; Kracht, H.

1979-01-01

Details of the design of the 2nd reactor core are given, followed by a brief report summarising the operating experience gained with this 2nd core, as well as by an evaluation of measured data and statements concerning the usefulness of the knowledge gained for the development of future reactor cores. Quite a number of these data have been used to improve the concept and thus the specifications for the fuel elements of the 3rd core of the reactor of the NS Otto Hahn. (orig./HP) [de

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 ...

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. ...

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.

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...

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

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...

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

Science.gov (United States)

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

2017-03-01

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

EL-2 reactor: Thermal neutron flux distribution

International Nuclear Information System (INIS)

Rousseau, A.; Genthon, J.P.

1958-01-01

The flux distribution of thermal neutrons in EL-2 reactor is studied. The reactor core and lattices are described as well as the experimental reactor facilities, in particular, the experimental channels and special facilities. The measurement shows that the thermal neutron flux increases in the central channel when enriched uranium is used in place of natural uranium. However the thermal neutron flux is not perturbed in the other reactor channels by the fuel modification. The macroscopic flux distribution is measured according the radial positioning of fuel rods. The longitudinal neutron flux distribution in a fuel rod is also measured and shows no difference between enriched and natural uranium fuel rods. In addition, measurements of the flux distribution have been effectuated for rods containing other material as steel or aluminium. The neutron flux distribution is also studied in all the experimental channels as well as in the thermal column. The determination of the distribution of the thermal neutron flux in all experimental facilities, the thermal column and the fuel channels has been made with a heavy water level of 1825 mm and is given for an operating power of 1000 kW. (M.P.)

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

Physics design of advanced steady-state tokamak reactor A-SSTR2

International Nuclear Information System (INIS)

Nishio, Satoshi; Ushigusa, Kenkichi

2000-10-01

Based on design studies on the fusion power reactor such as the DEMO reactor SSTR, the compact power reactor A-SSTR and the DREAM reactor with a high environmental safety and high availability, a new concept of compact and economic fusion power reactor (A-SSTR2) with high safety and high availability is proposed. Employing high temperature superconductor, the toroidal filed coils supplies the maximum field of 23T on conductor which corresponds to 11T at the magnetic axis. A-SSTR2 (R p =6.2m, a p =1.5m, I p =12MA) has a fusion power of 4GW with β N =4. For an easy maintenance and for an enough support against a strong electromagnetic force on coils, a poloidal coils system has no center solenoid coils and consists of 6 coils located on top and bottom of the machine. Physics studies on the plasma equilibrium, controllability of the configuration, the plasma initiation and non-inductive current ramp-up, fusion power controllability and the diverter have shown the validity of the A-SSTR2 concept. (author)

FORE-2, Thermohydraulics and Space-Independent Reactor Kinetics for Transients

International Nuclear Information System (INIS)

Fox, J.N.; Lawler, B.E.; Butz, H.R.; Heames, T.J.

1984-01-01

1 - Description of problem or function: FORE2 is a coupled thermal hydraulics-point kinetics digital computer code designed to calculate significant reactor parameters under steady-state conditions, or as functions of time during transients. The transients may result from a programmed reactivity insertion or a power change. Variable inlet coolant flow rate and temperature are considered. The code calculates the reactor power, the individual reactivity feedbacks, and the temperature of coolant, cladding, fuel, structure, and additional material for up to seven axial positions in three channel types which represent radial zones of the reactor. The heat of fusion, accompanying fuel melting, the liquid metal voiding reactivity, and the spatial and the time variation of the fuel cladding gap coefficient due to changes in gap size are considered. 2 - Method of solution: FORE2 input consists of property data, geometry, power and flow distribution factors, external time varying functions, experimental coefficients, and termination data. The differential equations for fluid flow, heat transfer, and point neutronics are solved by explicit finite-difference procedures. 3 - Restrictions on the complexity of the problem: Reactor excursions which can be calculated are restricted to those transients in which the reactor is not substantially destroyed. As a general rule, changes in reactor geometry and composition during an excursion are limited to those cases in which the reactivity effects of the changes may be considered as small perturbations of the initial system. Thus, accidents involving large-scale disassembly and bulk meltdown of a core are not covered by FORE2. FORE2 is valid only while the core retains its initial geometry

Coma Berenices: The First Evidence for Incomplete Vertical Phase-mixing in Local Velocity Space with RAVE—Confirmed with Gaia DR2

Science.gov (United States)

Monari, G.; Famaey, B.; Minchev, I.; Antoja, T.; Bienaymé, O.; Gibson, B. K.; Grebel, E. K.; Kordopatis, G.; McMillan, P.; Navarro, J.; Parker, Q. A.; Quillen, A. C.; Reid, W.; Seabroke, G.; Siebert, A.; Steinmetz, M.; Wyse, R. F. G.; Zwitter, T.

2018-05-01

Before the publication of the Gaia DR2 we confirmed with RAVE and TGAS an observation recently made with the GALAH survey by Quillen ey al. concerning the Coma Berenices moving group in the Solar neighbourhood, namely that it is only present at negative Galactic latitudes. This allowed us to show that it is coherent in vertical velocity, providing a first evidence for incomplete vertical phase-mixing. We estimated for the first time from dynamical arguments that the moving group must have formed at most ~ 1.5 Gyr ago, and related this to a pericentric passage of the Sagittarius dwarf satellite galaxy. The present note is a rewritten version of the original arXiv post on this result now also including a confirmation of our finding with Gaia DR2.

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.

Keeping research reactors relevant: A pro-active approach for SLOWPOKE-2

International Nuclear Information System (INIS)

Cosby, L.R.; Bennett, L.G.I.; Nielsen, K.; Weir, R.

2010-01-01

The SLOWPOKE is a small, inherently safe, pool-type research reactor that was engineered and marketed by Atomic Energy of Canada Limited (AECL) in the 1970s and 80s. The original reactor, SLOWPOKE-1, was moved from Chalk River to the University of Toronto in 1970 and was operated until upgraded to the SLOWPOKE-2 reactor in 1973. In all, eight reactors in the two versions were produced and five are still in operation today, three having been decommissioned. All of the remaining reactors are designated as SLOWPOKE-2 reactors. These research reactors are prone to two major issues: aging components and lack of relevance to a younger audience. In order to combat these problems, one SLOWPOKE -2 facility has embraced a strategy that involves modernizing their reactor in order to keep the reactor up to date and relevant. In 2001, this facility replaced its aging analogue reactor control system with a digital control system. The system was successfully commissioned and has provided a renewed platform for student learning and research. The digital control system provides a better interface and allows flexibility in data storage and retrieval that was never possible with the analogue control system. This facility has started work on another upgrade to the digital control and instrumentation system that will be installed in 2010. The upgrade includes new computer hardware, updated software and a web-based simulation and training system that will allow licensed operators, students and researchers to use an online simulation tool for training, education and research. The tool consists of: 1) A dynamic simulation for reactor kinetics (e.g., core flux, power, core temperatures, etc). This tool is useful for operator training and student education; 2) Dynamic mapping of the reactor and pool container gamma and neutron fluxes as well as the vertical neutron beam tube flux. This research planning tool is used for various researchers who wish to do irradiations (e.g., neutron

Calculations of reactor-accident consequences, Version 2. CRAC2: computer code user's guide

International Nuclear Information System (INIS)

Ritchie, L.T.; Johnson, J.D.; Blond, R.M.

1983-02-01

The CRAC2 computer code is a revision of the Calculation of Reactor Accident Consequences computer code, CRAC, developed for the Reactor Safety Study. The CRAC2 computer code incorporates significant modeling improvements in the areas of weather sequence sampling and emergency response, and refinements to the plume rise, atmospheric dispersion, and wet deposition models. New output capabilities have also been added. This guide is to facilitate the informed and intelligent use of CRAC2. It includes descriptions of the input data, the output results, the file structures, control information, and five sample problems

Thermal reactor benchmark tests on JENDL-2

International Nuclear Information System (INIS)

Takano, Hideki; Tsuchihashi, Keichiro; Yamane, Tsuyoshi; Akino, Fujiyoshi; Ishiguro, Yukio; Ido, Masaru.

1983-11-01

A group constant library for the thermal reactor standard nuclear design code system SRAC was produced by using the evaluated nuclear data JENDL-2. Furthermore, the group constants for 235 U were calculated also from ENDF/B-V. Thermal reactor benchmark calculations were performed using the produced group constant library. The selected benchmark cores are two water-moderated lattices (TRX-1 and 2), two heavy water-moderated cores (DCA and ETA-1), two graphite-moderated cores (SHE-8 and 13) and eight critical experiments for critical safety. The effective multiplication factors and lattice cell parameters were calculated and compared with the experimental values. The results are summarized as follows. (1) Effective multiplication factors: The results by JENDL-2 are considerably improved in comparison with ones by ENDF/B-IV. The best agreement is obtained by using JENDL-2 and ENDF/B-V (only 235 U) data. (2) Lattice cell parameters: For the rho 28 (the ratio of epithermal to thermal 238 U captures) and C* (the ratio of 238 U captures to 235 U fissions), the values calculated by JENDL-2 are in good agreement with the experimental values. The rho 28 (the ratio of 238 U to 235 U fissions) are overestimated as found also for the fast reactor benchmarks. The rho 02 (the ratio of epithermal to thermal 232 Th captures) calculated by JENDL-2 or ENDF/B-IV are considerably underestimated. The functions of the SRAC system have been continued to be extended according to the needs of its users. A brief description will be given, in Appendix B, to the extended parts of the SRAC system together with the input specification. (author)

WWER-1000 reactor simulator. Material for training courses and workshops. 2. ed

International Nuclear Information System (INIS)

2005-01-01

The International Atomic Energy Agency (IAEA) has established an activity in nuclear reactor simulation computer programs to assist its Member States in education. The objective is to provide, for a variety of advanced reactor types, insight and practice in their operational characteristics and their response to perturbations and accident situations. To achieve this, the IAEA arranges for the development and distribution of simulation programs and educational material and sponsors courses and workshops. The workshops are in two parts: techniques and tools for reactor simulator development; and the use of reactor simulators in education. Workshop material for the first part is covered in the IAEA publication: Training Course Series No.12, Reactor Simulator Development (2001). Course material for workshops using a pressurized water reactor (PWR) simulator developed for the IAEA by Cassiopeia Technologies Inc. of Canada is presented in the IAEA publication, Training Course Series No. 22, 2nd edition, Pressurized Water Reactor Simulator (2005) and Training Course Series No.23, 2nd edition, Boiling Water Reactor Simulator (2005). This report consists of course material for workshops using the WWER-1000 Reactor Department Simulator from the Moscow Engineering and Physics Institute, Russian Federation

ASAMPSA2 best-practices guidelines for L2 PSA development and applications. Volume 3 - Extension to Gen IV reactors

International Nuclear Information System (INIS)

Bassi, C.; Bonneville, H.; Brinkman, H.; Burgazzi, L.; Polidoro, F.; Vincon, L.; Jouve, S.

2010-01-01

The main objective assigned to the Work Package 4 (WP4) of the 'ASAMPSA2' project (EC 7. FPRD) consist in the verification of the potential compliance of L2PSA guidelines based on PWR/BWR reactors (which are specific tasks of WP2 and WP3) with Generation IV representative concepts. Therefore, in order to exhibit potential discrepancies between LWRs and new reactor types, the following work was based on the up-to-date designs of: - The European Fast Reactor (EFR) which will be considered as prototypical of a pool-type Sodium-cooled Fast Reactor (SFR); - The ELSY design for the Lead-cooled Fast Reactor (LFR) technology; - The ANTARES project which could be representative of a Very-High Temperature Reactor (VHTR); - The CEA 2400 MWth Gas-cooled Fast Reactor (GFR). (authors)

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…

Catalytic Oxidation of Vanillyl Alcohol Using FeMCM-41 Nanoporous Tubular Reactor

Science.gov (United States)

Elamathi, P.; Kolli, Murali Krishna; Chandrasekar, G.

Iron containing nanoporous MCM-41 (FeMCM-41) with different Si/Fe ratios of 50, 100 and 150 was synthesized by hydrothermal synthesis process. The materials obtained from hydrothermal synthesis were characterized by various physico chemical techniques such as XRD, N2 adsorption, DR UV-vis, EPR and FTIR spectroscopy. XRD analyses of FeMCM-41 materials confirmed the presence of well-ordered crystalline structure. N2 isotherm of FeMCM-41 materials showed type IV adsorption isotherm. EPR and DR UV-vis analysis of FeMCM-41 samples indicates the presence of high tetrahedral coordination at the Si/Fe ratios of 100 and 150. The catalytic performance of FeMCM-41 nano tubular reactor was tested in the liquid phase oxidation of vanillyl alcohol into vanillin using H2O2 (50wt% in water). The reaction products were analyzed by gas chromatography in DB-5 capillary column with flame ionization detector. The products were confirmed by 1H NMR, 13C NMR and LC-Mass spectroscopy. The maximum conversion of vanillyl alcohol (85%) and selectivity towards vanillin (82%) were observed using the catalyst FeMCM-41(100) in 30min at 60∘C. The influence of reaction temperature, reaction time, reactants molar ratio, Si/Fe ratio and amount of catalyst were investigated.

Current status of restoration work for obstacle and upper core structure in reactor vessel of experimental fast reactor 'Joyo'. 2-2

International Nuclear Information System (INIS)

Okuda, Eiji; Ito, Hiromichi; Yoshihara, Shizuya

2014-01-01

An accident occurred in experimental fast reactor 'Joyo' in 2007 which is obstruction of fuel change equipment caused by contacting rotating plug and MARICO-2. In addition, we confirmed two happenings in the reactor vessel that (1) Deformation of MARICO-2 subassembly on the in vessel storage rack together with a transfer pot, (2) Deformation of the Upper core structure of 'Joyo' caused by contacting MARICO-2 subassembly and the UCS. We do the restoration work for restoring it. This time, we describe current status of Replacement work of the UCS. (author)

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.

Computer codes for the operational control of the research reactors

International Nuclear Information System (INIS)

Kalker, K.J.; Nabbi, R.; Bormann, H.J.

1986-01-01

Four small computer codes developed by ZFR are presented, which have been used for several years during operation of the research reactors FRJ-1, FRJ-2, AVR (all in Juelich) and DR-2 (Riso, Denmark). Because of interest coming from the other reactor stations the codes are documented within the frame work of the IAEA Research Contract No. 3634/FG. The zero-dimensional burnup program CREMAT is used for reactor cores in which flux measurements at each individual fuel element are carried out during operation. The program yields burnup data for each fuel element and for the whole core. On the basis of these data, fuel reloading is prepared for the next operational period under consideration of the permitted minimum shut down reactivity of the system. The program BURNY calculates burnup for fuel elements inaccessible for flux measurements, but for which 'position weighting factors' have been measured/calculated during zero power operation of the core, and which are assumed to be constant in all operational situations. The code CURIAX calculates post-irradiation data for discharged fuel elements needed in their manipulation and transport. These three programs have been written for highly enriched fuel and take into account U-235 only. The modification of CREMAT for LEU Cores and its combiantion with ORIGEN is in preparation. KINIK is an inverse kinetic code and widely used for absorber rod calibration at the abovementioned research reactors. It includes a special polynomial subroutine which can easily be used in other codes. (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...

Sterilization of E. coli bacterium in a flowing N2-O2 post-discharge reactor

International Nuclear Information System (INIS)

Villeger, S; Cousty, S; Ricard, A; Sixou, M

2003-01-01

Effective destruction of Escherichia coli (E. coli) bacteria has been obtained in a flowing N 2 -O 2 microwave post-discharge reactor. The sterilizing agents are the O atoms and the UV emissions of NOβ which are produced by N and O atoms recombination in the reactor. In the following plasma conditions: pressure 5 Torr, flow rate 1 L n min -1 , microwave power of 100 W in a quartz tube of 5 mm, an O atom density of 2.5x10 15 cm -3 is measured by NO titration in the post-discharge reactor with UV emission in a N 2 -(5%)O 2 gas mixture. Full destruction of 10 13 cfu ml -1 E. coli is observed after a treatment time of 25 min. (rapid communication)

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

International Nuclear Information System (INIS)

1978-07-01

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

Safe dismantling of the SVAFO research reactors R2 and R2-0 in Sweden

International Nuclear Information System (INIS)

ARNOLD, Hans-Uwe; BROY, Yvonne; Dirk Schneider

2017-01-01

The R2 and R2-0 reactors were part of the Swedish government's research program on nuclear power from the early 1960's. Both reactors were shut down in 2005 following a decision by former operator Studsvik Nuclear AB. The decommissioning of the R2 and R2-0 reactors is divided into three phases. The first phase - awarded to AREVA - involved dismantling of the reactors and associated systems in the reactor pool, treatment of the disassembled components as well as draining, cleaning and emptying the pool. In the second phase, the pool structure itself will be dismantled, while removal of remaining reactor systems, treatment and disposal of materials and clean-up will be carried out in the third stage. The entire work is planned to be completed before the end of this decade. The paper describes the several steps of phase 1 - starting with the team building, followed by the dismantling operations and covers challenges encountered and lessons learned as well. The reactors consist of 5.400 kg aluminum, 6.000 kg stainless steel restraint structures as well as, connection elements of the mostly flanged components (1.000 kg). The most demanding - from a radiological point of view - was the R2-0 reactor that was limited to ∼ 1 m"3 construction volumes but with an extremely heterogeneous activation profile. Based on the calculated radiological entrance data and later sampling, nuclide vectors for both reactors depending on the real placement of the single component and on the material (aluminum and stainless steel) were created. Finally, for the highest activated component from R2 reactor, 85 Sv/h were measured. The dismantling principles - adopted on a safety point of view - were the following: The always protected base area of the ponds served as a flexible buffer area for waste components and packaging. Specific protections were also installed on the walls to protect them from mechanical stress which may occur during dismantling work. A specific work platform was

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 ...

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, ...

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)

Benchmark calculations for VENUS-2 MOX -fueled reactor dosimetry

International Nuclear Information System (INIS)

Kim, Jong Kung; Kim, Hong Chul; Shin, Chang Ho; Han, Chi Young; Na, Byung Chan

2004-01-01

As a part of a Nuclear Energy Agency (NEA) Project, it was pursued the benchmark for dosimetry calculation of the VENUS-2 MOX-fueled reactor. In this benchmark, the goal is to test the current state-of-the-art computational methods of calculating neutron flux to reactor components against the measured data of the VENUS-2 MOX-fuelled critical experiments. The measured data to be used for this benchmark are the equivalent fission fluxes which are the reaction rates divided by the U 235 fission spectrum averaged cross-section of the corresponding dosimeter. The present benchmark is, therefore, defined to calculate reaction rates and corresponding equivalent fission fluxes measured on the core-mid plane at specific positions outside the core of the VENUS-2 MOX-fuelled reactor. This is a follow-up exercise to the previously completed UO 2 -fuelled VENUS-1 two-dimensional and VENUS-3 three-dimensional exercises. The use of MOX fuel in LWRs presents different neutron characteristics and this is the main interest of the current benchmark compared to the previous ones

PCU arrangement of a supercritical CO{sub 2} cooled micro modular reactor

Energy Technology Data Exchange (ETDEWEB)

Kim, Seong Gu; Baik, Seungjoon; Cho, Seong Kuk; Oh, Bong Seong; Lee, Jeong Ik [KAIST, Daejeon (Korea, Republic of)

2016-05-15

As part of the SMR(Small Modular Reactor)s development effort, the authors propose a concept of supercritical CO{sub 2} (S-CO{sub 2}) cooled fast reactor combined with the S-CO{sub 2} Brayton cycle. The reactor concept is named as KAIST Micro Modular Reactor (MMR). The S-CO{sub 2} Brayton cycle has many strong points when it is used for SMR's power conversion unit. It occupies small footprints due to the compact cycle components and simple layout. Thus, a concept of one module containing the S-CO{sub 2} cooled fast reactor and power conversion system is possible. This module can be shipped via ground transportation (by trailer) or marine transportation. In this study, the authors propose a new conceptual layout for the S-CO{sub 2} cooled direct cycle while considering various issues for arranging cycle components. The new design has an improved cycle efficiency (from 31% to 34%) than the earlier version of MMR by reducing pressure drops in the heat exchangers. As a more efficient option, a recompression recuperated cycle was also designed. It improves 5% of thermal efficiency while 18tons of mass can be added in comparison to the simple recuperated cycle. Even if we adopt recompression cycle as a PCU, the weight of module (152tons) is less than the ground transportable limit (260tons)

TMI-2 reactor vessel head removal

International Nuclear Information System (INIS)

Bengel, P.R.; Smith, M.D.; Estabrook, G.A.

1984-12-01

This report describes the safe removal and storage of the Three Mile Island Unit 2 reactor vessel head. The head was removed in July 1984 to permit the removal of the plenum and the reactor core, which were damaged during the 1979 accident. From July 1982, plans and preparations were made using a standard head removal procedure modified by the necessary precautions and changes to account for conditions caused by the accident. After data acquisition, equipment and structure modifications, and training the head was safely removed and stored and the internals indexing fixture and a work platform were installed on top of the vessel. Dose rates during and after the operation were lower than expected; lessons were learned from the operation which will be applied to the continuing fuel removal operations activities

Neutronic study using oxide and nitride fuels for the Super Phenix 2 reactor

International Nuclear Information System (INIS)

Batista, J.L.; Renke, C.A.C.

1991-11-01

This report presents a neutronic analysis and a description of the Super Phenix 2 reactor, taken as reference. We present the methodology and results for cell and global reactor calculations for oxide (U O 2 - Pu O 2 ) and nitride (U N - Pu N) fuels. To conclude we compare the performance of oxide and nitride fuels for the reference reactor. (author)

Shadow corrosion evaluation in the Studsvik R2 reactor

International Nuclear Information System (INIS)

Sanders, Ch.; Lysell, G.

2000-01-01

Post-irradiation examination has shown that increased corrosion occurs when zirconium alloys are in contact with or in proximity to other metallic objects. The observations indicate an influence of irradiation from the adjacent component as the enhanced corrosion occurs as a 'shadow' of the metallic object on the zirconium surface. This phenomenon could ultimately limit the lifetime of certain zirconium alloy components in the reactor. The Studsvik R2 materials test reactor has an In-Core Autoclave (INCA) test facility especially designed for water chemistry and materials research. The INCA facility has been evaluated and found suitable for shadow corrosion studies. The R2 reactor core containing the INCA facility was modeled with the Monte Carlo N-Particle (MCNP) code in order to evaluate the electron deposition in various materials and to develop a hypothesis of the shadow corrosion mechanism. (authors)

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.

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 ...

Benchmark tests of JENDL-3.2 for thermal and fast reactors

International Nuclear Information System (INIS)

Takano, Hideki

1995-01-01

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

Radionuclide distribution in TMI-2 reactor building basement liquids and solids

International Nuclear Information System (INIS)

Horan, J.T.; McIsaac, C.V.; Keefer, D.G.

1984-01-01

As a result of the TMI-2 accident, approximately 2.46 x 10 6 L of contaminated water were released to the Reactor Building basement. The principal fission product release pathway from the damaged core was through the reactor coolant system (RCS) to the pressurizer, through the pressure-operated relief valve (PORV) on the pressurizer to the Reactor Coolant Drain Tank (RCDT), and then through the RCDT rupture disk to the Reactor Building basement. Since August 1979, a number of efforts have been made to determine the location, quantity, and composition of fission products released to the Reactor Building basement. These efforts have included sampling of the basement water and solids, the basement sump pump recirculation line, the RCDT, and visual surveys using a closed circuit television (CCTV) system. The analysis of basement samples has provided data on the physical and radioisotopic characteristics of the liquids and solids. This paper describes the sample collection techniques and discusses radiochemical analyses results

An experimental investigation of fission product release in SLOWPOKE-2 reactors

International Nuclear Information System (INIS)

Harnden, A.M.C.

1995-09-01

Increasing radiation fields due to a release of fission products in the reactor container of several SLOWPOKE-2 reactors fuelled with a highly-enriched uranium (HEU) alloy core have been observed. It is believed that these increases are associated with the fuel fabrication where a small amount of uranium-bearing material is exposed to the coolant at the end-welds of the fuel element. To investigate this phenomenon samples of reactor water and gas from the headspace above the water have been obtained and examined by gamma spectrometry methods for reactors of various burnups at the University of Toronto, Ecole Polytechnique and Kanata Isotope Production Facility. An underwater visual examination of the fuel core at Ecole Polytechnique has also provided information on the condition of the core. This report (Volume 1) summarizes the equipment, analysis techniques and results of tests conducted at the various reactor sites. The data report is published as Volume 2. (author). 30 refs., 9 tabs., 20 figs

The Oak Ridge Research Reactor: safety analysis: Volume 2, supplement 2

International Nuclear Information System (INIS)

Hurt, S.S.

1986-11-01

The Oak Ridge Research Reactor Safety Analysis was last updated via ORNL-4169, Vol. 2, Supplement 1, in May of 1978. Since that date, several changes have been effected through the change-memo system described below. While these changes have involved the cooling system, the electrical system, and the reactor instrumentation and controls, they have not, for the most part, presented new or unreviewed safety questions. However, some of the changes have been based on questions or recommendations stemming from safety reviews or from reactor events at other sites. This paper discusses those changes which were judged to be safety related and which include revisions to the syphon-break system and changes related to seismic considerations which were very recently completed. The maximum hypothetical accident postulated in the original safety analysis requires dynamic containment and filtered flow for compliance with 10CFR100 limits at the site boundary

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:

Loss of coolant analysis for the tower shielding reactor 2

International Nuclear Information System (INIS)

Radcliff, T.D.; Williams, P.T.

1990-06-01

The operational limits of the Tower Shielding Reactor-2 (TSR-2) have been revised to account for placing the reactor in a beam shield, which reduces convection cooling during a loss-of-coolant accident (LOCA). A detailed heat transfer analysis was performed to set operating time limits which preclude fuel damage during a LOCA. Since a LOCA is survivable, the pressure boundary need not be safety related, minimizing seismic and inspection requirements. Measurements of reactor component emittance for this analysis revealed that aluminum oxidized in water may have emittance much higher than accepted values, allowing higher operating limits than were originally expected. These limits could be increased further with analytical or hardware improvements. 5 refs., 7 figs

Dr. Vernon W. Hughes, 81, authority on the subatomic

CERN Multimedia

Lavietes, S

2002-01-01

"Dr. Vernon W. Hughes, a Yale physicist whose investigation of particles called muons poked holes in standard subatomic theory and provided evidence for the existence of previously undetected matter, died at Yale-New Haven Hospital last Tuesday" (1/2 page).

Dalhousie SLOWPOKE-2 reactor: A nuclear analytical chemistry facility

International Nuclear Information System (INIS)

Chatt, A.; Holzbecher, J.

1990-01-01

SLOWPOKE is an acronym for Safe Low POwer Kritical Experiment. The SOWPOKE-2 is a compact, inherently safe, swimming-pool-type reactor designed by the Atomic Energy of Canada Limited for neutron activation analysis (NAA) and isotope production. The Dalhousie University SLOWPOKE-2 reactor (DUSR) has been operating since 1976; a large beryllium reflector was added in 1986 to extend its lifetime by another 8 to 10 yr. The DUSR is generally operated at half-power with a maximum thermal flux of 1.1 x 10 12 n/cm 2 ·s in the inner pneumatic sites and that of 5.4 x 10 11 n/cm 2 ·s in the outer sites. Despite this comparatively low flux, SLOWPOKE-2 reactors have many beneficial features that are continuously being exploited at the DUSR facility for developing nuclear analytical methods for fundamental as well as applied studies. Although NAA is a well-established analytical technique, much of the activation analysis being performed in most facilities has been limited to methods using fairly long-lived nuclides. The approach at the DUSR facility has been to utilize the highly homogeneous, stable, and reproducible neutron flux to develop NAA methods based on short-lived nuclides. SLOWPOKE reactors have a fairly high epithermal neutron flux, which is being advantageously used for determining several trace elements in complex matrices. Radiochemical NAA (RNAA) methods using coprecipitation, distillation, and ion-exchange separations have been used for the determination of very low levels of several elements in biological materials

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

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

Science.gov (United States)

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

2018-03-01

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

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

International Nuclear Information System (INIS)

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

1993-01-01

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

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, ...

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.

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

International Nuclear Information System (INIS)

Greene, S.R.; Spellman, D.J.; Bevard, B.B.

1996-09-01

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative

FMDP Reactor Alternative Summary Report: Volume 2 - CANDU heavy water reactor alternative

Energy Technology Data Exchange (ETDEWEB)

Greene, S.R.; Spellman, D.J.; Bevard, B.B. [and others

1996-09-01

The Department of Energy Office of Fissile Materials Disposition (DOE/MD) initiated a detailed analysis activity to evaluate each of ten plutonium disposition alternatives that survived an initial screening process. This document, Volume 2 of a four volume report, summarizes the results of these analyses for the CANDU reactor based plutonium disposition alternative.

Dynamic simulation of the 2 MWt slowpoke heating reactor

International Nuclear Information System (INIS)

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

1982-04-01

A 2 MWt SLOWPOKE reactor, intended for commercial space heating, is being developed at the Chalk River Nuclear Laboratories. A small-signal dynamic simulation of this reactor, without closed-loop control, was developed. Basic equations were used to describe the physical phenomena in each kf the eight reactor subsystems. These equations were then linearized about the normal operation conditions and rearranged in a dimensionless form for implementation. The overall simulation is non-linear. Slow transient responses (minutes to days) of the simulation to both reactivity and temperature perturbations were measured at full power. In all cases the system reached a new steady state in times varying from 12 h to 250 h. These results illustrate the benefits of the inherent negative reactivity feedback of this reactor concept. The addition of closed-loop control using core outlet temperature as the controlled variable to move a beryllium reflector is also examined

Distribution of energy of impulses of the modernized IBR-2 REACTOR

International Nuclear Information System (INIS)

Tayibov, L.A; Mehtiyeva, R.N.; )

2011-01-01

Full text: For the modernized IBR-2 reactor there are two main reasons causing fluctuations of energy of impulses [1,3] on low power of stochastic fluctuations, on the nominal - giving rise to fluctuations of external reactance. The fluctuations of pulse energy is quite significant (20%). They affect the dynamics of the reactor, the process of regulation, starting, as well as the work of the experimental apparatus, etc. It is clear that research of fluctuation of energy of impulses has special value for the IBR-2 type reactor. Sufficient information about the statistical properties of the reactor noise gives the density distribution of the energy pulse power. We used the usual procedure of statistical analysis of time series. Calculated pulse energy of density and the parameters of this distribution.

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.

Intra HLA-D/DR region recombinant detected by primed lymphocyte typing (PLT)

DEFF Research Database (Denmark)

Jakobsen, B K; Kristensen, T; Lamm, L U

1983-01-01

The chromosome 6 markers, HLA-ABC, D, DR, MT, properdin factor Bf, and complement factors 2 (C2) and 5 (C4), were studied in three families, each of which included two HLA identical siblings, one or both of whom were known to be HLA-B: GLO recombinants. The families were also typed with primed...... lymphocyte typing (PLT) for HLA-D/DR region associated DP antigens. None of these studies gave evidence that the recombinations had occurred within the HLA region. Mixed leucocyte culture (MLC) tests within the families showed no detectable stimulation between the HLA identical siblings in two...

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.

Perbedaan Kadar LDL-kolesterol pada Pasien Diabetes Melitus Tipe 2 dengan dan tanpa Hipertensi di RS Dr. M. Djamil Padang Tahun 2011

Directory of Open Access Journals (Sweden)

Finisia Noviyanti

2015-05-01

Full Text Available AbstrakHipertensi seringkali menjadi kondisi komorbid yang menyertai diabetes melitus tipe 2. Diabetes melitus, hipertensi dan peningkatan LDL kolesterol merupakan keadaan yang sering dijumpai saling berkaitan. Tujuan penelitian ini adalah untuk melihat perbedaan kadar LDL kolesterol penderita diabetes melitus tipe 2 dengan dan tanpa hipertensi. Penelitian ini menggunakan desain cross sectional comparatif. Pengumpulan data dilakukan dengan observasi data rekam medis pasien diabetes melitus tipe 2 dengan dan tanpa hipertensi tahun 2011 di RS. Dr. M. Djamil Padang. Analisis statistik menggunakan uji chi-square dan uji t-berpasangan. Hasil penelitian menemukan kadar LDL kolesterol pada pasien diabetes melitus tipe 2 dengan hipertensi (137,56±41,43 mg/dl lebih tinggi dibandingkan tanpa hipertensi (94,39±35,36 mg/dl. Uji chi-square menunjukkkan adanya hubungan yang bermakna antara peningkatan kadar LDL kolesterol dengan kejadian hipertensi (p<0,05. Uji t-berpasangan menunjukkan bahwa adanya perbedaan bermakna kadar LDL kolesterol antara kelompok pasien diabetes melitus dengan hipertensi dan tanpa hipertensi (p<0,05. Penelitian ini menyimpulkan adanya perbedaan yang bermakna kadar LDL kolesterol pada pasien diabetes melitus tipe 2 dengan hipertensi dan tanpa hipertensi di RS. Dr. M. Djamil Padang.Kata kunci: LDL kolesterol, diabetes melitus tipe 2, hipertensi AbstractHypertension is often a comorbid conditions that accompany diabetes mellitus type 2. Diabetes mellitus, hypertension and increased LDL cholesterol is a condition that is often be found related one another. The objective of this study was to determine difference LDL cholesterol level among diabetes melitus type 2 with hypertension and without hypertension.This research used cross-sectional comparatif design. The data was collected through observation of the patient’s medical records diabetes mellitus type 2 with hypertension and without hypertension in 2011 at the hospital Dr. M

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

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.

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.)

Equipment for thermal neutron flux measurements in reactor R2

Energy Technology Data Exchange (ETDEWEB)

Johansson, E; Nilsson, T; Claeson, S

1960-04-15

For most of the thermal neutron flux measurements in reactor R2 cobalt wires will be used. The loading and removal of these wires from the reactor core will be performed by means of a long aluminium tube and electromagnets. After irradiation the wires will be scanned in a semi-automatic device.

A conceptual design of LIB fusion reactor: UTLIF(2)

International Nuclear Information System (INIS)

Madarame, Haruki; Kondo, Shunsuke; Iwata, Shuichi; Oka, Yoshiaki; Miya, Kenzo.

1984-01-01

UTLIF(2) is a conceptual design study on a light ion beam driven fusion reactor based on a concept of rod-bundle blanket. Survivability and maintainability of the first wall and the blanket are regarded as of major importance in the design. The blanket rod is composed of a thick tube which has enough stiffness, a thin wrapping wall which receives high heat flux, and liquid lithium which breeds tritium and removes generated heat. The rod can be pulled out from the outside of the reactor vessel, hence the replacement is very easy. Nuclear and thermal analysis have been made and the performance of the reactor has been shown to be satisfactory. (author)

The BR2 materials testing reactor. Past, ongoing and under-study upgradings

Energy Technology Data Exchange (ETDEWEB)

Baugnet, J M; Roedt, Ch de; Gubel, P; Koonen, E [Centre d' Etude de I' Energie Nucleaire, Studiecentrum voor Kernenergie, C.E.N./S.C.K., Mol (Belgium)

1990-05-01

The BR2 reactor (Mol, Belgium) is a high-flux materials testing reactor. The fuel is 93% {sup 235}U enriched uranium. The nominal power ranges from 60 to 100 MW. The main features of the design are the following: 1) maximum neutron flux, thermal: 1.2 x 10{sup 15} n/cm{sup 2} s; fast (E > 0.1 MeV) : 8.4 x 10{sup 14} n /cm{sup 2} s; 2) great flexibility of utilization: the core configuration and operation mode can be adapted to the experimental loading; 3) neutron spectrum tailoring; 4) availability of five 200 mm diameter channels besides the standard channels (84 mm diameter); 5) access to the top and bottom covers of the reactor authorizing the irradiation of loops. The reactor is used to study the behaviour of fuel elements and structural materials intended for future nuclear power stations of several types (fission and fusion). Irradiations are carried out in connection with performance tests up to very high burn-up or neutron fluence as well as for safety experiments, power cycling experiments, and generally speaking, tests under off-normal conditions. Irradiations for nuclear transmutation (production of high specific activity radio-isotopes and transplutonium elements), neutron-radiography, use of beam tubes for physics studies, and gamma irradiations are also carried out. The BR2 is used in support of Belgian programs, at the request of utilities, industry and universities and in the framework of international agreements. The paper reviews the past and ongoing upgrading and enhancement of reactor capabilities as well as those under study or consideration, namely with regard to: reactor equipment, fuel elements, irradiation facilities, reactor operation conditions and long-term strategy. (author)

TiO2 Solar Photocatalytic Reactor Systems: Selection of Reactor Design for Scale-up and Commercialization—Analytical Review

Directory of Open Access Journals (Sweden)

Yasmine Abdel-Maksoud

2016-09-01

Full Text Available For the last four decades, viability of photocatalytic degradation of organic compounds in water streams has been demonstrated. Different configurations for solar TiO2 photocatalytic reactors have been used, however pilot and demonstration plants are still countable. Degradation efficiency reported as a function of treatment time does not answer the question: which of these reactor configurations is the most suitable for photocatalytic process and optimum for scale-up and commercialization? Degradation efficiency expressed as a function of the reactor throughput and ease of catalyst removal from treated effluent are used for comparing performance of different reactor configurations to select the optimum for scale-up. Comparison included parabolic trough, flat plate, double skin sheet, shallow ponds, shallow tanks, thin-film fixed-bed, thin film cascade, step, compound parabolic concentrators, fountain, slurry bubble column, pebble bed and packed bed reactors. Degradation efficiency as a function of system throughput is a powerful indicator for comparing the performance of photocatalytic reactors of different types and geometries, at different development scales. Shallow ponds, shallow tanks and fountain reactors have the potential of meeting all the process requirements and a relatively high throughput are suitable for developing into continuous industrial-scale treatment units given that an efficient immobilized or supported photocatalyst is used.

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.

Planned Scientific programs around the Triga Mark 2 Reactor

International Nuclear Information System (INIS)

Majah, M Ibn.

2007-01-01

Full text: Nuclear techniques have been introduced to Morocco since the sixties. After the energy crisis of 1973, Morocco decides to create the National Center for Energy Sciences and Nuclear Techniques (CNESTEN) under the supervision of the Ministry of high Education and Research, with a research commercial and support vocation. CNESTEN is in charge of promoting nuclear application, to act as technical support for the authorities and to prepare the technological basis for nuclear power option. In 1998, CNESTEN started the construction of Nuclear Research Centre. The on going activities cover many sectors : earth and environmental sciences, high energy physics, safety and security, waste management. In 2001, CNESTEN started the construction of a 2MW TRiga Mark 2 Reactor, with the possibility to increase the power to 3 MW. The construction was achieved in January 2007. The operation of the reactor is expected for April 2007. The program of the utilization of the reactor was established with th contribution of the university and with the assistance of IAEA. Some of the experimental set-up installed around the reactor have been designed. CNESTEN has developed cooperation with Nuclear research centres from other countries and is receiving visitors and trainees mainly through the IAEA [fr

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

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:

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

Power noise spectrum classification in the problem of the IBR-2 reactor

International Nuclear Information System (INIS)

Bargel, M.; Kitowski, J.; Pepelyshev, Yu.N.

1988-01-01

The classification spectrum results of random fluctuations in the IBR-2 energy pulse are presented. The work is performed for the application of the obtained results to the reactor diagnostics and the study of its noise uncontrolled states. For classification of the spectra the method of pattern recognition based upon the ISODATA heuristic algorithm is used. It is shown that a set of noise uncontrolled reactor states, registered during the reactor operation period at power of 0.4-2 MVt with the first variant of moving reflector (1983-1986) is formed into 4(5) most typical states. Each of the states corresponds to the general conditions of the reactor core cooling and provides the normal work of the moving reflector. However, these states differ in coolant flow, power level and peculiarities of the moving reflector rotation regime. One type of anomal power noise, connected with some disorder in the moving reflctor work, is isolated. This work also presents the possibility of control over the state of moving reflectors according to the change in the amplitude of power oscillations at some frequences. The reactor noise classification results can be used as the data bank for the IBR-2 reactor diagnostic system

Research reactor FR2 - 20 years chemical and radiochemical measurements

International Nuclear Information System (INIS)

Feuerstein, H.; Graebner, H.; Oschinski, J.; Hoffmann, W.; Beyer, J.

1986-09-01

The FR2 has been a D 2 O cooled and moderated research reactor with a thermal output of 44 MW. It was in operation from 1961 to 1981. Because of the operating conditions of the reactor, only a small number of routine measurements were performed. For these however special techniques had to be developed. During the 20 years of operation a number of special events occured or have been observed, sometimes with very amazing results, e.g. the 'aceton effect'. This report describes the chemical and radiochemical conditions of the reactor systems, as well as the results of the surveilance work. Not described are measurements for the many experiments. The last chapter gives in a short form a description of the most unusual events and observations. (orig.) [de

Venting krypton-85 from the Three Mile Island Unit 2 reactor building

International Nuclear Information System (INIS)

Burton, H.M.

1981-01-01

To permit the less restricted access to the reactor building necessary to maintain instrumentation and equipment, and to proceed towad the total decontamination of the facility, General Public Utilities, operators of the facility referred to hereafter as GPU, asked the United States Nuclear Regulatory Commission, or NRC, for permission to remove the 85 Kr from the reactor building by venting it to the environment. GPU supported their request with the Safety Analysis and Environmental Assessment Report on the proposed reactor building venting plan. On June 12, 1980, after seven months of licensing deliberations and numerous public hearings, the NRC granted GPU's request. The actual venting took place between June 28 and July 11, 1980. This report presents an overview of the detailed effort involved in the TMI-2 reactor building venting program. The findings reported here are condensed from a published report entitled TMI-2 Reactor Building Purge--Kr-85 Venting

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 ...

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:

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:

Research on economics and CO2 emission of magnetic and inertial fusion reactors

International Nuclear Information System (INIS)

Mori, Kenjiro; Yamazaki, Kozo; Oishi, Tetsutarou; Arimoto, Hideki; Shoji, Tatsuo

2011-01-01

An economical and environment-friendly fusion reactor system is needed for the realization of attractive power plants. Comparative system studies have been done for magnetic fusion energy (MFE) reactors, and been extended to include inertial fusion energy (IFE) reactors by Physics Engineering Cost (PEC) system code. In this study, we have evaluated both tokamak reactor (TR) and IFE reactor (IR). We clarify new scaling formulas for cost of electricity (COE) and CO 2 emission rate with respect to key design parameters. By the scaling formulas, it is clarified that the plant availability and operation year dependences are especially dominant for COE. On the other hand, the parameter dependences of CO 2 emission rate is rather weak than that of COE. This is because CO 2 emission percentage from manufacturing the fusion island is lower than COE percentage from that. Furthermore, the parameters dependences for IR are rather weak than those for TR. Because the CO 2 emission rate from manufacturing the laser system to be exchanged is very large in comparison with CO 2 emission rate from TR blanket exchanges. (author)

Development of a TiO2-coated optical fiber reactor for water decontamination

International Nuclear Information System (INIS)

Danion, A.

2004-09-01

The objective of this study was to built and to study a photo-reactor composed by TiO 2 -coated optical fibers for water decontamination. The physico-chemical characteristics and the optical properties of the TiO 2 coating were first studied. Then, the influences of different parameters as the coating thickness, the coating length and the coating volume were investigated both on the light transmission in the TiO 2 - coated fiber and on the photo-catalytic activity of the fiber for a model compound (malic acid). The photo-catalytic degradation of malic acid was optimized using the experimental design methodology allowing to build a multi-fiber reactor comprising 57 optical fibers. The photo-degradation of malic acid was conducted in the multi-fiber reactor and it was demonstrated that the multi-fiber reactor was more efficient than the single-fiber reactor at the same fibers density. Finally, the multi-fiber reactor was applied to the photo-degradation of a fungicide, called fenamidone, and a degradation pathway was proposed. (author)

Loss and benefit of DR system in mass screening for upper GI-tracts. Comparison with an II-TV based DR system and 100-mm roll-film system

International Nuclear Information System (INIS)

Ogura, Toshihiro; Fujita, Hiroshi.

1995-01-01

A 2048 x 2048 matrix II-TV based digital radiography (DR) system, a fully digital imaging system with diagnosis on the CRT monitor, had been introduced to Cancer Institute Hospital for the GI-tracts examinations since January 1990. Furthermore, we had applied it to the mass screening of upper GI-tract since November 1992. In the present study, a retrospective study on clinical evaluation and features of the DR system for the mass screening were investigated and compared with the screening data taken by conventional 100-mm roll-film technique in the previous year. The loss ratios and appearance of the mucosal patterns in upper gastric images were studied as well. Also determined was the reading time of those images in the mass screening situation. It was found that the loss ratio on the subject image information in 100-mm roll-film images was smaller than that in DR images. However, the DR images processed by windowing technique provided the perfect information without partially over or under density area. It was shown that the clinical image quality greatly depended on the radiographic technique by radiologists or technologists rather than on the imaging modality itself employed; even in II/TV-DR system, the radiographic technique is important. Because of some issues, including the size of CRT monitor, eyestrain for CRT monitor, and windowing operation regard to reading system, the reading time of CRT images was 1.44-2.05 times longer than that of 100-mm roll-film images. (author)

TMI-2 reactor-vessel head removal and damaged-core-removal planning

International Nuclear Information System (INIS)

Logan, J.A.; Hultman, C.W.; Lewis, T.J.

1982-01-01

A major milestone in the cleanup and recovery effort at TMI-2 will be the removal of the reactor vessel closure head, planum, and damaged core fuel material. The data collected during these operations will provide the nuclear power industry with valuable information on the effects of high-temperature-dissociated coolant on fuel cladding, fuel materials, fuel support structural materials, neutron absorber material, and other materials used in reactor structural support components and drive mechanisms. In addition, examination of these materials will also be used to determine accident time-temperature histories in various regions of the core. Procedures for removing the reactor vessel head and reactor core are presented

The sensitivity and specificity of one field non-mydriatic digital fundus photography for DR screening

Directory of Open Access Journals (Sweden)

Bin-Bin Li

2013-07-01

Full Text Available AIM:To evaluate the sensitivity and specificity of one-field non-mydriatic digital fundus photography and direct ophthalmoscopy for diabetic retinopathy(DRscreening, compared with fundus fluorescein angiography( FFA .METHODS:All 93 patients of type 1 or 2 diabetic who have underwent one-field non-mydriatic digital fundus photography, and direct ophthalmoscopy with dilation of their pupils, and FFA by ophthalmologists. The sensitivity and specificity of one-field non-mydriatic digital fundus photography and direct ophthalmoscopy were calculated respectively, compared with FFA.RESULTS: The sensitivity and specificity of one-field non-mydriatic digital fundus photography for detection of any DR were 80.4% and 94.7%; The sensitivity and specificity of direct ophthalmoscopy for detection of any DR were 64.2% and 84.2%; After the standard for referable DR being lowered down to the moderate non-proliferative diabetic retinopathy(M-NPDR, the sensitivity and specificity of non-mydriatic digital fundus photography for detection were 88.9% and 98.4%, the sensitivity and specificity of direct ophthalmoscopy for detection were 71.5% and 96.7%.CONCLUSION: One-field non-mydriatic digital fundus photography is an effective method for DR screening.

[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.

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”...

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)

The WIRED Survey. 2; Infrared Excesses in the SDSS DR7 White Dwarf Catalog

Science.gov (United States)

Debes, John H.; Hoard, D. W.; Wachter, Stefanie; Leisawitz, David T.; Cohen, Martin

2011-01-01

With the launch of the Wide-field Infrar.ed Survey Explorer (WISE), a new era of detecting planetary debris and brown dwarfs (BDs) around white dwarfs (WDs) has begun with the WISE InfraRed Excesses around Degenerates (WIRED) Survey. The WIRED Survey is sensitive to substellar objects and dusty debris around WDs out to distances exceeding 100 pc, well beyond the completeness level of local WDs. In this paper, we present a cross-correlation of the preliminary Sloan Digital Sky Survey (SDSS) Data Release 7 (DR7) WD catalog between the WISE, Two-Micron All Sky Survey (2MASS), UKIRT Infrared Deep Sky Survey (UKIDSS), and SDSS DR7 photometric catalogs. From -18,000 input targets, there are WISE detections comprising 344 "naked" WDs (detection of the WD photosphere only), 1020 candidate WD+M dwarf binaries, 42 candidate WD+BD systems, 52 candidate WD+dust disk systems, and 69 targets with indeterminate infrared excess. We classified all of the detected targets through spectral energy distribution model fitting of the merged optical, near-IR, and WISE photometry. Some of these detections could be the result of contaminating sources within the large (approx. 6") WISE point-spread function; we make a preliminary estimate for the rates of contamination for our WD+BD and WD+disk candidates and provide notes for each target of interest. Each candidate presented here should be confirmed with higher angular resolution infrared imaging or infrared spectroscopy. We also present an overview of the observational characteristics of the detected WDs in the WISE photometric bands, including the relative frequencies of candidate WD+M, WD+BD, and WD+disk systems.

Proceedings of the 1992 topical meeting on advances in reactor physics. Volume 2

Energy Technology Data Exchange (ETDEWEB)

1992-04-01

This document, Volume 2, presents proceedings of the 1992 Topical Meeting on Advances in Reactor Physics on March 8--11, 1992 at Charleston, SC. Session topics were as follows: Transport Theory; Fast Reactors; Plant Analyzers; Integral Experiments/Measurements & Analysis; Core Computational Systems; Reactor Physics; Monte Carlo; Safety Aspects of Heavy Water Reactors; and Space-Time Core Kinetics. The individual reports have been cataloged separately. (FI)

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

DR Experiments in the 60 years since the Bates paper

International Nuclear Information System (INIS)

Johnsen, Rainer

2011-01-01

About 60 years have passed since David Bates in a 1950 Physical Review Letter to the Editor first clarified the dissociative recombination mechanism (DR) of molecular ions and provided the conceptual basis for the process that plays an important role in the ionospheres of Earth and other planets, the interstellar medium, and electrical discharges. His visionary (and characteristically 'terse') thumbnail sketch of the DR mechanism only hinted at the subtleties that have kept atomic theorists and experimentalists busy for many years. In my talk, I will focus on experiments on N 2 + recombination, beginning with plasma afterglows, and then move on to the 'after'-afterglow period that is now dominated by the powerful storage-ring methods.

A theoretical analysis of methanol synthesis from CO2 and H2 in a ceramic membrane reactor

NARCIS (Netherlands)

Gallucci, F.; Basile, A.

2007-01-01

In this theoretical work the CO2 conversion into methanol in both a traditional reactor (TR) and a membrane reactor (MR) is considered. The purpose of this study was to investigate the possibility of increasing CO2 conversion into methanol with respect to a TR. A zeolite MR, able to combine

Cronos 2: a neutronic simulation software for reactor core calculations

International Nuclear Information System (INIS)

Lautard, J.J.; Magnaud, C.; Moreau, F.; Baudron, A.M.

1999-01-01

The CRONOS2 software is that part of the SAPHYR code system dedicated to neutronic core calculations. CRONOS2 is a powerful tool for reactor design, fuel management and safety studies. Its modular structure and great flexibility make CRONOS2 an unique simulation tool for research and development for a wide variety of reactor systems. CRONOS2 is a versatile tool that covers a large range of applications from very fast calculations used in training simulators to time and memory consuming reference calculations needed to understand complex physical phenomena. CRONOS2 has a procedure library named CPROC that allows the user to create its own application environment fitted to a specific industrial use. (authors)

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

Science.gov (United States)

1999-01-01

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

Sirsat, Dr Satyavati Motiram

Indian Academy of Sciences (India)

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

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 ...

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

CERN Multimedia

Patrice Loïez

2001-01-01

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

Abd-Allah, Dr. Adel-Gamil

African Journals Online (AJOL)

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

CD25 targeted therapy of chemotherapy resistant leukemic stem cells using DR5 specific TRAIL peptide

Directory of Open Access Journals (Sweden)

Jayaprakasam Madhumathi

2017-03-01

Full Text Available Chemotherapy resistant leukemic stem cells (LSCs are being targeted as a modern therapeutic approach to prevent disease relapse. LSCs isolated from methotrexate resistant side population (SP of leukemic cell lines HL60 and MOLT4 exhibited high levels of CD25 and TRAIL R2/DR5 which are potential targets. Recombinant immunotoxin conjugating IL2α with TRAIL peptide mimetic was constructed for DR5 receptor specific targeting of LSCs and were tested in total cell population and LSCs. IL2-TRAIL peptide induced apoptosis in drug resistant SP cells from cell lines and showed potent cytotoxicity in PBMCs derived from leukemic patients with an efficacy of 81.25% in AML and 100% in CML, ALL and CLL. IL2-TRAIL peptide showed cytotoxicity in relapsed patient samples and was more effective than TRAIL or IL2-TRAIL proteins. Additionally, DR5 specific IL2-TRAIL peptide was effective in targeting and killing LSCs purified from cell lines [IC50: 952 nM in HL60, 714 nM in MOLT4] and relapsed patient blood samples with higher efficacy (85% than IL2-TRAIL protein (46%. Hence, CD25 and DR5 specific targeting by IL2-TRAIL peptide may be an effective strategy for targeting drug resistant leukemic cells and LSCs.

Set of rules SOR 2 reactor site criteria

International Nuclear Information System (INIS)

1976-06-01

The purpose of this set of rules is to describe criteria which guide the Director in his evaluation of the suitability of proposed sites for stationary power and testing reactors subject to SOR 2. (B.G.)

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-01-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testings of CENDL-2 and ENDF/B-6. (4 tabs., 2 figs.)

Groundwater Monitoring Plan for the Reactor Technology Complex Operable Unit 2-13

International Nuclear Information System (INIS)

Richard P. Wells

2007-01-01

This Groundwater Monitoring Plan describes the objectives, activities, and assessments that will be performed to support the on-going groundwater monitoring requirements at the Reactor Technology Complex, formerly the Test Reactor Area (TRA). The requirements for groundwater monitoring were stipulated in the Final Record of Decision for Test Reactor Area, Operable Unit 2-13, signed in December 1997. The monitoring requirements were modified by the First Five-Year Review Report for the Test Reactor Area, Operable Unit 2-13, at the Idaho National Engineering and Environmental Laboratory to focus on those contaminants of concern that warrant continued surveillance, including chromium, tritium, strontium-90, and cobalt-60. Based upon recommendations provided in the Annual Groundwater Monitoring Status Report for 2006, the groundwater monitoring frequency was reduced to annually from twice a year

Homogeneous fast reactor benchmark testing of CENDL-2 and ENDF/B-6

International Nuclear Information System (INIS)

Liu Guisheng

1995-11-01

How to choose correct weighting spectrum has been studied to produce multigroup constants for fast reactor benchmark calculations. A correct weighting option makes us obtain satisfying results of K eff and central reaction rate ratios for nine fast reactor benchmark testing of CENDL-2 and ENDF/B-6. (author). 8 refs, 2 figs, 4 tabs

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

Directory of Open Access Journals (Sweden)

Rebecca J. Travnichek

2011-04-01

Full Text Available

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

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...

An experimental investigation of fission product release in SLOWPOKE-2 reactors - Data report

International Nuclear Information System (INIS)

Harnden, A.M.C.

1995-09-01

The results of an investigation into the release of fission products from SLOWPOKE-2 reactors fuelled with a highly-enriched uranium alloy core are detailed in Volume 1. This data report (Volume 2) contains plots of the activity concentrations of the fission products observed in the reactor container at the University of Toronto, Ecole Polytechnique and the Kanata Isotope Production Facility. Release rates from the reactor container water to the gas headspace are also included. (author)

Safety assessments relating to the use of new fuels in research reactors: application to the case of FRM 2 reactor fuel

International Nuclear Information System (INIS)

Abou Yehia, H.; Bars, G.; Tran Dai

2001-01-01

After giving a brief reminder of the procedure applied in France for the licensing of the use of a new fuel type or design in a research reactor, we outline the main safety aspects associated with such a modification. Finally, by way of an example, we focus on the safety assessment relating to the IRIS irradiation device used in SILOE reactor, in particular for the qualification of the fuel dedicated to FRM II reactor of the Technical University of Munich. This qualification was carried out on a U 3 Si 2 fuel plate enriched to about 90 % in weight of 235 U and containing 1.5 g of uranium per cm 3 . The evaluation performed by the IPSN for GRS did not call into question the choice of U 3 Si 2 fuel plates for the FRM-II reactor. (authors)

Thermal neutron flux distribution in ET-RR-2 reactor thermal column

Directory of Open Access Journals (Sweden)

Imam Mahmoud M.

2002-01-01

Full Text Available The thermal column in the ET-RR-2 reactor is intended to promote a thermal neutron field of high intensity and purity to be used for following tasks: (a to provide a thermal neutron flux in the neutron transmutation silicon doping, (b to provide a thermal flux in the neutron activation analysis position, and (c to provide a thermal neutron flux of high intensity to the head of one of the beam tubes leading to the room specified for boron thermal neutron capture therapy. It was, therefore, necessary to determine the thermal neutron flux at above mentioned positions. In the present work, the neutron flux in the ET-RR-2 reactor system was calculated by applying the three dimensional diffusion depletion code TRITON. According to these calculations, the reactor system is composed of the core, surrounding external irradiation grid, beryllium block, thermal column and the water reflector in the reactor tank next to the tank wall. As a result of these calculations, the thermal neutron fluxes within the thermal column and at irradiation positions within the thermal column were obtained. Apart from this, the burn up results for the start up core calculated according to the TRITION code were compared with those given by the reactor designer.

Apollo-L2, an advanced fuel tokamak reactor utilizing direct conversion

International Nuclear Information System (INIS)

Emmert, G.A.; Kulcinski, G.L.; Blanchard, J.P.; El-Guebaly, L.A.; Khater, H.Y.; Santarius, J.F.; Sawan, M.E.; Sviatoslavsky, I.N.; Wittenberg, L.J.; Witt, R.J.

1989-01-01

A scoping study of a tokamak reactor fueled by a D- 3 He plasma is presented. The Apollo D- 3 He tokamak capitalizes on recent advances in high field magnets (20 T) and utilizes rectennas to convert the synchrotron radiation directly to electricity. The low neutron wall loading (0.1 MW/m 2 ) permits a first wall lasting the life of the plant and enables the reactor to be classified as inherently safe. The cost of electricity is less than that from a similar power level DT reactor. 10 refs., 1 fig., 4 tabs

Reactor containment and reactor safety in the United States

International Nuclear Information System (INIS)

Kouts, H.

1986-01-01

The reactor safety systems of two reactors are studied aiming at the reactor containment integrity. The first is a BWR type reactor and is called Peachbottom 2, and the second is a PWR type reactor, and is called surry. (E.G.) [pt

China's Investment Leade Dr, Alyce Su

Institute of Scientific and Technical Information of China (English)

2010-01-01

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

Rapid data acquisition from the safety system of the FRJ-2 reactor

International Nuclear Information System (INIS)

Inhoven, H.

1980-06-01

The central department for research reactors (ZFR) of the Juelich Nuclear Research Centre (KFA) is operating the reactors FRJ-1 (MERLIN) and FRJ-2 (DIDO) since 1962. In 1976, a Siemens 330 computer has been put into operation especially for the processing of data from the DIDO reactor, followed by another computer of the same type for the purpose of processing data from the ZFR department in general. The present report is a result of the work investigating 'Data acquisition and data processing in the FRJ-2' and primarily discusses the complex of 'fast analog and binary signals'. The activities in this field of work have been and still are mainly concerned with general problems encountered in adapting a currently 14-year-old reactor system to a digital computer, namely problems such as data decoupling in the safety system of the reactor, data acquisition using the CAMAC system, data transfer via an 'extended branch', data acquisition software as core-resident programs, temporary storage as common data, interpreting software as peripheral - storage - resident programs. (orig./WB) [de

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies.

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

The Reactor Physics and Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis on reactor fuel. This expertise is applied within the Reactor Physics and MYRRHA Research Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments. Progress and achievements in 1999 in the following areas are reported on: (1) investigations on the use of military plutonium in commercial power reactors; (2) neutron and gamma calculations performed for BR-2 and for other reactors; (3) the updating of neutron and gamma cross-section libraries; (4) the implementation of reactor codes; (6) the management of the UNIX workstations; and (6) fuel cycle studies

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

Science.gov (United States)

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

Estimation of power feedback parameters of pulse reactor IBR-2M on transients

International Nuclear Information System (INIS)

Pepyolyshev, Yu.N.; Popov, A.K.

2013-01-01

Parameters of the IBR-2M reactor power feedback (PFB) on a model of the reactor dynamics by mathematical treatment of two registered transients are estimated. Frequency characteristics and the pulse transient characteristics corresponding to these PFB parameters are calculated. PFB parameters received thus can be considered as their express tentative estimation as real measurements in this case occupy no more than 30 minutes. Total PFB is negative at 1 and 2 MW. At the received estimations of PFB parameters in a self-regulation mode it is possible to consider the stability margins of the IBR-2M reactor satisfactory

Independent CO2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, Task 2.50.05

International Nuclear Information System (INIS)

Stojic, M.; Pavicevic, M.

1964-01-01

This report contains the following volumes V and VI of the Project 'Independent CO 2 loop for cooling the samples irradiated in RA reactor vertical experimental channels': Design project of the dosimetry control system in the independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels, and Safety report for the Independent CO 2 loop for cooling the samples irradiated in the RA reactor vertical experimental channels [sr

PSA Level 2 activities for RBMK reactors

International Nuclear Information System (INIS)

Gubler, R.

1998-01-01

Probabilistic safety analyses (PSAs) of the boiling water graphite moderated pressure tube reactors (RBMKs) have been developed only recently and they are limited to Level 1. Activities at the IAEA were first motivated because of the difficulties to characterize core damage for RBMK reactors. Core damage probability is used in documents of the IAEA as a convenient single valued measure, for example for probabilistic safety criteria. The limited number of PSAs that have been completed for the RBMK reactors have shown that several special features of these channel type reactors necessitate revisiting of the characterization of core damage for these reactors. Furthermore, it has become increasingly evident that detailed deterministic analysis of DBAs and beyond design basis accidents reveal considerable insights into RBMK response to various accident conditions. These analyses can also help in better characterizing the outstanding phenomenological uncertainties, improved EOPs and AM strategies, including potential risk-beneficial accident negative backfits. The deterministic efforts should be focused first on elucidating accident progression processes and phenomena, and second on finding, qualifying and implementing procedures to minimize the risk of severe accident states The IAEA PSA procedures were mainly developed in New of vessel type LWRs, and would therefore require extensions to make them directly applicable. to channel type reactors. (author) (author)

Studsvik's R2 reactor - Review of activities

Energy Technology Data Exchange (ETDEWEB)

Grounes, Mikael; Tomani, Hans; Graeslund, Christian; Rundquist, Hans; Skoeld, Kurt [Studsvik Nuclear AB, Nykoeping (Sweden)

1993-07-01

A general description of the R2 reactor, its associated facilities and its history is given. The facilities and range of work are described for the following types of activities: fuel testing, materials testing, neutron transmutation doping of silicon, activation analysis, radioisotope production and basic research including thermal neutron scattering, nuclear chemistry and neutron capture radiography. (author)

Decommissioning of reactor facilities (2). Required technology

International Nuclear Information System (INIS)

Yanagihara, Satoshi

2014-01-01

Decommissioning of reactor facilities was planned to perform progressive dismantling, decontamination and radioactive waste disposal with combination of required technology in a safe and economic way. This article outlined required technology for decommissioning as follows: (1) evaluation of kinds and amounts of residual radioactivity of reactor facilities with calculation and measurement, (2) decontamination technology of metal components and concrete structures so as to reduce worker's exposure and production of radioactive wastes during dismantling, (3) dismantling technology of metal components and concrete structures such as plasma arc cutting, band saw cutting and controlled demolition with mostly remote control operation, (3) radioactive waste disposal for volume reduction and reuse, and (4) project management of decommissioning for safe and rational work to secure reduction of worker's exposure and prevent the spreading of contamination. (T. Tanaka)

Reproduction of the PSBR reactor with Exterminator-2; Reproduccion del reactor PSBR con exterminador-2

Energy Technology Data Exchange (ETDEWEB)

Aguilar H, F. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1983-08-15

To reproduce the reactor PSBR reported in (1), with the available version of the Exterminator-II in the ININ, they took the dimensions, composition specifications, effective sections of the different compositions (excepting those of the central thimble and of the moderator), the K{sub eff} and the factors of power (FP) for the different burners. Based on the comparison of the K{sub eff} and of the FP obtained with those reported the precision it is determined before in the reproduction of the reactor mentioned. (Author)

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

International Nuclear Information System (INIS)

Carlson, R.A.

2005-01-01

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

Production of Sn-117m in the BR2 high-flux reactor.

Science.gov (United States)

Ponsard, B; Srivastava, S C; Mausner, L F; Russ Knapp, F F; Garland, M A; Mirzadeh, S

2009-01-01

The BR2 reactor is a 100MW(th) high-flux 'materials testing reactor', which produces a wide range of radioisotopes for various applications in nuclear medicine and industry. Tin-117m ((117m)Sn), a promising radionuclide for therapeutic applications, and its production have been validated in the BR2 reactor. In contrast to therapeutic beta emitters, (117m)Sn decays via isomeric transition with the emission of monoenergetic conversion electrons which are effective for metastatic bone pain palliation and radiosynovectomy with lesser damage to the bone marrow and the healthy tissues. Furthermore, the emitted gamma photons are ideal for imaging and dosimetry.

Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) are compared

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

This article compares the 2 types of light water reactors that are used to produce electricity: the Pressurized Water Reactor (PWR) and the Boiling Water Reactor (BWR). Historically the BWR concept was developed after the PWR concept. Today 80% of light water reactors operating in the world are of PWR-type. This comparison is comprehensive and detailed. First the main technical features are reviewed and compared: reactor architecture, core and fuel design, reactivity control, reactor vessel, cooling systems and reactor containment. Secondly, various aspects concerning reactor operations like reactor control, fuel management, maintenance, inspections, radiation protection, waste generation and reactor reliability are presented and compared for both reactors. As for the issue of safety, it is highlighted that the accidental situations are too different for the 2 reactors to be compared. The main features of reactor safety are explained for both reactors

Sproglige drømmerier

DEFF Research Database (Denmark)

Farø, Ken Joensen

2015-01-01

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

Proceedings of 2. Yugoslav symposium on reactor physics, Part 1, Herceg Novi (Yugoslavia), 27-29 Sep 1966

International Nuclear Information System (INIS)

1966-01-01

This Volume 1 of the Proceedings of 2. Yugoslav symposium on reactor physics includes nine papers dealing with the following topics: reactor kinetics, reactor noise, neutron detection, methods for calculating neutron flux spatial and time dependence in the reactor cores of both heavy and light water moderated experimental reactors, calculation of reactor lattice parameters, reactor instrumentation, reactor monitoring systems; measuring methods of reactor parameters; reactor experimental facilities

Comparative study between fluidized bed and fixed bed reactors in methane reforming with CO2 and O2 to produce syngas

International Nuclear Information System (INIS)

Jing Qiangshan; Lou Hui; Mo Liuye; Zheng Xiaoming

2006-01-01

Reforming of methane with carbon dioxide and oxygen was investigated over Ni/MgO-SiO 2 catalysts using fixed bed and fluidized bed reactors. The conversions of CH 4 and CO 2 in a fluidized bed reactor were close to thermodynamic equilibrium. The activity and stability of the catalyst in the fixed bed reactor were lower than that in the fluidized bed reactor due to carbon deposition and nickel sintering. TGA and TEM techniques were used to characterize the spent catalysts. The results showed that a lot of whisker carbon was found on the catalyst in the rear of the fixed bed reactor, and no deposited carbon was observed on the catalysts in the fluidized bed reactor after reaction. It is suggested that this phenomenon is related to a permanent circulation of catalyst particles between the oxygen rich and oxygen free zones. That is, fluidization of the catalysts in the fluidized bed reactor favors inhibiting deposited carbon and thermal uniformity in the reactor

Benchmark testing of Canadol-2.1 for heavy water reactor

International Nuclear Information System (INIS)

Liu Ping

1999-01-01

The new version evaluated nuclear data library of ENDF-B 6.5 has been released recently. In order to compare the quality of evaluated nuclear data CENDL-2.1 with ENDF-B 6.5, it is necessary to do benchmarks testing for them. In this work, CENDL-2.1 and ENDF-B 6.5 were used to generated the WIMS-69 group library respectively, and benchmarks testing was done for the heavy water reactor, using WIMS5A code. It is obvious that data files of CENDL-2.1 is better than that of old WIMS library for the heavy water reactors calculations, and is in good agreement with those of ENDF-B 6.5

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).

Oxygen suppression in boiling water reactors. Phase 2. Annual report 1981, December 2, 1980-December 31, 1981

International Nuclear Information System (INIS)

Burley, E.L.

1982-07-01

A hydrogen addition test will be performed in the Dresden-2 reactor of Commonwealth Edison Company during 1982. Up to 2 ppM hydrogen will be added to and dissolved in the reactor feedwater to reverse the radiolysis reaction in the reactor core and suppress oxgen concentration in the primary coolant. At low oxygen levels the propensity of stressed and sensitized 304 stainless steel toward intergranular stress corrosion cracking is greatly reduced. The test will answer outstanding questions and uncertainties in the areas of water chemistry, equipment design and materials performance. Nine special sample facilities will be prepared in the primary coolant, main stream, feedwater/condensate, and offgas systems. Instrumentation will be available to measure hydrogen, oxygen, conductivity, pH, soluble and insoluble corrosion products, and electrochemical potentials. In addition, an autoclave in which confirming constant extension rate tests can be conducted in reactor water will be provided

Characterization of fuel distributions in the Three-Mile Island Unit 2 (TMI-2) reactor system by neutron and gamma-ray dosimetry

International Nuclear Information System (INIS)

Gold, R.; Roberts, J.H.; Ruddy, F.H.; Preston, C.C.; McNeece, J.P.; Kaiser, B.J.; McElroy, W.N.

1984-04-01

The resolution of technical issues generated by the accident at Three-Mile Island Unit 2 (TMI-2) will inevitably be of long range benefit. Determination of the fuel debris dispersal in the TMI-2 reactor system represents a major technical issue. In reactor recovery operations, such as for the safe handling and final disposal of TMI-2 waste, quantitative fuel assessments are being conducted throughout the reactor core and primary coolant system

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, ...

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

International Nuclear Information System (INIS)

Bissani, M; O'Kelly, D S

2006-01-01

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to provide color-enhanced gemstones but is

Joint Assessment of ETRR-2 Research Reactor Operations Program, Capabilities, and Facilities

Energy Technology Data Exchange (ETDEWEB)

Bissani, M; O' Kelly, D S

2006-05-08

A joint assessment meeting was conducted at the Egyptian Atomic Energy Agency (EAEA) followed by a tour of Egyptian Second Research Reactor (ETRR-2) on March 22 and 23, 2006. The purpose of the visit was to evaluate the capabilities of the new research reactor and its operations under Action Sheet 4 between the U.S. DOE and the EAEA, ''Research Reactor Operation'', and Action Sheet 6, ''Technical assistance in The Production of Radioisotopes''. Preliminary Recommendations of the joint assessment are as follows: (1) ETRR-2 utilization should be increased by encouraging frequent and sustained operations. This can be accomplished in part by (a) Improving the supply-chain management for fresh reactor fuel and alleviating the perception that the existing fuel inventory should be conserved due to unreliable fuel supply; and (b) Promulgating a policy for sample irradiation priority that encourages the use of the reactor and does not leave the decision of when to operate entirely at the discretion of reactor operations staff. (2) Each experimental facility in operation or built for a single purpose should be reevaluated to focus on those that most meet the goals of the EAEA strategic business plan. Temporary or long-term elimination of some experimental programs might be necessary to provide more focused utilization. There may be instances of emerging reactor applications for which no experimental facility is yet designed or envisioned. In some cases, an experimental facility may have a more beneficial use than the purpose for which it was originally designed. For example, (a) An effective Boron Neutron Capture Therapy (BNCT) program requires nearby high quality medical facilities. These facilities are not available and are unlikely to be constructed near the Inshas site. Further, the BNCT facility is not correctly designed for advanced research and therapy programs using epithermal neutrons. (b) The ETRR-2 is frequently operated to

analysis and implementation of reactor protection system circuits - case study Egypt's 2 nd research reactor-

International Nuclear Information System (INIS)

Elnokity, O.E.M.

2006-01-01

this work presents a way to design and implement the trip unit of a reactor protection system (RPS) using a field programmable gate arrays (FPGA). instead of the traditional embedded microprocessor based interface design method, a proposed tailor made FPGA based circuit is built to substitute the trip unit (TU), which is used in Egypt's 2 nd research reactor ETRR-2. the existing embedded system is built around the STD32 field computer bus which is used in industrial and process control applications. it is modular, rugged, reliable, and easy-to-use and is able to support a large mix of I/O cards and to easily change its configuration in the future. therefore, the same bus is still used in the proposed design. the state machine of this bus is designed based around its timing diagrams and implemented in VHDL to interface the designed TU circuit

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

International Nuclear Information System (INIS)

Yang Zhongcheng

2006-01-01

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

Effects of dietary pattern and education on glycemic control in patients with type 2 diabetes mellitus at Dr. Sardjito Central General Hospital, Yogyakarta.

Science.gov (United States)

Sinorita, Hemi; Saádah; Jazakillah, Setyowati

2008-04-01

to recognize the effect of education and diet on glycemic control in patients with type 2 diabetes mellitus at Dr. Sardjito Central General Hospital, Jogjakarta. a cross-sectional study was conducted in 88 patients with type 2 DM who had routine visit to the outpatient clinic in Endocrinology Division of Dr. Sardjito Central General Hospital, Jogjakarta. As inclusion criteria, patients who had routine visit in 3 month continuously with fasting plasma glucose (GDN) 126 mg/dl as poor glycemic control group. Data were recorded which included age, sex, period of DM, daily diet pattern, and education received. we found that glycemic control was not affected by sex (p=0.52) and age (p=0.38), but it was affected by period of DM (p=0.02). Glycemic control in the present study was affected by dietary pattern (p=0.01), but not by education (p=1.00). the present study has found significant correlation between regulation of dietary pattern and glycemic control (p=0.01).

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.

General outline of the operation and utilization of the BR2 reactor

International Nuclear Information System (INIS)

Baugnet, J.M.; Leonard, F.; Gandolfo, J.M.; Lenders, H.

1978-01-01

The BR2 reactor is a high-flux material testing reactor of the thermal heterogeneous type. The fuel is 93% 235 U enriched uranium in the form of plates clad in aluminium. The moderator consists of beryllium and light water, the water being pressurized (12.5kg/cm 2 )and acting also as coolant. The pressure vessel is of aluminium, and is placed in a pool of demineralized water. One should stress the following main features of the design: the experimental channels are skew, the tube bundle presenting the form of a hyperboloid of revolution (see figure 1)-this gives easy access at the top and bottom reactor covers allowing complex instrumented devices, while maintaining a very high neutron flux at the core; great flexibilty of utilization, due to the fact that it is possible to adapt the core configuration to the experimental loading as the fissile charge can be centred on different experimental channels; although BR2 is a thermal reactor, it is possible to achieve neutron spectra very similar to those obtained in a fast reactor, either by the use of absorbing screens or by the use of fissile material within the experimental device; five 200mm diameter channels are available for loading large experimental irradiation devices, as in-pile sodium, gas or water loops. (author)

Benchmark testing of CENDL-2 for U-fuel thermal reactors

International Nuclear Information System (INIS)

Zhang Baocheng; Liu Guisheng; Liu Ping

1995-01-01

Based on CENDL-2, NJOY-WIMS code system was used to generate 69-group constants, and do benchmark testing for TRX-1,2; BAPL-UO-2-1,2,3; ZEEP-1,2,3. All the results proved that CENDL-2 is reliable for thermal reactor calculations. (3 tabs.)

Shadow corrosion testing in the INCA facility in the Studsvik R2 reactor

International Nuclear Information System (INIS)

Nystrand, A.C.; Lassing, A.

1999-01-01

Shadow corrosion is a phenomenon which occurs when zirconium alloys are in contact with or in proximity to other metallic objects in a boiling water reactor environment (BWR, RBMK, SGHWR etc.). An enhanced corrosion occurs on the zirconium alloy with the appearance of a 'shadow' of the metallic object. The magnitude of the shadow corrosion can be significant, and is potentially limiting for the lifetime of certain zirconium alloy components in BWRs and other reactors with a similar water chemistry. In order to evaluate the suitability of the In-Core Autoclave (INCA) in the Studsvik R2 materials testing reactor as an experimental facility for studying shadow corrosion, a demonstration test has been performed. A number of test specimens consisting of Zircaloy-2 tubing in contact with Inconel were exposed in an oxidising water chemistry. Some of the specimens were placed within the reactor core and some above the core. The conclusion of this experiment after post irradiation examination is that it is possible to use the INCA facility in the Studsvik R2 reactor to develop a significant level of shadow corrosion after only 800 hours of irradiation. (author)

The 5th surveillance testing for Kori unit 2 reactor vessel materials

Energy Technology Data Exchange (ETDEWEB)

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

2001-03-01

Surveillance testing for reactor vessel materials is performed in order to evaluate the irradiation embrittlement due to neutrons during operation and set the condition of safe operation of nuclear reactor. The 5th surveillance testing was performed completely by Korea Atomic Energy Research Institute at Taejeon after the capsule was transported from Kori site including its removal from reactor. Fast neutron fluences for capsules were calculated and various testing including mechanical and chemistry analysis were performed in order to evaluate the integrity of Kori unit 2 reactor vessel during the operation until life time. The evaluation results are as follows; Fast neutron fluences for capsules V, R, P, T and N are 2.837E+18, 1.105E+19, 2.110E+19, 3.705E+19 and 4.831E+19n/cm{sup 2}, respectively. The bias factor, the ratio of measurement/calculation, was 0.918 for the 1st through 5th testing and the calculational uncertainty, 11.6% satisfied the requirement of USNRC Reg.Guide DG-1053, 20%. The best estimated neutron fluence for reactor vessel inside surface was 1.898E+19n/cm{sup 2} based on the end of 15th fuel cycle and it was predicted that the fluences of vessel inside surface at 32, 40, 48 and 56EFPY would reach 4.203E+19, 5.232E+19, 6.262E+19 and 7.291E+19n/cm{sup 2} based on the current calculation. The result through this analysis for Kori unit 2 showed that there would be no problem for the pressurized thermal shock(PTS) during the operation until design life. 49 refs., 35 figs., 48 tabs. (Author)

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

Science.gov (United States)

Babić, Rade Radomir; Stanković Babić, Gordana

2015-01-01

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

Digital, remote control system for a 2-MW research reactor

International Nuclear Information System (INIS)

Battle, R.E.; Corbett, G.K.

1988-01-01

A fault-tolerant programmable logic controller (PLC) and operator workstations have been programmed to replace the hard-wired relay control system in the 2-MW Bulk Shielding Reactor (BSR) at Oak Ridge National Laboratory. In addition to the PLC and remote and local operator workstations, auxiliary systems for remote operation include a video system, an intercom system, and a fiber optic communication system. The remote control station, located at the High Flux Isotope Reactor 2.5 km from the BSR, has the capability of rector startup and power control. The system was designed with reliability and fail-safe features as important considerations. 4 refs., 3 figs

VizieR Online Data Catalog: Mira stars discovered in LAMOST DR4 (Yao+, 2017)

Science.gov (United States)

Yao, Y.; Liu, C.; Deng, L.; de Grijs, R.; Matsunaga, N.

2017-10-01

By the end of 2016 March, the wide-field Large sky Area Multi-Object fiber Spectroscopic Telescope (LAMOST) DR4 catalog had accumulated 7681185 spectra (R=1800), of which 6898298 were of stars. We compiled a photometrically confirmed sample of Mira variables from the Kiso Wide-Field Camera (KWFC) Intensive Survey of the Galactic Plane (KISOGP; Matsunaga 2017, arXiv:1705.08567), the American Association of Variable Star Observers (AAVSO) International Database Variable Star Index (VSX; Watson 2006, B/vsx, version 2017-05-02; we selected stars of variability type "M"), and the SIMBAD Astronomical Database. We first cross-matched the KISOGP and VSX Miras with the LAMOST DR4 catalog. Finally, we cross-matched the DR4 catalog with the SIMBAD database. See section 2. (1 data file).

Interview with Smithsonian NASM Spacesuit Curator Dr. Cathleen Lewis

Science.gov (United States)

Lewis, Cathleen; Wright, Rebecca

2012-01-01

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

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

Science.gov (United States)

Fawcett, Jacqueline

2012-04-01

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

A nodal Grean's function method of reactor core fuel management code, NGCFM2D

International Nuclear Information System (INIS)

Li Dongsheng; Yao Dong.

1987-01-01

This paper presents the mathematical model and program structure of the nodal Green's function method of reactor core fuel management code, NGCFM2D. Computing results of some reactor cores by NGCFM2D are analysed and compared with other codes

RHTF 2, a 1200 MWe high temperature reactor

International Nuclear Information System (INIS)

Brisbois, Jacques

1978-01-01

After having adapted to French conditions the 1160 MWe G.A.C. reactor, Commissariat a l'Energie Atomique and French Industry have decided to design an High Temperature Reactor 1200 MWe based on the G.A.C. technology and taking into account the point of view of Electricite de France and the experience of C.E.A. and industry on the gas cooled reactor technology. The main objective of this work is to produce a reactor design having a low technical risk, good operability, with an emphasis on the safety aspects easing the licensing problems

Turkey's regulatory plans for high enriched to low enriched conversion of TR-2 reactor core

International Nuclear Information System (INIS)

Guelol Oezdere, Oya

2003-01-01

Turkey is a developing country and has three nuclear facilities two of which are research reactors and one pilot fuel production plant. One of the two research reactors is TR-2 which is located in Cekmece site in Istanbul. TR-2 Reactor's core is composed of both high enriched and low enriched fuel and from high enriched to low enriched core conversion project will take place in year 2005. This paper presents the plans for drafting regulations on the safety analysis report updates for high enriched to low enriched core conversion of TR-2 reactor, the present regulatory structure of Turkey and licensing activities of nuclear facilities. (author)

Techno-economic assessment of membrane assisted fluidized bed reactors for pure H_2 production with CO_2 capture

International Nuclear Information System (INIS)

Spallina, V.; Pandolfo, D.; Battistella, A.; Romano, M.C.; Van Sint Annaland, M.; Gallucci, F.

2016-01-01

Highlights: • Membrane reactors improve the overall efficiency of H_2 production up to 20%. • Respect to conventional reforming, the H_2 yield increases from 12% to 20%. • The COH is reduced of at least 220% using membrane reactors. • FBMR capture 72% of CO_2 with a specific cost of 8 eur/tonn_C_O_2_. • MA-CLR can reach 90% of CO_2 avoided with same cost of FTR. - Abstract: This paper addresses the techno-economic assessment of two membrane-based technologies for H_2 production from natural gas, fully integrated with CO_2 capture. In the first configuration, a fluidized bed membrane reactor (FBMR) is integrated in the H_2 plant: the natural gas reacts with steam in the catalytic bed and H_2 is simultaneously separated using Pd-based membranes, and the heat of reaction is provided to the system by feeding air as reactive sweep gas in part of the membranes and by burning part of the permeated H_2 (in order to avoid CO_2 emissions for heat supply). In the second system, named membrane assisted chemical looping reforming (MA-CLR), natural gas is converted in the fuel rector by reaction with steam and an oxygen carrier (chemical looping reforming), and the produced H_2 permeates through the membranes. The oxygen carrier is re-oxidized in a separate air reactor with air, which also provides the heat required for the endothermic reactions in the fuel reactor. The plants are optimized by varying the operating conditions of the reactors such as temperature, pressures (both at feed and permeate side), steam-to-carbon ratio and the heat recovery configuration. The plant design is carried out using Aspen Simulation, while the novel reactor concepts have been designed and their performance have been studied with a dedicated phenomenological model in Matlab. Both configurations have been designed and compared with reference technologies for H_2 production based on conventional fired tubular reforming (FTR) with and without CO_2 capture. The results of the analysis show

Reactor building integrity testing: A novel approach at Gentilly 2 - principles and methodology

International Nuclear Information System (INIS)

Collins, N.; Lafreniere, P.

1991-01-01

In 1987, Hydro-Quebec embarked on an ambitious development program to provide the Gentilly 2 nuclear power station with an effective, yet practical reactor building Integrity Test. The Gentilly 2 Integrity Test employs an innovative approach based on the reference volume concept. It is identified as the Temperature Compensation Method (TCM) System. This configuration has been demonstrated at both high and low test pressure and has achieved extraordinary precision in the leak rate measurement. The Gentilly 2 design allows the Integrity Test to be performed at a nominal 3 kPa(g) test pressure during an (11) hour period with the reactor at full power. The reactor building Pressure Test by comparison, is typically performed at high pressure 124 kPa(g)) in a 7 day window during an annual outage. The Integrity Test was developed with the goal of demonstrating containment availability. Specifically it was purported to detect a leak or hole in the 'bottled-up' reactor building greater in magnitude than an equivalent pipe of 25 mm diameter. However it is considered feasible that the high precision of the Gentilly 2 TCM System Integrity Test and a stable reactor building leak characteristic will constitute sufficient grounds for the reduction of the Pressure Test frequency. It is noted that only the TCM System has, to this date, allowed a relevant determination of the reactor building leak rate at a nominal test pressure of 3 kPa(g). Classical method tests at low pressure have lead to inconclusive results due to the high lack of precision

Maximum credible accident analysis for TR-2 reactor conceptual design

International Nuclear Information System (INIS)

Manopulo, E.

1981-01-01

A new reactor, TR-2, of 5 MW, designed in cooperation with CEN/GRENOBLE is under construction in the open pool of TR-1 reactor of 1 MW set up by AMF atomics at the Cekmece Nuclear Research and Training Center. In this report the fission product inventory and doses released after the maximum credible accident have been studied. The diffusion of the gaseous fission products to the environment and the potential radiation risks to the population have been evaluated

UO{sub 2} and PuO{sub 2} utilization in high temperature engineering test reactor with helium coolant

Energy Technology Data Exchange (ETDEWEB)

Waris, Abdul, E-mail: awaris@fi.itb.ac.id; Novitrian,; Pramuditya, Syeilendra; Su’ud, Zaki [Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia); Aji, Indarta K. [Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung (Indonesia)

2016-03-11

High temperature engineering test reactor (HTTR) is one of high temperature gas cooled reactor (HTGR) types which has been developed by Japanese Atomic Energy Research Institute (JAERI). The HTTR is a graphite moderator, helium gas coolant, 30 MW thermal output and 950 °C outlet coolant temperature for high temperature test operation. Original HTTR uses UO{sub 2} fuel. In this study, we have evaluated the use of UO{sub 2} and PuO{sub 2} in form of mixed oxide (MOX) fuel in HTTR. The reactor cell calculation was performed by using SRAC 2002 code, with nuclear data library was derived from JENDL3.2. The result shows that HTTR can obtain its criticality condition if the enrichment of {sup 235}U in loaded fuel is 18.0% or above.

The Chernobyl reactor accident. Pt. 1 and 2

International Nuclear Information System (INIS)

1986-06-01

The report first summarizes the available information on the various incidents of the whole accident scenario, and combines the information to present a first general outline and a basis for appraisal. The most significant incidents reported, namely power excursion, core meltdown, and fire, are discussed with a view to the reactor design and safety of reactors installed in the FRG. The main differences and advantages of German reactor designs are shown, as e.g.: Power excursions are mastered by inherent physical conditions; far better redundancy of engineered safety systems; enclosure of the complete reactor cooling system in a pressure-retaining steel containment; reactor buildings being made of reinforced concrete. The second part of the report deals with the radiological effects to be expected for our country. Data are given on the varying radiological exposure of the different regions. The fate and uptake of radioactivity in the human body are discussed. The conclusion drawn from the data presented is that the individual exposure due to the reactor accident will remain within the variations and limits of natural radioactivity and effects. (orig./HP) [de

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,...

DR. MIKA MAJALE MEMORIAL LECTURE

African Journals Online (AJOL)

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

Ali, Dr Moizuddin Abdul Salim

Indian Academy of Sciences (India)

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

Synthesis of the IRSN report related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor. Referral of the Permanent Group of Experts for nuclear reactors (GPR), examination of probabilistic level-2 safety studies (EPS 2) and severe accidents (AG) of the Flamanville reactor nr 3. Opinion related to severe accidents and to the probabilistic level-2 safety study for the Flamanville EPR reactor (FA3). Electronuclear reactors - EDF - Flamanville 3 EPR reactor. Severe accidents and probabilistic level 2 studies

International Nuclear Information System (INIS)

2015-01-01

This document gathers several documents. The first one recalls the main arrangements implemented on the FA3 EPR reactor regarding accidents with core fusion, reports the analysis made by the IRSN about the sizing of these arrangements to reach a controlled status of the installation after a severe accident, regarding the probabilistic level-2 safety assessment, regarding the radiological impact of a severe accident on the population and on the environment, regarding those aimed at facing a total and long duration loss of electric power sources and cold sources, and about the situation of the reactor with respect to WENRA positions on severe accidents for new reactors. The second document is a letter sent by the ASN to the Permanent Group of Experts for nuclear reactors (GPR) to address probabilistic level-2 safety studies (EPS2) and severe accidents for the Flamanville 3 reactor. The third one reports the opinion of the GPR on these both issues and proposes a set of recommendations. The next document is a letter sent by the ASN to the Flamanville 3 project manager at EDF which recalls the related objectives, the ASN opinion on the implemented arrangements for severe accidents (de-pressurization of the primary circuit, management of hydrogen-related risks, corium recovery and cooling outside the vessel, limitation of vapour explosion risks outside the vessel, heat evacuation system, containment enclosure, management of the risk of a return to criticality), to face a total and long duration loss of electricity sources and cold sources, and other aspects addressed in the IRSN analysis. Requests and remarks formulated by the ASN are provided in an appendix to this last document

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

International Nuclear Information System (INIS)

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

2005-01-01

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

Reactor core for LMFBR type reactors

International Nuclear Information System (INIS)

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

1987-01-01

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

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

Separátory, sedimentační nádrže včetně funkce retenční nádrže Jeneweinova

OpenAIRE

Turic, Jakub

2016-01-01

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

A Conceptual Study on a Supercritical CO_2-cooled Micro Modular Reactor

International Nuclear Information System (INIS)

Yu, Hwanyeal; Hartanto, Donny; Kim, Yonghee

2014-01-01

A Micro Modular Reactor (MMR) using Supercritical-CO_2 (S-CO_2) as coolant has been investigated from the neutronics perspective. The MMR is designed to be transportable so it can reach the remote areas. The thermal power of the reactor is 36.2 M Wth. The size of the active core is limited to 1.2 m length and 93.16 cm width. The size of whole core is 2.8 m length and 166.9 cm width. The reactor lifetime design target is 20 years. To maximize the fuel volume fraction in the core, high density uranium nitride UN"1"5 was used. The PbO/MgO reflector was also utilized to improve the neutron economy. The S-CO_2 is chosen as the coolant because it offers a higher thermal efficiency. In this study, neutronics calculations and depletion using McCARD Monte Carlo code has been done to determine the lifetime and behavior of the core. Several important safety parameters such as Control Rod worth, Doppler reactivity coefficients and coolant void reactivity coefficient have also been analyzed. (author)

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

Science.gov (United States)

Ilić, M

1992-01-01

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

Comparison of the N Reactor and Ignalina Unit No. 2 Level 1 Probabilistic Safety Assessments

International Nuclear Information System (INIS)

Coles, G.A.; McKay, S.L.

1995-06-01

A multilateral team recently completed a full-scope Level 1 Probabilistic Safety Assessment (PSA) on the Ignalina Unit No. 2 reactor plant in Lithuania. This allows comparison of results to those of the PSA for the U.S. Department of Energy's (DOE) N Reactor. The N Reactor, although unique as a Western design, has similarities to Eastern European and Soviet graphite block reactors

Raghavarao, Dr Karumanchi Srisaila Mallikarjuna S

Indian Academy of Sciences (India)

Elected: 2014 Section: Engineering & Technology. Raghavarao, Dr Karumanchi Srisaila Mallikarjuna S Ph.D. (Mumbai), FNAE, FNAAS. Specialization: Food Engineering, Biotechnology Address: Chief Scientist, Department of Food Engineering, Central Food Technological Research Institute, Mysore 570 020, Karnataka

CHAP-2 heat-transfer analysis of the Fort St. Vrain reactor core

International Nuclear Information System (INIS)

Kotas, J.F.; Stroh, K.R.

1983-01-01

The Los Alamos National Laboratory is developing the Composite High-Temperature Gas-Cooled Reactor Analysis Program (CHAP) to provide advanced best-estimate predictions of postulated accidents in gas-cooled reactor plants. The CHAP-2 reactor-core model uses the finite-element method to initialize a two-dimensional temperature map of the Fort St. Vrain (FSV) core and its top and bottom reflectors. The code generates a finite-element mesh, initializes noding and boundary conditions, and solves the nonlinear Laplace heat equation using temperature-dependent thermal conductivities, variable coolant-channel-convection heat-transfer coefficients, and specified internal fuel and moderator heat-generation rates. This paper discusses this method and analyzes an FSV reactor-core accident that simulates a control-rod withdrawal at full power

Development of Zr-2.5Nb pressure tubes for Advanced CANDU Reactor

International Nuclear Information System (INIS)

Bickel, G.A.; Griffiths, M.; Douchant, A.; Douglas, S.; Woo, O.T.; Buyers, A.

2010-01-01

In an Advanced CANDU Reactor (ACR), pressure tubes of cold-worked Zr-2.5Nb materials will be used in the reactor core to contain the fuel bundles and the light water coolant. They will be subjected to higher temperature, pressure and flux than that in a CANDU reactor. In order to ensure that these tubes will perform acceptably over their 30-year design life in such an environment, a manufacturing process has been developed to produce 6.5 mm thick ACR pressure tubes with optimized chemical composition, improved mechanical properties and in-reactor behaviour. The test and examination results show that, when compared with current in-service pressure tubes, the mechanical properties of ACR pressure tubes are significantly improved. Based on previous experience with CANDU reactor pressure tubes an assessment of the grain structure and texture indicates that the in-reactor creep deformation will be improved also. Analysis of the distribution of texture parameters from a trial batch of 26 tubes shows that the variability is reduced relative to tubes fabricated in the past. This reduction in variability together with a shift to a coarser grain structure will result in a reduction in diametral creep design limits and thus a longer economic life for the fuel channels of the advanced CANDU reactor. (author)

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

Severe accident analysis for level 2 PSA of SMART reactor

Energy Technology Data Exchange (ETDEWEB)

Lee, Jin Yong; Lee, Jeong Hun; Kim, Jong Uk; Yoo, Tae Geun; Chung, Soon Il; Kim, Min Gi [FNC Technology Co., Seoul (Korea, Republic of)

2010-12-15

The objectives of this study are to produce data for level 2 PSA and evaluation results of severe accident by analyzing severe accident sequence of transient events, producing fault tree of containment systems and evaluating direct containment heating of the SMART. In this project, severe accident analysis results were produced for general transient, loss of feedwater, station blackout, and steam line break events, and based on the results, design safety of SMART was verified. Also, direct containment heating phenomenon of the SMART was evaluated using TCE methodology. For level 2 PSA, fault tree of the containment isolation system, reactor cavity flooding system, plant chilled water system, and reactor containment building HVAC system was produced and analyzed

Recent advances in the utilization and the irradiation technology of the refurbished BR2 reactor

International Nuclear Information System (INIS)

Dekeyser, J.; Benoit, P.; Decloedt, C.; Pouleur, Y.; Verwimp, A.; Weber, M.; Vankeerberghen, M.; Ponsard, B.

1999-01-01

Operation and utilization of the materials testing reactor BR2 at the Belgian Nuclear Research Centre (SCK·CEN) has since its start in 1963 always followed closely the needs and developments of nuclear technology. In particular, a multitude of irradiation experiments have been carried out for most types of nuclear power reactors, existing or under design. Since the early 1990s and increased focus was directed towards more specific irradiation testing needs for light water reactor fuels and materials, although other areas of utilization continued as well (e.g. fusion reactor materials, safety research, ...), including also the growing activities of radioisotope production and silicon doping. An important milestone was the decision in 1994 to implement a comprehensive refurbishment programme for the BR2 reactor and plant installations. The scope of this programme comprised very substantial studies and hardware interventions, which have been completed in early 1997 within planning and budget. Directly connected to this strategic decision for reactor refurbishment was the reinforcement of our efforts to requalify and upgrade the existing irradiation facilities and to develop advanced devices in BR2 to support emerging programs in the following fields: - LWR pressure vessel steel, - LWR irradiation assisted stress corrosion cracking (IASCC), - reliability and safety of high-burnup LWR fuel, - fusion reactor materials and blanket components, - fast neutron reactor fuels and actinide burning, - extension and diversification of radioisotope production. The paper highlights these advances in the areas of BR2 utilisation and the ongoing development activities for the required new generation of irradiations devices. (author)

An improved thermal-hydraulic modeling of the Jules Horowitz Reactor using the CATHARE2 system code

Energy Technology Data Exchange (ETDEWEB)

Pegonen, R., E-mail: pegonen@kth.se [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden); Bourdon, S.; Gonnier, C. [CEA, DEN, DER, SRJH, CEA Cadarache, 13108 Saint-Paul-lez-Durance Cedex (France); Anglart, H. [KTH Royal Institute of Technology, Roslagstullsbacken 21, SE-10691 Stockholm (Sweden)

2017-01-15

Highlights: • An improved thermal-hydraulic modeling of the JHR reactor is described. • Thermal-hydraulics of the JHR is analyzed during loss of flow accident. • The heat exchanger approach gives more realistic and less conservative results. - Abstract: The newest European high performance material testing reactor, the Jules Horowitz Reactor, will support current and future nuclear reactor designs. The reactor is under construction at the CEA Cadarache research center in southern France and is expected to achieve first criticality at the end of this decade. This paper presents an improved thermal-hydraulic modeling of the reactor using solely CATHARE2 system code. Up to now, the CATHARE2 code was simulating the full reactor with a simplified approach for the core and the boundary conditions were transferred into the three-dimensional FLICA4 core simulation. A new more realistic methodology is utilized to analyze the thermal-hydraulic simulation of the reactor during a loss of flow accident.

Hybrid reactors

International Nuclear Information System (INIS)

Moir, R.W.

1980-01-01

The rationale for hybrid fusion-fission reactors is the production of fissile fuel for fission reactors. A new class of reactor, the fission-suppressed hybrid promises unusually good safety features as well as the ability to support 25 light-water reactors of the same nuclear power rating, or even more high-conversion-ratio reactors such as the heavy-water type. One 4000-MW nuclear hybrid can produce 7200 kg of 233 U per year. To obtain good economics, injector efficiency times plasma gain (eta/sub i/Q) should be greater than 2, the wall load should be greater than 1 MW.m -2 , and the hybrid should cost less than 6 times the cost of a light-water reactor. Introduction rates for the fission-suppressed hybrid are usually rapid

Proceedings of 2. Yugoslav symposium on reactor physics, Part 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966; 2. Jugoslovenski simpozijum iz reaktorske fizike, Deo 2, Herceg Novi (Yugoslavia), 27-29 Sep 1966

Energy Technology Data Exchange (ETDEWEB)

NONE

1966-07-01

This Volume 2 of the Proceedings of 2. Yugoslav symposium on reactor physics includes eight papers dealing with the following topics: method for measuring high anti reactivities of a reactor system; integration method for thermal reaction rate calculation; Determination of initial core configuration for BHWR-200 MWe; safety shutdowns and failures of the RA reactor equipment; determining the reactivity of absorption rods; measurements of thermal and fast neutron fluxes at the TRIGA reactor and other measurements during operation of the TRIGA reactor; mathematical modelling of the reactor safety; review of problems and methods for radiation risk assessment in the environment of a nuclear power plant.

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.

Den europæiske drøm - om EU

DEFF Research Database (Denmark)

Østergaard, Uffe

2007-01-01

Anmeldelse af: Jeremy Rifkin: Den europæiske drøm (Informations Forlag, 2006). Oversat fra engelsk efter: "The European Dream: How Europe's Vision of the Future Is Quietly Eclipsing the American Dream" (2004)......Anmeldelse af: Jeremy Rifkin: Den europæiske drøm (Informations Forlag, 2006). Oversat fra engelsk efter: "The European Dream: How Europe's Vision of the Future Is Quietly Eclipsing the American Dream" (2004)...

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

CERN Multimedia

Maximilien Brice

2003-01-01

Dr. David Syz, State Secretary for Economic Affairs, Switzerland is seen here (seventh from right) visiting the assembly hall for the ATLAS experiment during his recent visit to CERN. To his right is Dr. Peter Jenni (blue shirt), spokesperson for the ATLAS Collaboration. The horizontal metal cylinder behind the group is one of the eight vacuum vessels for the superconducting coils of the ATLAS barrel toroid magnet system.

Celebrating the Life and Legacy of Dr. John Hope Franklin

Science.gov (United States)

Harris, Robert L., Jr.; Levering-Lewis, David; French, John D.; Wharton, Clifton R., Jr.

2009-01-01

Dr. John Hope Franklin chronicled the experiences of African-Americans like no one before him, forcing America to recognize Black history as American history. His contributions were innumerable and his impact was abiding. In celebration of his life and legacy, the authors profile the celebrated scholar and activist, Dr. John Hope Franklin.

Problems of nuclear reactor safety. Vol. 2

International Nuclear Information System (INIS)

Goncharov, L.A.

1995-01-01

Theses of proceedings of the 9 Topical Meeting on problems of nuclear power plant safety are presented. Reports include results of neutron-physical experiments carried out for reactor safety justification. Concepts of advanced reactors with improved safety are considered. Results of researches on fuel cycles are given too

Dr Jacob van der Land, marine biologist extraordinary

OpenAIRE

Bruggen, van, A.C.

2001-01-01

This contribution is an attempt to sketch the life and works of Dr Jacob van der Land, curator of worms and chief marine biologist of the National Museum of Natural History, on the occasion of his official retirement. Born in 1935, Jacob van der Land read biology at Leiden University (1958-1964), where he obtained his Ph.D. in 1970 on a treatise on the Priapulida under the supervision of Prof. Dr L.D. Brongersma. In 1964 he was appointed curator of worms in the museum. Later on he took over l...

The Effect Of Beryllium Interaction With Fast Neutrons On the Reactivity Of ETRR-2 Research Reactor

International Nuclear Information System (INIS)

Aziz, M.; El Messiry, A.M.

2000-01-01

The effect of beryllium interactions with fast neutrons is studied for Etrr 2 research reactors. Isotope build up inside beryllium blocks is calculated under different irradiation times. a new model for the Etrr 2 research reactor is designed using MCNP code to calculate the reactivity and flux change of the reactor due to beryllium poison

Economics and utilization of thorium in nuclear reactors. Technical annexes 1 and 2

International Nuclear Information System (INIS)

1978-05-01

An assessment of the impact of utilizing the 233 U/thorium fuel cycle in the U.S. nuclear economy is strongly dependent upon several decisions involving nuclear energy policy. These decisions include: (1) to recycle or not recycle fissile material; (2) if fissile material is recycled, to recycle plutonium, 233 U, or both; and (3) to deploy or not to deploy advanced reactor designs such as Fast Breeder Reactors (FBR's), High Temperature Gas Reactors (HTGR's), and Canadian Deuterium Uranium Reactors (CANDU's). This report examines the role of thorium in the context of the above policy decisions while focusing special attention on economics and resource utilization

The Honorable Dr Adolfo Urso, Vice Minister for Foreign Trade, "Viceministro delle Attivita' Produttive, Italia"

CERN Multimedia

Patrice Loïez

2002-01-01

Photo 01: The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy, visiting SM18 with (from l to r): Dr Roberto Saban, Technical Coordination and Planning, LHC machine; Prof. Luciano Maiani, CERN Director-General; Dr Mario Gerbino, Director General of the Ministry and Prof. Lucio Rossi, LHC Main Magnet and Superconductors (MMS) Group Leader. Photo 02: Prof. Luciano Maiani, CERN Director-General and The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy, in front of one of the LHC superconducting magnet in SM18. Photo 03 :In front of one of the LHC superconducting magnets - from left to right Dr Roberto Saban, Technical Coordination and Planning, LHC machine; The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy and Prof. Luciano Maiani, CERN Director-General. Photo 04: In the SM18 hall (from l. to r.) Prof. Luciano Maiani, CERN Director-General, The Honorable Dr Adolfo Urso, Deputy Minister for Productive Activities, Italy and Dr Mario Ge...