WorldWideScience

Sample records for code results status

  1. Computer and compiler effects on code results: status report

    International Nuclear Information System (INIS)

    1996-01-01

    Within the framework of the international effort on the assessment of computer codes, which are designed to describe the overall reactor coolant system (RCS) thermalhydraulic response, core damage progression, and fission product release and transport during severe accidents, there has been a continuous debate as to whether the code results are influenced by different code users or by different computers or compilers. The first aspect, the 'Code User Effect', has been investigated already. In this paper the other aspects will be discussed and proposals are given how to make large system codes insensitive to different computers and compilers. Hardware errors and memory problems are not considered in this report. The codes investigated herein are integrated code systems (e. g. ESTER, MELCOR) and thermalhydraulic system codes with extensions for severe accident simulation (e. g. SCDAP/RELAP, ICARE/CATHARE, ATHLET-CD), and codes to simulate fission product transport (e. g. TRAPMELT, SOPHAEROS). Since all of these codes are programmed in Fortran 77, the discussion herein is based on this programming language although some remarks are made about Fortran 90. Some observations about different code results by using different computers are reported and possible reasons for this unexpected behaviour are listed. Then methods are discussed how to avoid portability problems

  2. Status of MARS Code

    Energy Technology Data Exchange (ETDEWEB)

    N.V. Mokhov

    2003-04-09

    Status and recent developments of the MARS 14 Monte Carlo code system for simulation of hadronic and electromagnetic cascades in shielding, accelerator and detector components in the energy range from a fraction of an electronvolt up to 100 TeV are described. these include physics models both in strong and electromagnetic interaction sectors, variance reduction techniques, residual dose, geometry, tracking, histograming. MAD-MARS Beam Line Build and Graphical-User Interface.

  3. TRAC code development status and plans

    International Nuclear Information System (INIS)

    Spore, J.W.; Liles, D.R.; Nelson, R.A.

    1986-01-01

    This report summarizes the characteristics and current status of the TRAC-PF1/MOD1 computer code. Recent error corrections and user-convenience features are described, and several user enhancements are identified. Current plans for the release of the TRAC-PF1/MOD2 computer code and some preliminary MOD2 results are presented. This new version of the TRAC code implements stability-enhancing two-step numerics into the 3-D vessel, using partial vectorization to obtain a code that has run 400% faster than the MOD1 code

  4. Development status of TUF code

    International Nuclear Information System (INIS)

    Liu, W.S.; Tahir, A.; Zaltsgendler

    1996-01-01

    An overview of the important development of the TUF code in 1995 is presented. The development in the following areas is presented: control of round-off error propagation, gas resolution and release models, and condensation induced water hammer. This development is mainly generated from station requests for operational support and code improvement. (author)

  5. Status of SPACE Safety Analysis Code Development

    International Nuclear Information System (INIS)

    Lee, Dong Hyuk; Yang, Chang Keun; Kim, Se Yun; Ha, Sang Jun

    2009-01-01

    In 2006, the Korean the Korean nuclear industry started developing a thermal-hydraulic analysis code for safety analysis of PWR(Pressurized Water Reactor). The new code is named as SPACE(Safety and Performance Analysis Code for Nuclear Power Plant). The SPACE code can solve two-fluid, three-field governing equations in one dimensional or three dimensional geometry. The SPACE code has many component models required for modeling a PWR, such as reactor coolant pump, safety injection tank, etc. The programming language used in the new code is C++, for new generation of engineers who are more comfortable with C/C++ than old FORTRAN language. This paper describes general characteristics of SPACE code and current status of SPACE code development

  6. Status of the CONTAIN computer code for LWR containment analysis

    International Nuclear Information System (INIS)

    Bergeron, K.D.; Murata, K.K.; Rexroth, P.E.; Clauser, M.J.; Senglaub, M.E.; Sciacca, F.W.; Trebilcock, W.

    1983-01-01

    The current status of the CONTAIN code for LWR safety analysis is reviewed. Three example calculations are discussed as illustrations of the code's capabilities: (1) a demonstration of the spray model in a realistic PWR problem, and a comparison with CONTEMPT results; (2) a comparison of CONTAIN results for a major aerosol experiment against experimental results and predictions of the HAARM aerosol code; and (3) an LWR sample problem, involving a TMLB' sequence for the Zion reactor containment

  7. Status of the CONTAIN computer code for LWR containment analysis

    International Nuclear Information System (INIS)

    Bergeron, K.D.; Murata, K.K.; Rexroth, P.E.; Clauser, M.J.; Senglaub, M.E.; Sciacca, F.W.; Trebilcock, W.

    1982-01-01

    The current status of the CONTAIN code for LWR safety analysis is reviewed. Three example calculations are discussed as illustrations of the code's capabilities: (1) a demonstration of the spray model in a realistic PWR problem, and a comparison with CONTEMPT results; (2) a comparison of CONTAIN results for a major aerosol experiment against experimental results and predictions of the HAARM aerosol code; and (3) an LWR sample problem, involving a TMLB' sequence for the Zion reactor containment

  8. Status of reactor core design code system in COSINE code package

    International Nuclear Information System (INIS)

    Chen, Y.; Yu, H.; Liu, Z.

    2014-01-01

    For self-reliance, COre and System INtegrated Engine for design and analysis (COSINE) code package is under development in China. In this paper, recent development status of the reactor core design code system (including the lattice physics code and the core simulator) is presented. The well-established theoretical models have been implemented. The preliminary verification results are illustrated. And some special efforts, such as updated theory models and direct data access application, are also made to achieve better software product. (author)

  9. Status of reactor core design code system in COSINE code package

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y.; Yu, H.; Liu, Z., E-mail: yuhui@snptc.com.cn [State Nuclear Power Software Development Center, SNPTC, National Energy Key Laboratory of Nuclear Power Software (NEKLS), Beijiing (China)

    2014-07-01

    For self-reliance, COre and System INtegrated Engine for design and analysis (COSINE) code package is under development in China. In this paper, recent development status of the reactor core design code system (including the lattice physics code and the core simulator) is presented. The well-established theoretical models have been implemented. The preliminary verification results are illustrated. And some special efforts, such as updated theory models and direct data access application, are also made to achieve better software product. (author)

  10. Challenges to code status discussions for pediatric patients.

    Directory of Open Access Journals (Sweden)

    Katherine E Kruse

    Full Text Available In the context of serious or life-limiting illness, pediatric patients and their families are faced with difficult decisions surrounding appropriate resuscitation efforts in the event of a cardiopulmonary arrest. Code status orders are one way to inform end-of-life medical decision making. The objectives of this study are to evaluate the extent to which pediatric providers have knowledge of code status options and explore the association of provider role with (1 knowledge of code status options, (2 perception of timing of code status discussions, (3 perception of family receptivity to code status discussions, and (4 comfort carrying out code status discussions.Nurses, trainees (residents and fellows, and attending physicians from pediatric units where code status discussions typically occur completed a short survey questionnaire regarding their knowledge of code status options and perceptions surrounding code status discussions.Single center, quaternary care children's hospital.203 nurses, 31 trainees, and 29 attending physicians in 4 high-acuity pediatric units responded to the survey (N = 263, 90% response rate. Based on an objective knowledge measure, providers demonstrate poor understanding of available code status options, with only 22% of providers able to enumerate more than two of four available code status options. In contrast, provider groups self-report high levels of familiarity with available code status options, with attending physicians reporting significantly higher levels than nurses and trainees (p = 0.0125. Nurses and attending physicians show significantly different perception of code status discussion timing, with majority of nurses (63.4% perceiving discussions as occurring "too late" or "much too late" and majority of attending physicians (55.6% perceiving the timing as "about right" (p<0.0001. Attending physicians report significantly higher comfort having code status discussions with families than do nurses or trainees

  11. Benchmarking NNWSI flow and transport codes: COVE 1 results

    International Nuclear Information System (INIS)

    Hayden, N.K.

    1985-06-01

    The code verification (COVE) activity of the Nevada Nuclear Waste Storage Investigations (NNWSI) Project is the first step in certification of flow and transport codes used for NNWSI performance assessments of a geologic repository for disposing of high-level radioactive wastes. The goals of the COVE activity are (1) to demonstrate and compare the numerical accuracy and sensitivity of certain codes, (2) to identify and resolve problems in running typical NNWSI performance assessment calculations, and (3) to evaluate computer requirements for running the codes. This report describes the work done for COVE 1, the first step in benchmarking some of the codes. Isothermal calculations for the COVE 1 benchmarking have been completed using the hydrologic flow codes SAGUARO, TRUST, and GWVIP; the radionuclide transport codes FEMTRAN and TRUMP; and the coupled flow and transport code TRACR3D. This report presents the results of three cases of the benchmarking problem solved for COVE 1, a comparison of the results, questions raised regarding sensitivities to modeling techniques, and conclusions drawn regarding the status and numerical sensitivities of the codes. 30 refs

  12. Status of the ASTEC integral code

    International Nuclear Information System (INIS)

    Van Dorsselaere, J.P.; Jacq, F.; Allelein, H.J.

    2000-01-01

    The ASTEC (Accident Source Term Evaluation Code) integrated code is developed since 1997 in close collaboration by IPSN and GRS to predict an entire LWR severe accident sequence from the initiating event up to Fission Product (FP) release out of the containment. The applications of such a code are source term determination studies, scenario evaluations, accident management studies and Probabilistic Safety Assessment level 2 (PSA-2) studies. The version V0 of ASTEC is based on the RCS modules of the ESCADRE integrated code (IPSN) and on the upgraded RALOC and FIPLOC codes (GRS) for containment thermalhydraulics and aerosol behaviour. The latest version V0.2 includes the general feed-back from the overall validation performed in 1998 (25 separate-effect experiments, PHEBUS.FP FPT1 integrated experiment), some modelling improvements (i.e. silver-iodine reactions in the containment sump), and the implementation of the main safety systems for Severe Accident Management. Several reactor-applications are under way on French and German PWR, and on VVER-1000, all with a multi-compartment configuration of the containment. The total IPSN-GRS manpower involved in ASTEC project is today about 20 men/year. The main evolution of the next version V1, foreseen end of 2001, concerns the integration of the front-end phase and the improvement of the in-vessel degradation late-phase modelling. (author)

  13. Current status of high energy nucleon-meson transport code

    Energy Technology Data Exchange (ETDEWEB)

    Takada, Hiroshi; Sasa, Toshinobu [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    Current status of design code of accelerator (NMTC/JAERI code), outline of physical model and evaluation of accuracy of code were reported. To evaluate the nuclear performance of accelerator and strong spallation neutron origin, the nuclear reaction between high energy proton and target nuclide and behaviors of various produced particles are necessary. The nuclear design of spallation neutron system used a calculation code system connected the high energy nucleon{center_dot}meson transport code and the neutron{center_dot}photon transport code. NMTC/JAERI is described by the particle evaporation process under consideration of competition reaction of intranuclear cascade and fission process. Particle transport calculation was carried out for proton, neutron, {pi}- and {mu}-meson. To verify and improve accuracy of high energy nucleon-meson transport code, data of spallation and spallation neutron fragment by the integral experiment were collected. (S.Y.)

  14. The PARTRAC code: Status and recent developments

    Science.gov (United States)

    Friedland, Werner; Kundrat, Pavel

    Biophysical modeling is of particular value for predictions of radiation effects due to manned space missions. PARTRAC is an established tool for Monte Carlo-based simulations of radiation track structures, damage induction in cellular DNA and its repair [1]. Dedicated modules describe interactions of ionizing particles with the traversed medium, the production and reactions of reactive species, and score DNA damage determined by overlapping track structures with multi-scale chromatin models. The DNA repair module describes the repair of DNA double-strand breaks (DSB) via the non-homologous end-joining pathway; the code explicitly simulates the spatial mobility of individual DNA ends in parallel with their processing by major repair enzymes [2]. To simulate the yields and kinetics of radiation-induced chromosome aberrations, the repair module has been extended by tracking the information on the chromosome origin of ligated fragments as well as the presence of centromeres [3]. PARTRAC calculations have been benchmarked against experimental data on various biological endpoints induced by photon and ion irradiation. The calculated DNA fragment distributions after photon and ion irradiation reproduce corresponding experimental data and their dose- and LET-dependence. However, in particular for high-LET radiation many short DNA fragments are predicted below the detection limits of the measurements, so that the experiments significantly underestimate DSB yields by high-LET radiation [4]. The DNA repair module correctly describes the LET-dependent repair kinetics after (60) Co gamma-rays and different N-ion radiation qualities [2]. First calculations on the induction of chromosome aberrations have overestimated the absolute yields of dicentrics, but correctly reproduced their relative dose-dependence and the difference between gamma- and alpha particle irradiation [3]. Recent developments of the PARTRAC code include a model of hetero- vs euchromatin structures to enable

  15. Nutritional knowledge and status of coaches in various sporting codes

    African Journals Online (AJOL)

    Coaches have an important responsibility in the lives of athletes since athletes often use them as a source of advice for various performance-related issues, such as the nutritional regime. This descriptive study set out to identify the nutritional knowledge and nutritional status of coaches from various sport codes, as well as ...

  16. Association of code status discussion with invasive procedures among advanced-stage cancer and noncancer patients

    Directory of Open Access Journals (Sweden)

    Sasaki A

    2017-07-01

    Full Text Available Akinori Sasaki,1 Eiji Hiraoka,1 Yosuke Homma,2 Osamu Takahashi,3 Yasuhiro Norisue,4 Koji Kawai,5 Shigeki Fujitani4 1Department of Internal Medicine, 2Department of Emergency Medicine, Tokyo Bay Urayasu Ichikawa Medical Center, Urayasu City, Chiba, 3Department of Internal Medicine, St. Luke’s International Hospital, Chuo-ku, Tokyo, 4Department of Critical Care Medicine, Tokyo Bay Urayasu Ichikawa Medical Center, Urayasu City, Chiba, 5Department of Gastroenterology, Ito Municipal Hospital, Ito City, Shizuoka, Japan Background: Code status discussion is associated with a decrease in invasive procedures among terminally ill cancer patients. We investigated the association between code status discussion on admission and incidence of invasive procedures, cardiopulmonary resuscitation (CPR, and opioid use among inpatients with advanced stages of cancer and noncancer diseases. Methods: We performed a retrospective cohort study in a single center, Ito Municipal Hospital, Japan. Participants were patients who were admitted to the Department of Internal Medicine between October 1, 2013 and August 30, 2015, with advanced-stage cancer and noncancer. We collected demographic data and inquired the presence or absence of code status discussion within 24 hours of admission and whether invasive procedures, including central venous catheter placement, intubation with mechanical ventilation, and CPR for cardiac arrest, and opioid treatment were performed. We investigated the factors associated with CPR events by using multivariate logistic regression analysis. Results: Among the total 232 patients, code status was discussed with 115 patients on admission, of which 114 (99.1% patients had do-not-resuscitate (DNR orders. The code status was not discussed with the remaining 117 patients on admission, of which 69 (59% patients had subsequent code status discussion with resultant DNR orders. Code status discussion on admission decreased the incidence of central venous

  17. FFTF startup: status and results

    International Nuclear Information System (INIS)

    Noordhoff, B.H.; Moore, C.E.

    1980-03-01

    Startup testing on the Fast Flux Test Facility (FFTF) during the past three years has progressed beyond initial criticality toward the principal goal of power demonstration in 1980. An overview is presented of technical results to date and project plans to achieve power demonstration and complete the startup test program

  18. Processes of code status transitions in hospitalized patients with advanced cancer.

    Science.gov (United States)

    El-Jawahri, Areej; Lau-Min, Kelsey; Nipp, Ryan D; Greer, Joseph A; Traeger, Lara N; Moran, Samantha M; D'Arpino, Sara M; Hochberg, Ephraim P; Jackson, Vicki A; Cashavelly, Barbara J; Martinson, Holly S; Ryan, David P; Temel, Jennifer S

    2017-12-15

    Although hospitalized patients with advanced cancer have a low chance of surviving cardiopulmonary resuscitation (CPR), the processes by which they change their code status from full code to do not resuscitate (DNR) are unknown. We conducted a mixed-methods study on a prospective cohort of hospitalized patients with advanced cancer. Two physicians used a consensus-driven medical record review to characterize processes that led to code status order transitions from full code to DNR. In total, 1047 hospitalizations were reviewed among 728 patients. Admitting clinicians did not address code status in 53% of hospitalizations, resulting in code status orders of "presumed full." In total, 275 patients (26.3%) transitioned from full code to DNR, and 48.7% (134 of 275 patients) of those had an order of "presumed full" at admission; however, upon further clarification, the patients expressed that they had wished to be DNR before the hospitalization. We identified 3 additional processes leading to order transition from full code to DNR acute clinical deterioration (15.3%), discontinuation of cancer-directed therapy (17.1%), and education about the potential harms/futility of CPR (15.3%). Compared with discontinuing therapy and education, transitions because of acute clinical deterioration were associated with less patient involvement (P = .002), a shorter time to death (P cancer were because of full code orders in patients who had a preference for DNR before hospitalization. Transitions due of acute clinical deterioration were associated with less patient engagement and a higher likelihood of inpatient death. Cancer 2017;123:4895-902. © 2017 American Cancer Society. © 2017 American Cancer Society.

  19. The present status of the blowdown code BRUCH

    International Nuclear Information System (INIS)

    Karwat, H.

    1975-01-01

    The present status and the important features of the blowdown code for a PWR, BRUCH-D version 04 which is presently in use, are described. The code is to investigate the depressurization process, fluid dynamic situation in the core, the fuel temperature and the core mass flow as influenced by important primary system components such as steam generators, pumps etc. The code is a multinode point model with a fixed node arrangement. It makes use of the basic fluid dynamic equations describing the mass, energy and volume conservation as well as the momentum equation and the equation of state with appropriate assumptions. The core heat generation and heat transfer to the fluid is simulated by a given number of average fuel rods with up to 20 axial segmentation independent of the axial subdivision of the core fluid region. In parallel up to 5 types of the fuel rods can be studied. The pump behaviour is specified by input. For the break flow, the code provides three models; Bernoulli, homogenous and moody. The implicit-explicit method IMEX is used for the integration of the differential equations. An example for application of BRUCH-S to an experiment which is for a BWR but has some basis of BRUCH-D is also shown in the paper

  20. Leadership Class Configuration Interaction Code - Status and Opportunities

    Science.gov (United States)

    Vary, James

    2011-10-01

    With support from SciDAC-UNEDF (www.unedf.org) nuclear theorists have developed and are continuously improving a Leadership Class Configuration Interaction Code (LCCI) for forefront nuclear structure calculations. The aim of this project is to make state-of-the-art nuclear structure tools available to the entire community of researchers including graduate students. The project includes codes such as NuShellX, MFDn and BIGSTICK that run a range of computers from laptops to leadership class supercomputers. Codes, scripts, test cases and documentation have been assembled, are under continuous development and are scheduled for release to the entire research community in November 2011. A covering script that accesses the appropriate code and supporting files is under development. In addition, a Data Base Management System (DBMS) that records key information from large production runs and archived results of those runs has been developed (http://nuclear.physics.iastate.edu/info/) and will be released. Following an outline of the project, the code structure, capabilities, the DBMS and current efforts, I will suggest a path forward that would benefit greatly from a significant partnership between researchers who use the codes, code developers and the National Nuclear Data efforts. This research is supported in part by DOE under grant DE-FG02-87ER40371 and grant DE-FC02-09ER41582 (SciDAC-UNEDF).

  1. Medieval codes of ius commune in Portugal: status quaestionis

    Directory of Open Access Journals (Sweden)

    José Domingues

    2016-12-01

    Full Text Available Portugal inherited from the kingdom of León legal sources and its earliest law code. With the “rebirth” of Roman law, the Ius commune –arriving very early in the twelfth century– soon came to shape everyday life, from the middle ages until the Enlightenment of the late eighteenth century. Enormous research efforts have been made to locate chronologically and spatially medieval remnants of these legal texts. This work aims to provide a summary, including a comprehensive and updated picture, of the status quaestionis of this theme.

  2. ATLAS @ LHC: status and recent results

    CERN Document Server

    McPherson, Robert; The ATLAS collaboration

    2017-01-01

    The status and data taking summary of the ATLAS experiment at the CERN Large Hadron Collider is reviewed. Recent physics analysis results are presented, and the detector upgrade program is briefly summarized.

  3. Status Report on Hydrogen Management and Related Computer Codes

    International Nuclear Information System (INIS)

    Liang, Z.; Chan, C.K.; Sonnenkalb, M.; Bentaib, A.; Malet, J.; Sangiorgi, M.; Gryffroy, D.; Gyepi-Garbrah, S.; Duspiva, J.; Sevon, T.; Kelm, S.; Reinecke, E.A.; Xu, Z.J.; Cervone, A.; Utsuno, H.; Hotta, A.; Hong, S.W.; Kim, J.T.; Visser, D.C.; Stempniewicz, M.M.; Kuriene, L.; Prusinski, P.; Martin-Valdepenas, J.M.; Frid, W.; Isaksson, P.; Dreier, J.; Paladino, D.; Algama, D.; Notafrancesco, A.; Amri, A.; Kissane, M.; )

    2014-01-01

    In follow-up to the Fukushima Daiichi NPP accident, the Committee on the Safety of Nuclear Installations (CSNI) decided to launch several high priority activities. At the 14. plenary meeting of the Working Group on Analysis and Management of Accidents (WGAMA), a proposal for a status paper on hydrogen generation, transport and mitigation under severe accident conditions was approved. The proposed activity is in line with the WGAMA mandate and it was considered to be needed to revisit the hydrogen issue. The report is broken down into five Chapters and two appendixes. Chapter 1 provides background information for this activity and expected topics defined by the WGAMA members. A general understanding of hydrogen behavior and control in severe accidents is discussed. A brief literature review is included in this chapter to summarize the progress obtained from the early US NRC sponsored research on hydrogen and recent international OECD or EC sponsored projects on hydrogen related topics (generation, distribution, combustion and mitigation). Chapter 2 provides a general overview of the various reactor designs of Western PWRs, BWRs, Eastern European VVERs and PHWRs (CANDUs). The purpose is to understand the containment design features in relation to hydrogen management measures. Chapter 3 provides a detailed description of national requirements on hydrogen management and hydrogen mitigation measures inside the containment and other places (e.g., annulus space, secondary buildings, spent fuel pool, etc.). Discussions are followed on hydrogen analysis approaches, application of safety systems (e.g., spray, containment ventilation, local air cooler, suppression pool, and latch systems), hydrogen measurement strategies as well as lessons learnt from the Fukushima Daiichi nuclear power accident. Chapter 4 provides an overview of various codes that are being used for hydrogen risk assessment, and the codes capabilities and validation status in terms of hydrogen related

  4. Present status of transport code development based on Monte Carlo method

    International Nuclear Information System (INIS)

    Nakagawa, Masayuki

    1985-01-01

    The present status of development in Monte Carlo code is briefly reviewed. The main items are the followings; Application fields, Methods used in Monte Carlo code (geometry spectification, nuclear data, estimator and variance reduction technique) and unfinished works, Typical Monte Carlo codes and Merits of continuous energy Monte Carlo code. (author)

  5. Results from the Metis code participation to the Hydrocoin exercise

    International Nuclear Information System (INIS)

    Raimbault, P.

    1987-04-01

    The METIS code, developed at the ENSMP is a 2D finite element radionuclide transport and groundwater flow model based on the hypothesis of an equivalent porous medium with an explicit description of the main fractures. It is integrated in the global risk assessment code MELODIE for nuclear waste repositories in geological formations. The participation of the METIS code to the HYDROCOIN exercise is of prime importance for its development and its incorporation in the performance assessment procedure in France. Results from HYDROCOIN cases show that the code can handle correctly fractured media, high permeability contrast formations and buoyancy effects. A 3D version of the code has been developed for carrying comparisons of field experiments and groundwater flow models in HYDROCOIN level 2. In order to carry out the exercise, several pre and post-processing programs were developed and integrated in a conversational module. They include: contour plots, velocity field representations, interpolations, particule tracking routines and uncertainty and sensitivity analysis modules

  6. Automated Testing Infrastructure and Result Comparison for Geodynamics Codes

    Science.gov (United States)

    Heien, E. M.; Kellogg, L. H.

    2013-12-01

    The geodynamics community uses a wide variety of codes on a wide variety of both software and hardware platforms to simulate geophysical phenomenon. These codes are generally variants of finite difference or finite element calculations involving Stokes flow or wave propagation. A significant problem is that codes of even low complexity will return different results depending on the platform due to slight differences in hardware, software, compiler, and libraries. Furthermore, changes to the codes during development may affect solutions in unexpected ways such that previously validated results are altered. The Computational Infrastructure for Geodynamics (CIG) is funded by the NSF to enhance the capabilities of the geodynamics community through software development. CIG has recently done extensive work in setting up an automated testing and result validation system based on the BaTLab system developed at the University of Wisconsin, Madison. This system uses 16 variants of Linux and Mac platforms on both 32 and 64-bit processors to test several CIG codes, and has also recently been extended to support testing on the XSEDE TACC (Texas Advanced Computing Center) Stampede cluster. In this work we overview the system design and demonstrate how automated testing and validation occurs and results are reported. We also examine several results from the system from different codes and discuss how changes in compilers and libraries affect the results. Finally we detail some result comparison tools for different types of output (scalar fields, velocity fields, seismogram data), and discuss within what margins different results can be considered equivalent.

  7. Status, first results and prospects for MAGIC

    International Nuclear Information System (INIS)

    Rico, Javier

    2006-01-01

    MAGIC is the world-largest Imaging Air Cherenkov Telescope (IACT) for Very High Energy (VHE) γ-ray astronomy and operates in the range from ∼50 GeV to ∼10 TeV. In this paper we will briefly summarize the status of the project, including the construction of a second (MAGIC-II) telescope, and review the results obtained from the first observations

  8. Patient-Physician Communication About Code Status Preferences: A Randomized Controlled Trial

    Science.gov (United States)

    Rhondali, Wadih; Perez-Cruz, Pedro; Hui, David; Chisholm, Gary B.; Dalal, Shalini; Baile, Walter; Chittenden, Eva; Bruera, Eduardo

    2013-01-01

    Purpose Code status discussions are important in cancer care. The best modality for such discussions has not been established. Our objective was to determine the impact of a physician ending a code status discussion with a question (autonomy approach) versus a recommendation (beneficence approach) on patients' do-not-resuscitate (DNR) preference. Methods Patients in a supportive care clinic watched two videos showing a physician-patient discussion regarding code status. Both videos were identical except for the ending: one ended with the physician asking for the patient's code status preference and the other with the physician recommending DNR. Patients were randomly assigned to watch the videos in different sequences. The main outcome was the proportion of patients choosing DNR for the video patient. Results 78 patients completed the study. 74% chose DNR after the question video, 73% after the recommendation video. Median physician compassion score was very high and not different for both videos. 30/30 patients who had chosen DNR for themselves and 30/48 patients who had not chosen DNR for themselves chose DNR for the video patient (100% v/s 62%). Age (OR=1.1/year) and white ethnicity (OR=9.43) predicted DNR choice for the video patient. Conclusion Ending DNR discussions with a question or a recommendation did not impact DNR choice or perception of physician compassion. Therefore, both approaches are clinically appropriate. All patients who chose DNR for themselves and most patients who did not choose DNR for themselves chose DNR for the video patient. Age and race predicted DNR choice. PMID:23564395

  9. Under-coding of secondary conditions in coded hospital health data: Impact of co-existing conditions, death status and number of codes in a record.

    Science.gov (United States)

    Peng, Mingkai; Southern, Danielle A; Williamson, Tyler; Quan, Hude

    2017-12-01

    This study examined the coding validity of hypertension, diabetes, obesity and depression related to the presence of their co-existing conditions, death status and the number of diagnosis codes in hospital discharge abstract database. We randomly selected 4007 discharge abstract database records from four teaching hospitals in Alberta, Canada and reviewed their charts to extract 31 conditions listed in Charlson and Elixhauser comorbidity indices. Conditions associated with the four study conditions were identified through multivariable logistic regression. Coding validity (i.e. sensitivity, positive predictive value) of the four conditions was related to the presence of their associated conditions. Sensitivity increased with increasing number of diagnosis code. Impact of death on coding validity is minimal. Coding validity of conditions is closely related to its clinical importance and complexity of patients' case mix. We recommend mandatory coding of certain secondary diagnosis to meet the need of health research based on administrative health data.

  10. Development status of Severe Accident Analysis Code SAMPSON

    International Nuclear Information System (INIS)

    Iwashita, Tsuyoshi; Ujita, Hiroshi

    2000-01-01

    The Four years of the IMPACT, 'Integrated Modular Plant Analysis and Computing Technology' project Phase 1 have been completed. The verification study of Severe Accident Analysis Code SAMPSON prototype developed in Phase 1 was conducted in two steps. First, each analysis module was run independently and analysis results were compared and verified against separate-effect test data with good results. Test data are as follows: CORA-13 (FZK) for the Core Heat-up Module; VI-3 of HI/VI Test (ORNL) for the FP Release from Fuel Module; KROTOS-37 (JRC-ISPRA) for the Molten Core Relocation Module; Water Spread Test (UCSB) for the Debris Spreading Model and Benard's Melting Test for Natural Convection Model in the Debris Cooling Module; Hydrogen Burning Test (NUPEC) for the Ex-Vessel Thermal Hydraulics Module; PREMIX, PM10 (FZK) for the Steam Explosion Module; and SWISS-2 (SNL) for the Debris-Concrete Interaction Module. Second, with the Simulation Supervisory System, up to 11 analysis modules were executed concurrently in the parallel environment (currently, NUPEC uses IBM-SP2 with 72 process elements), to demonstrate the code capability and integrity. The target plant was Surry as a typical PWR and the initiation events were a 10-inch cold leg failure. The analysis is divided to two cases; one is in-vessel retention analysis when the gap cooling is effective (In-vessel scenario test), the other is analysis of phenomena event is extended to ex-vessel due to the Reactor Pressure Vessel failure when the gap cooling is not sufficient (Ex-vessel scenario test). The system verification test has confirmed that the full scope of the scenarios can be analyzed and phenomena occurred in scenarios can be simulated qualitatively reasonably considering the physical models used for the situation. The Ministry of International Trade and Industry, Japan sponsors this work. (author)

  11. Methodology, status and plans for development and assessment of Cathare code

    Energy Technology Data Exchange (ETDEWEB)

    Bestion, D.; Barre, F.; Faydide, B. [CEA - Grenoble (France)

    1997-07-01

    This paper presents the methodology, status and plans for the development, assessment and uncertainty evaluation of the Cathare code. Cathare is a thermalhydraulic code developed by CEA (DRN), IPSN, EDF and FRAMATOME for PWR safety analysis. First, the status of the code development and assessment is presented. The general strategy used for the development and the assessment of the code is presented. Analytical experiments with separate effect tests, and component tests are used for the development and the validation of closure laws. Successive Revisions of constitutive laws are implemented in successive Versions of the code and assessed. System tests or integral tests are used to validate the general consistency of the Revision. Each delivery of a code Version + Revision is fully assessed and documented. A methodology is being developed to determine the uncertainty on all constitutive laws of the code using calculations of many analytical tests and applying the Discrete Adjoint Sensitivity Method (DASM). At last, the plans for the future developments of the code are presented. They concern the optimization of the code performance through parallel computing - the code will be used for real time full scope plant simulators - the coupling with many other codes (neutronic codes, severe accident codes), the application of the code for containment thermalhydraulics. Also, physical improvements are required in the field of low pressure transients and in the modeling for the 3-D model.

  12. Results from the Coded Aperture Neutron Imaging System (CANIS)

    International Nuclear Information System (INIS)

    Brubaker, Erik; Steele, John T.; Brennan, James S.; Hilton, Nathan R.; Marleau, Peter

    2010-01-01

    Because of their penetrating power, energetic neutrons and gamma rays (∼1 MeV) offer the best possibility of detecting highly shielded or distant special nuclear material (SNM). Of these, fast neutrons offer the greatest advantage due to their very low and well understood natural background. We are investigating a new approach to fast-neutron imaging- a coded aperture neutron imaging system (CANIS). Coded aperture neutron imaging should offer a highly efficient solution for improved detection speed, range, and sensitivity. We have demonstrated fast neutron and gamma ray imaging with several different configurations of coded masks patterns and detectors including an 'active' mask that is composed of neutron detectors. Here we describe our prototype detector and present some initial results from laboratory tests and demonstrations.

  13. Results from the coded aperture neutron imaging system

    International Nuclear Information System (INIS)

    Brubaker, Erik; Steele, John T.; Brennan, James S.; Marleau, Peter

    2010-01-01

    Because of their penetrating power, energetic neutrons and gamma rays (∼1 MeV) offer the best possibility of detecting highly shielded or distant special nuclear material (SNM). Of these, fast neutrons offer the greatest advantage due to their very low and well understood natural background. We are investigating a new approach to fast-neutron imaging - a coded aperture neutron imaging system (CANIS). Coded aperture neutron imaging should offer a highly efficient solution for improved detection speed, range, and sensitivity. We have demonstrated fast neutron and gamma ray imaging with several different configurations of coded masks patterns and detectors including an 'active' mask that is composed of neutron detectors. Here we describe our prototype detector and present some initial results from laboratory tests and demonstrations.

  14. The Mistra experiment for field containment code validation first results

    International Nuclear Information System (INIS)

    Caron-Charles, M.; Blumenfeld, L.

    2001-01-01

    The MISTRA facility is a large scale experiment, designed for the purpose of thermal-hydraulics multi-D codes validation. A short description of the facility, the set up of the instrumentation and the test program are presented. Then, the first experimental results, studying helium injection in the containment and their calculations are detailed. (author)

  15. Wind power within European grid codes: Evolution, status and outlook

    DEFF Research Database (Denmark)

    Vrana, Til Kristian; Flynn, Damian; Gomez-Lazaro, Emilio

    2018-01-01

    Grid codes are technical specifications that define the requirements for any facility connected to electricity grids. Wind power plants are increasingly facing system stability support requirements similar to conventional power stations, which is to some extent unavoidable, as the share of wind...... power in the generation mix is growing. The adaptation process of grid codes for wind power plants is not yet complete, and grid codes are expected to evolve further in the future. ENTSO-E is the umbrella organization for European TSOs, seen by many as a leader in terms of requirements sophistication...... is largely based on the definitions and provisions set out by ENTSO-E. The main European grid code requirements are outlined here, including also HVDC connections and DC-connected power park modules. The focus is on requirements that are considered particularly relevant for large wind power plants...

  16. Current Status of the LIFE Fast Reactors Fuel Performance Codes

    International Nuclear Information System (INIS)

    Yacout, A.M.; Billone, M.C.

    2013-01-01

    The LIFE-4 (Rev. 1) code was calibrated and validated using data from (U,Pu)O2 mixed-oxide fuel pins and UO2 blanket rods which were irradiation tested under steady-state and transient conditions. – It integrates a broad material and fuel-pin irradiation database into a consistent framework for use and extrapolation of the database to reactor design applications. – The code is available and running on different computer platforms (UNIX & PC) – Detailed documentations of the code’s models, routines, calibration and validation data sets are available. LIFE-METAL code is based on LIFE4 with modifications to include key phenomena applicable to metallic fuel, and metallic fuel properties – Calibrated with large database from irradiations in EBR-II – Further effort for calibration and detailed documentation. Recent activities with the codes are related to reactor design studies and support of licensing efforts for 4S and KAERI SFR designs. Future activities are related to re-assessment of the codes calibration and validation and inclusion of models for advanced fuels (transmutation fuels)

  17. The status of Korean nuclear codes and standards

    International Nuclear Information System (INIS)

    Namha Kim; Jong-Hae Kim

    2005-01-01

    Korea Electric Power Industry Code (KEPIC), a set of integrated standards applicable to the design, construction and operation of electric power facilities including nuclear power plants, has been developed on the basis of referring to the prevailing U.S. codes and standards which had been applied to the electric power facilities in Korea. Being the developing and managing organization of KEPIC, Korea Electric Association (KEA) published its first edition in 1995, the second in 200,0 and is expected to publish the 2005 edition. KEPIC was applied to the construction of Ulchin Nuclear Units 5 and 6 in 1997, and will be applicable to the construction of forthcoming nuclear power plants in Korea. Along with the effectuation of the Agreement on Technical Barriers to Trade (TBT) in 1995, the international trend related to codes and standards is changing rapidly. The KEA is, therefore, making its utmost efforts so as for KEPIC to keep abreast with the changing environment in international arena. KEA notified ISO/IEC Information Centre of its acceptance of the Code of Good Practice in the Agreement on TBT. The 2005 KEPIC edition will be retrofitted according to the ISO/IEC Guide 21- Adoption of International Standards as regional or national standards. KEA's efforts will help KEPIC correspond with international standards such as ISO/IEC standards, and internationally recognized standards such as ASME codes and standards. (authors)

  18. Results from the First Validation Phase of CAP code

    International Nuclear Information System (INIS)

    Choo, Yeon Joon; Hong, Soon Joon; Hwang, Su Hyun; Kim, Min Ki; Lee, Byung Chul; Ha, Sang Jun; Choi, Hoon

    2010-01-01

    The second stage of Safety Analysis Code Development for Nuclear Power Plants was lunched on Apirl, 2010 and is scheduled to be through 2012, of which the scope of work shall cover from code validation to licensing preparation. As a part of this project, CAP(Containment Analysis Package) will follow the same procedures. CAP's validation works are organized hieratically into four validation steps using; 1) Fundamental phenomena. 2) Principal phenomena (mixing and transport) and components in containment. 3) Demonstration test by small, middle, large facilities and International Standard Problems. 4) Comparison with other containment codes such as GOTHIC or COMTEMPT. In addition, collecting the experimental data related to containment phenomena and then constructing the database is one of the major works during the second stage as a part of this project. From the validation process of fundamental phenomenon, it could be expected that the current capability and the future improvements of CAP code will be revealed. For this purpose, simple but significant problems, which have the exact analytical solution, were selected and calculated for validation of fundamental phenomena. In this paper, some results of validation problems for the selected fundamental phenomena will be summarized and discussed briefly

  19. Current status of the transient integral fuel element performance code URANUS

    International Nuclear Information System (INIS)

    Preusser, T.; Lassmann, K.

    1983-01-01

    To investigate the behavior of fuel pins during normal and off-normal operation, the integral fuel rod code URANUS has been extended to include a transient version. The paper describes the current status of the program system including a presentation of newly developed models for hypothetical accident investigation. The main objective of current development work is to improve the modelling of fuel and clad material behavior during fast transients. URANUS allows detailed analysis of experiments until the onset of strong material transport phenomena. Transient fission gas analysis is carried out due to the coupling with a special version of the LANGZEIT-KURZZEIT-code (KfK). Fuel restructuring and grain growth kinetics models have been improved recently to better characterize pre-experimental steady-state operation; transient models are under development. Extensive verification of the new version has been carried out by comparison with analytical solutions, experimental evidence, and code-to-code evaluation studies. URANUS, with all these improvements, has been successfully applied to difficult fast breeder fuel rod analysis including TOP, LOF, TUCOP, local coolant blockage and specific carbide fuel experiments. Objective of further studies is the description of transient PCMI. It is expected that the results of these developments will contribute significantly to the understanding of fuel element structural behavior during severe transients. (orig.)

  20. Status of the assessment of the spreading code Thema against the Corine experiments

    International Nuclear Information System (INIS)

    Spindler, B.; Veteau, J.M.

    1999-01-01

    In the framework of severe accident research on PWR, the Thema code aims at predicting the spreading extent of Corium in given conditions of pouring rate, initial Corium composition and temperature and considers phenomena as complex as top, bottom freezing and melting of the substrate. This paper makes the current status of the assessment of the code against the Corine experimental program which considers separate effect tests working out non freezing and low melting point simulating materials to validate some essential models present in spreading codes. Isothermal tests using water-glycerol mixtures are first considered to investigate the validity of the friction law and the extent of surface tension effects at the front. Non isothermal spreading with bottom freezing is then considered. Comparison of results of the code with known solutions of different problems related to solidification of a moving warm liquid, thermal chock and conduction in the bottom plate appears to be a very useful tool to verify the relevance of the models and to adjust numerical parameters. Finally, first spreading calculations with bottom freezing are compared with Corine experiments using the eutectic Bismuth-Tin alloy as working material. (author)

  1. THE LEGAL STATUS OF COMPANIES UNDER THE NEW CIVIL CODE

    Directory of Open Access Journals (Sweden)

    Lucian Bernd SĂULEANU

    2017-10-01

    Full Text Available The new Civil Code sets provisions regarding the liability of shareholders, organization and functioning of legal entity, annulment of documents issued by the management bodies of the legal entity, company contract, regime of contributions, company types, simple partnership, unlimited, simple limited partnership, with limited liability, joint stock, partnership limited by shares, cooperatives, other type of company.

  2. Large-Signal Code TESLA: Current Status and Recent Development

    National Research Council Canada - National Science Library

    Chernyavskiy, Igor A; Vlasov, Alexander N; Cooke, Simon J; Abe, David K; Levush, Baruch; Antonsen, Jr., Thomas M; Nguyen, Khanh T

    2008-01-01

    .... One such tool is the large-signal code TESLA, which was successfully applied for the modeling of single-beam and multiple-beam klystron devices at the Naval Research Laboratory and which is now used by number of U.S. companies...

  3. Results of the Nonelastic Reaction Code Brieff for Nuclear Data

    International Nuclear Information System (INIS)

    Duarte, H.

    2009-01-01

    We present recent changes in our nonelastic reaction code BRIEFF and especially in the fast stage of reaction described by the intranuclear cascade (INC) code BRIC. Distributions and excitation functions of residual nuclei production cross sections are shown for proton-induced reaction on target nuclei. Slight improvements are seen in the proton-induced reaction on light nuclei with a closed shell when the energy levels are taken into account in the INC stage. On the other hand, fission gives poor results in the current version. To compare to other nuclear models and LA150 libraries, BRIEFF has been incorporated into MCNPX 2.5.0. Examples of neutron production from thick target irradiation by proton beams between 30 and 350 MeV are presented. Except for some discrepancies, a good agreement with data is obtained on average. (authors)

  4. Development status of the lattice physics code in COSINE project

    Energy Technology Data Exchange (ETDEWEB)

    Chen, Y.; Yu, H.; Li, S.; Liu, Z.; Yan, Y. [State Nuclear Power Software Development Center, SNPTC, National Energy Key Laboratory of Nuclear Power Software NEKLS, North Third Ring Road, Beijing 100029 (China)

    2013-07-01

    LATC is an essential part of COSINE code package, which stands for Core and System Integrated Engine for design and analysis. LATC performs 2D multi-group assembly transport calculation and generates few group constants and the required cross-section data for CORE, the core simulator code. LATC is designed to have the capability of modeling the API 000 series assemblies. The development is a continuously improved process. Currently, LATC uses well-proven technology to achieve the key functions. In the next stage, more advanced methods and modules will be implemented. At present, WIMS and WIMS improved format library could be read in LATC code. For resonance calculation, equivalent relation with rational approximations is utilized. For transport calculation, two options are available. One choice is collision probability method in cell homogenization while discrete coordinate method in assembly homogenization, the other is method of characteristics in assembly homogenization directly. For depletion calculation, an improved linear rate 'constant power' depletion method has been developed. (authors)

  5. Development status of the lattice physics code in COSINE project

    International Nuclear Information System (INIS)

    Chen, Y.; Yu, H.; Li, S.; Liu, Z.; Yan, Y.

    2013-01-01

    LATC is an essential part of COSINE code package, which stands for Core and System Integrated Engine for design and analysis. LATC performs 2D multi-group assembly transport calculation and generates few group constants and the required cross-section data for CORE, the core simulator code. LATC is designed to have the capability of modeling the API 000 series assemblies. The development is a continuously improved process. Currently, LATC uses well-proven technology to achieve the key functions. In the next stage, more advanced methods and modules will be implemented. At present, WIMS and WIMS improved format library could be read in LATC code. For resonance calculation, equivalent relation with rational approximations is utilized. For transport calculation, two options are available. One choice is collision probability method in cell homogenization while discrete coordinate method in assembly homogenization, the other is method of characteristics in assembly homogenization directly. For depletion calculation, an improved linear rate 'constant power' depletion method has been developed. (authors)

  6. Status of development and verification of the CTFD code FLUBOX

    International Nuclear Information System (INIS)

    Graf, U.; Paradimitriou, P.

    2004-01-01

    The Computational Two-Fluid Dynamics (CTFD) code FLUBOX is developed at GRS for the multidimensional simulation of two-phase flows. FLUBOX will also be used as a multidimensional module for the German system code ATHLET. The Benchmark test cases of the European ASTAR project were used to verify the ability of the code FLUBOX to calculate typical two-phase flow phenomena and conditions: void and pressure wave propagation, phase transitions, countercurrent flows, sharp interface movements, compressible (vapour) and nearly incompressible (water) conditions, thermal and mechanical non-equilibrium, stiff source terms due to mass and heat transfer between the phases. Realistic simulations of two-phase require beside the pure conservation equations additional transport equations for the interfacial area, turbulent energy and dissipation. A transport equation for the interfacial area density covering the whole two-phase flow range is in development. First validation calculations are presented in the paper. Turbulent shear stress for two-phase flows will be modelled by the development of transport equations for the turbulent kinetic energy and the turbulent dissipation rate. The development of the transport equations is mainly based on first principles on bubbles or drops and is largely free from empiricism. (author)

  7. Status of the coupled fluid-structure dynamics code SEURBNUK

    International Nuclear Information System (INIS)

    Smith, B.L.; Yerkess, A.; Adamson, J.

    1983-07-01

    The computer code SEURBNUK-2 is used collaboratively for the study of fast reactor containment integrity. Continuous extension and improvement of the numerical modelling has been required to match the performance of the code against the COVA series of scale model experiments and the requirements of reactor safety analysis. The present capabilities of SEURBNUK-2 are outlined and the most recent development topics are summarised. For internal structures amenable to thin shell treatment, a recent addition to the code permits these to be perforated, which is useful in modelling dip-plates and above-core structures in the reactor. In safety analysis much attention is paid to the response of the roof structure to impact loading from a rising coolant slug. The typical relationship between duration of the loading and the natural period of the roof shows that a coupled fluid/structure analysis is required. This must include the roof hold-down device which can introduce a low frequency component that considerably modifies the response of the closure system. A recent major extension to the SEURBNUK modelling is the installation of a moving roof option which, together with development of the logic to link structures external to the containment vessel, provides such coupling. (Auth.)

  8. Emergency medicine summary code for reporting CT scan results: implementation and survey results.

    Science.gov (United States)

    Lam, Joanne; Coughlin, Ryan; Buhl, Luce; Herbst, Meghan; Herbst, Timothy; Martillotti, Jared; Coughlin, Bret

    2018-06-01

    The purpose of the study was to assess the emergency department (ED) providers' interest and satisfaction with ED CT result reporting before and after the implementation of a standardized summary code for all CT scan reporting. A summary code was provided at the end of all CTs ordered through the ED from August to October of 2016. A retrospective review was completed on all studies performed during this period. A pre- and post-survey was given to both ED and radiology providers. A total of 3980 CT scans excluding CTAs were ordered with 2240 CTs dedicated to the head and neck, 1685 CTs dedicated to the torso, and 55 CTs dedicated to the extremities. Approximately 74% CT scans were contrast enhanced. Of the 3980 ED CT examination ordered, 69% had a summary code assigned to it. Fifteen percent of the coded CTs had a critical or diagnostic positive result. The introduction of an ED CT summary code did not show a definitive improvement in communication. However, the ED providers are in consensus that radiology reports are crucial their patients' management. There is slightly increased satisfaction with the providers with less than 5 years of experience with the ED CT codes compared to more seasoned providers. The implementation of a user-friendly summary code may allow better analysis of results, practice improvement, and quality measurements in the future.

  9. A commentary on the current status and the future role of the European accident code

    International Nuclear Information System (INIS)

    Butland, A.T.D.

    1990-01-01

    This paper describes the history of the project to produce the European Accident code (EAC), leading to the planned release of a version of EAC-2 at the end of 1989. The requirements of a computer code to model the initiation phase of Hypothetical Core Disruptive Accidents (HCDAs) are discussed, paying particular attention to the lessons learnt in the CABRI project. The current status and content of the EAC-2 code are examined in relation to these requirements, noting how the sophisticated modelling plans for EAC-2 make it a benchmark code. The validation status of EAC-2 and future plans are discussed, noting that currently it consists solely of stand-alone validation of the modules used in EAC-2, rather than validation of the combined code. The future role of EAC-2 is briefly discussed in relation to the fast reactor plans in the EEC countries. (author)

  10. Status of emergency spray modelling in the integral code ASTEC

    International Nuclear Information System (INIS)

    Plumecocq, W.; Passalacqua, R.

    2001-01-01

    Containment spray systems are emergency systems that would be used in very low probability events which may lead to severe accidents in Light Water Reactors. In most cases, the primary function of the spray would be to remove heat and condense steam in order to reduce pressure and temperature in the containment building. Spray would also wash out fission products (aerosols and gaseous species) from the containment atmosphere. The efficiency of the spray system in the containment depressurization as well as in the removal of aerosols, during a severe accident, depends on the evolution of the spray droplet size distribution with the height in the containment, due to kinetic and thermal relaxation, gravitational agglomeration and mass transfer with the gas. A model has been developed taking into account all of these phenomena. This model has been implemented in the ASTEC code with a validation of the droplets relaxation against the CARAIDAS experiment (IPSN). Applications of this modelling to a PWR 900, during a severe accident, with special emphasis on the effect of spray on containment hydrogen distribution have been performed in multi-compartment configuration with the ASTEC V0.3 code. (author)

  11. Letter report: status on code maintenance (EQ3/6)

    International Nuclear Information System (INIS)

    Wolery, T.J.

    1995-01-01

    EQ3/6 is a software package for geochemical modeling of aqueous systems, such as water/rock or waste/water rock. It is being developed for a variety of applications in geochemical studies for the Yucca Mountain Site Characterization Project. Version 7.2a was the first version of this software to be certified for use in quality- affecting work (originally issued for use in non-quality-affecting work only on 12/28/93; certified on S/17/94). In the past year, the Version 7 line software has been maintained while the new Version 8 line has been developed. In this period, sixteen defect reports have been logged and resolved. Corrected software is being released as Version 7.2b. Defect reporting and resolution for the Version 7 line will continue until all released versions in this line are retired, perhaps six months to a year after Version 8.0 is released later this year. The Version 7 software is written in Fortran 77, technically speaking, but incorporates many aspects of older Fortran. The Version 8 software is written in a much more modern Fortran, technically somewhere between Fortran 77 and Fortran 90. Future code maintenance activities will include a more complete move to Fortran 90, as well as continued maintaining of defect reporting and resolution

  12. Addressing the scaling issue by thermalhydraulic system codes: recent results

    International Nuclear Information System (INIS)

    D'auria, F.; Cherubini, M.; Galassi, G.M.; Muellner, N. . E-mail of corresponding author: dauria@ing.unipi.it; D'auria, F.)

    2005-01-01

    This lecture presents an introduction into the scaling issue following a 'top-down' approach. This means, recent studies which deal with a scaling analysis in LWR with special regards to the WWER Russian reactor type are presented to demonstrate important phenomena for scaling, to be more precise, the counterpart test (CT) methodology. As an example, one CT, a Small Break LOCA carried out in the PSB facility, is presented. PSB is a full height, full pressure rig that reproduces a WWER 1000, power and volume scaling factor is 1:300. The CT has been designed deriving boundary and initial condition from the same test performed in LOBI (that reproduces a PWR). The adopted scaling approach is based on the selection of a few characteristic parameters. They are chosen taking into account their relevance in the behaviour of the transient. The calculation of the SBLOCA has been performed using Relap5/Mod3.3 computer code and its accuracy has been demonstrated by qualitative and quantitative evaluation. For the quantitative evaluation the use of the FFT Based Method is foreseen and the fulfilment of its limits has been obtained. The aim of the example is to give an overview about the theoretical concepts of scaling, which is termed the s caling strategy , and comprises the steps of the selected scaling approach. At the same time interesting results from ongoing research projects will be presented. Comparing experimental data it was found that the investigated facilities show similar behaviour concerning the time trends, and are able to predict on a qualitative level the same thermal hydraulic phenomena. Main obtained results are summarized as follows: PSB and LOBI main parameters have similar trends. This is a confirmation of the validity of the adopted scaling approach and shows that PWR and WWER reactor type behaviour are very close to each other. No new phenomena occur during the CT, notwithstanding the two facilities have a different lay out, and the already known

  13. Current status and applications of intergrated safety assessment and simulation code system for ISA

    Energy Technology Data Exchange (ETDEWEB)

    Izquierdo, J. M.; Hortal, J.; Perea, M. Sanchez; Melendez, E. [Modeling and Simulation Area (MOSI), Nuclear Safety Council (CSN), Madrid (Spain); Queral, E.; Rivas-Lewicky, J. [Energy and Fuels Department, Technical University of Madrid (UPM), Madrid (Spain)

    2017-03-15

    This paper reviews current status of the unified approach known as integrated safety assessment (ISA), as well as the associated SCAIS (simulation codes system for ISA) computer platform. These constitute a proposal, which is the result of collaborative action among the Nuclear Safety Council (CSN), University of Madrid (UPM), and NFQ Solutions S.L, aiming to allow independent regulatory verification of industry quantitative risk assessments. The content elaborates on discussions of the classical treatment of time in conventional probabilistic safety assessment (PSA) sequences and states important conclusions that can be used to avoid systematic and unacceptable underestimation of the failure exceedance frequencies. The unified ISA method meets this challenge by coupling deterministic and probabilistic mutual influences. The feasibility of the approach is illustrated with some examples of its application to a real size plant.

  14. Thermal hydraulic codes for LWR safety analysis - present status and future perspective

    Energy Technology Data Exchange (ETDEWEB)

    Staedtke, H. [Commission of the European Union, Ispra (Italy)

    1997-07-01

    The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved.

  15. Thermal hydraulic codes for LWR safety analysis - present status and future perspective

    International Nuclear Information System (INIS)

    Staedtke, H.

    1997-01-01

    The aim of the present paper is to give a review on the current status and future perspective of present best-estimate Thermal Hydraulic codes. Reference is made to internationally well-established codes which have reached a certain state of maturity. The first part of the paper deals with the common basic code features with respect to the physical modelling and their numerical methods used to describe complex two-phase flow and heat transfer processes. The general predictive capabilities are summarized identifying some remaining code deficiencies and their underlying limitations. The second part discusses various areas including physical modelling, numerical techniques and informatic structure where the codes could be substantially improved

  16. Verification of SACI-2 computer code comparing with experimental results of BIBLIS-A and LOOP-7 computer code

    International Nuclear Information System (INIS)

    Soares, P.A.; Sirimarco, L.F.

    1984-01-01

    SACI-2 is a computer code created to study the dynamic behaviour of a PWR nuclear power plant. To evaluate the quality of its results, SACI-2 was used to recalculate commissioning tests done in BIBLIS-A nuclear power plant and to calculate postulated transients for Angra-2 reactor. The results of SACI-2 computer code from BIBLIS-A showed as much good agreement as those calculated with the KWU Loop 7 computer code for Angra-2. (E.G.) [pt

  17. Recent status and results from BES

    International Nuclear Information System (INIS)

    Wang, P.

    1994-01-01

    Recent results on the τ leptonic mass by the analysis of several one prong decay channels, the search of gluonium state near J/ψ which was proposed to explain the so-called ρπ puzzle, and some preliminary results of D s meson from BES (Beijing Electron Spectrometer) are reported. Future plans of upgrading BEPC (Beijing Electron-Positron Collider) and BES are also described. (author). 3 refs., 1 fig., 1 tab

  18. Wide Area Wind Field Monitoring Status & Results

    Energy Technology Data Exchange (ETDEWEB)

    Alan Marchant; Jed Simmons

    2011-09-30

    Volume-scanning elastic has been investigated as a means to derive 3D dynamic wind fields for characterization and monitoring of wind energy sites. An eye-safe volume-scanning lidar system was adapted for volume imaging of aerosol concentrations out to a range of 300m. Reformatting of the lidar data as dynamic volume images was successfully demonstrated. A practical method for deriving 3D wind fields from dynamic volume imagery was identified and demonstrated. However, the natural phenomenology was found to provide insufficient aerosol features for reliable wind sensing. The results of this study may be applicable to wind field measurement using injected aerosol tracers.

  19. Status of design code work for metallic high temperature components

    International Nuclear Information System (INIS)

    Bieniussa, K.; Seehafer, H.J.; Over, H.H.; Hughes, P.

    1984-01-01

    The mechanical components of high temperature gas-cooled reactors, HTGR, are exposed to temperatures up to about 1000 deg. C and this in a more or less corrosive gas environment. Under these conditions metallic structural materials show a time-dependent structural behavior. Furthermore changes in the structure of the material and loss of material in the surface can result. The structural material of the components will be stressed originating from load-controlled quantities, for example pressure or dead weight, and/or deformation-controlled quantities, for example thermal expansion or temperature distribution, and thus it can suffer rowing permanent strains and deformations and an exhaustion of the material (damage) both followed by failure. To avoid a failure of the components the design requires the consideration of the following structural failure modes: ductile rupture due to short-term loadings; creep rupture due to long-term loadings; reep-fatigue failure due to cyclic loadings excessive strains due to incremental deformation or creep ratcheting; loss of function due to excessive deformations; loss of stability due to short-term loadings; loss of stability due to long-term loadings; environmentally caused material failure (excessive corrosion); fast fracture due to instable crack growth

  20. Recent results in the decoding of Algebraic geometry codes

    DEFF Research Database (Denmark)

    Høholdt, Tom; Jensen, Helge Elbrønd; Nielsen, Rasmus Refslund

    1998-01-01

    We analyse the known decoding algorithms for algebraic geometry codes in the case where the number of errors is [(dFR-1)/2]+1, where dFR is the Feng-Rao distance......We analyse the known decoding algorithms for algebraic geometry codes in the case where the number of errors is [(dFR-1)/2]+1, where dFR is the Feng-Rao distance...

  1. BABAR Experiment Status and Recent Results

    Energy Technology Data Exchange (ETDEWEB)

    De Nardo, G.

    2004-10-04

    The BaBar detector at SLAC PEP-II asymmetric B-Factory has collected between 1999 and 2002 a data sample of 88 millions {Upsilon}(4S) {yields} B{bar B} decays. We present here recent measurements of branching fractions and time-dependent CP-violating asymmetries of neutral B mesons decays to several CP eigenstates. We present the results on the decays to (c{bar c}) K{sub S}{sup 0}/K{sub L}{sup 0}, which are related in the Standard Model to the angle {beta} of the Unitarity Triangle of the Cabibbo-Kobayashi-Maskawa quark mixing matrix. Moreover we present the branching fractions and the CP-asymmetries of charmless two body decays related to the angle {alpha}.

  2. The Majorana Demonstrator Status and Preliminary Results

    Science.gov (United States)

    Yu, C.-H.; Alvis, S. I.; Arnquist, I. J.; Avignone, F. T.; Barabash, A. S.; Barton, C. J.; Bertrand, F. E.; Bode, T.; Brudanin, V.; Busch, M.; Buuck, M.; Caldwell, T. S.; Chan, Y.-D.; Christofferson, C. D.; Chu, P.-H.; Cuesta, C.; Detwiler, J. A.; Dunagan, C.; Efremenko, Yu; Ejiri, H.; Elliott, S. R.; Gilliss, T.; Giovanetti, G. K.; Green, M.; Gruszko, J.; Guinn, I. S.; Guiseppe, V. E.; Haufe, C. R.; Hehn, L.; Henning, R.; Hoppe, E. W.; Howe, M. A.; Keeter, K. J.; Kidd, M. F.; Konovalov, S. I.; Kouzes, R. T.; Lopez, A. M.; Martin, R. D.; Massarczyk, R.; Meijer, S. J.; Mertens, S.; Myslik, J.; Othman, G.; Pettus, W.; Poon, A. W. P.; Radford, D. C.; Rager, J.; Reine, A. L.; Rielage, K.; Ruof, N. W.; Shanks, B.; Shirchenko, M.; Suriano, A. M.; Tedeschi, D.; Varner, R. L.; Vasilyev, S.; Vetter, K.; Vorren, K.; White, B. R.; Wilkerson, J. F.; Wiseman, C.; Xu, W.; Yakushev, E.; Yumatov, V.; Zhitnikov, I.; Zhu, B. Z.

    2018-05-01

    The MAJORANA Collaboration is using an array of high-purity Ge detectors to search for neutrinoless double-beta decay in 76Ge. Searches for neutrinoless double-beta decay are understood to be the only viable experimental method for testing the Majorana nature of the neutrino. Observation of this decay would imply violation of lepton number, that neutrinos are Majorana in nature, and provide information on the neutrino mass. The MAJORANA DEMONSTRATOR comprises 44.1 kg of p-type point-contact Ge detectors (29.7 kg enriched in 76Ge) surrounded by a low-background shield system. The experiment achieved a high efficiency of converting raw Ge material to detectors and an unprecedented detector energy resolution of 2.5 keV FWHM at Qββ. The MAJORANA collaboration began taking physics data in 2016. This paper summarizes key construction aspects of the Demonstrator and shows preliminary results from initial data.

  3. FACT — STATUS AND FIRST RESULTS

    Directory of Open Access Journals (Sweden)

    Daniela Dorner

    2014-06-01

    Full Text Available FACT is the first imaging Cherenkov telescope based on a camera using solid state photosensors (Geigermode Avalanche Photodiodes G-APD aka SiPM. Since October 2011, it has been taking data regularly. Apart from commissioning and calibration measurements, it has already started regular operation, where the main goal is to do long-term monitoring of bright TeV blazars. In June 2012, a flare of Mrk 501 was observed. Thanks to the robustness of the G-APDs, observations can be carried out during strong moon light without aging of the sensors. This improves the duty cycle of the instrument and provides better statistics for long-term light curves. The telescope, situated on the Canary Island of La Palma, is operated, already now, remotely from central Europe. For the future, robotic operation is planned. We report on our experiences during the commissioning, and we present first results from the first 1.5 years of observations.

  4. Post-processing of the TRAC code's results

    International Nuclear Information System (INIS)

    Baron, J.H.; Neuman, D.

    1987-01-01

    The TRAC code serves for the analysis of accidents in nuclear installations from the thermohydraulic point of view. A program has been developed with the aim of processing the information rapidly generated by the code, with screening graph capacity, both in high and low resolution, or either in paper through printer or plotter. Although the programs are intended to be used after the TRAC runs, they may be also used even when the program is running so as to observe the calculation process. The advantages of employing this type of tool, its actual capacity and its possibilities of expansion according to the user's needs are herein described. (Author)

  5. First Results for Fluid Dynamics, Neutronics and Fission Product Behaviour in HTR applying the HTR Code Package (HCP) Prototype

    International Nuclear Information System (INIS)

    Allelein, H.-J.; Kasselmann, S.; Xhonneux, A.; Lambertz, D.

    2014-01-01

    To simulate the different aspects of High Temperature Reactor (HTR) cores, a variety of specialized computer codes have been developed at Forschungszentrum Jülich (IEK-6) and Aachen University (LRST) in the last decades. In order to preserve knowledge, to overcome present limitations and to make these codes applicable to modern computer clusters, these individual programs are being integrated into a consistent code package. The so-called HTR code package (HCP) couples the related and recently applied physics models in a highly integrated manner and therefore allows to simulate phenomena with higher precision in space and time while at the same time applying state-of-the-art programming techniques and standards. This paper provides an overview of the status of the HCP and reports about first benchmark results for an HCP prototype which couples the fluid dynamics and time dependent neutronics code MGT-3D, the burn up code TNT and the fission product release code STACY. Due to the coupling of MGT-3D and TNT, a first step towards a new reactor operation and accident simulation code was made, where nuclide concentrations calculated by TNT are fed back into a new spectrum code of the HCP. Selected operation scenarios of the HTR-Module 200 concept plant and the HTTR were chosen to be simulated with the HCP prototype. The fission product release during normal operation conditions will be calculated with STACY based on a core status derived from SERPENT and MGT–3D. Comparisons will be shown against data generated by the legacy codes VSOP99/11, NAKURE and FRESCO-II. (author)

  6. THE LEGAL STATUS OF PROFESSIONALS IN THE CONTEXT OF CHANGES BROUGHT BY THE NEW CIVIL CODE

    Directory of Open Access Journals (Sweden)

    OANA-CARMEN RĂVAŞ

    2014-12-01

    Full Text Available Adoption of the New Civil Code (NCC meant a "turning point" for the radical concept of the subjects participating in legal relations which, according to the Commercial Code (now repealed almost all provisions usually were traders. Currently, the Unification of Private Law, according to the monistic conception embraced by NCC there are a series of difficulties in the conceptual framework of "professionals", the "company" and, especially, the professional traders. Professional traders are individuals: the individual, authorized individual and family business. The legal status of the three categories of individuals falling into the category of professionals traders is regulated by Ordinance no. 44/2008, amended.

  7. Reactivity Insertion Accident (RIA) Capability Status in the BISON Fuel Performance Code

    Energy Technology Data Exchange (ETDEWEB)

    Williamson, Richard L. [Idaho National Lab. (INL), Idaho Falls, ID (United States); Folsom, Charles Pearson [Idaho National Lab. (INL), Idaho Falls, ID (United States); Pastore, Giovanni [Idaho National Lab. (INL), Idaho Falls, ID (United States); Veeraraghavan, Swetha [Idaho National Lab. (INL), Idaho Falls, ID (United States)

    2016-05-01

    One of the Challenge Problems being considered within CASL relates to modelling and simulation of Light Water Reactor LWR) fuel under Reactivity Insertion Accident (RIA) conditions. BISON is the fuel performance code used within CASL for LWR fuel under both normal operating and accident conditions, and thus must be capable of addressing the RIA challenge problem. This report outlines required BISON capabilities for RIAs and describes the current status of the code. Information on recent accident capability enhancements, application of BISON to a RIA benchmark exercise, and plans for validation to RIA behavior are included.

  8. Comparison of results between different precision MAFIA codes

    International Nuclear Information System (INIS)

    Farkas, D.; Tice, B.

    1990-01-01

    In order to satisfy the inquiries of the Mafia Code users at SLAC, an evaluation of these codes was done. This consisted of running a cavity with known solutions. This study considered only the time independent solutions. No wake-field calculations were tried. The two machines involved were the NMFECC Cray (e-machine) at LLNL and the IBM/3081 at SLAC. The primary difference between the implementation of the codes on these machines is that the Cray has 64-bit accuracy while the IBM version has 32-bit accuracy. Unfortunately this study is incomplete as the Post-processor (P3) could not be made to work properly on the SLAC machine. This meant that no q's were calculated and no field patterns were generated. A certain amount of guessing had to be done when constructing the comparison tables. This problem aside, the probable conclusions that may be drawn are: (1) thirty-two bit precision is adequate for frequency determination; (2) sixty-four bit precision is desirable for field determination. This conclusion is deduced from the accuracy statistics. The cavity selected for study was a rectangular one with the dimensions (4,3,5) in centimeters. Only half of this cavity was used (2,3,5) with the x dimension being the one that was halved. The boundary conditions (B.C.) on the plane of symmetry were varied between Neumann and Dirichlet so as to cover all possible modes. Ten (10) modes were ran for each boundary condition

  9. Current Status of the Elevated Temperature Structure Design Codes for VHTR

    International Nuclear Information System (INIS)

    Kim, Jong-Bum; Kim, Seok-Hoon; Park, Keun-Bae; Lee, Won-Jae

    2006-01-01

    An elevated temperature structure design and analysis is one of the key issues in the VHTR (Very High Temperature Reactor) project to achieve an economic production of hydrogen which will be an essential energy source for the near future. Since the operating temperature of a VHTR is above 850 .deg. C, the existing code and standards are insufficient for a high temperature structure design. Thus the issues concerning a material selection and behaviors are being studied for the main structural components of a VHTR in leading countries such as US, France, UK, and Japan. In this study, the current status of the ASME code, French RCC-MR, UK R5, and Japanese code were investigated and the necessary R and D items were discussed

  10. First results for fluid dynamics, neutronics and fission product behavior in HTR applying the HTR code package (HCP) prototype

    Energy Technology Data Exchange (ETDEWEB)

    Allelein, H.-J., E-mail: h.j.allelein@fz-juelich.de [Forschungszentrum Jülich, 52425 Jülich (Germany); Institute for Reactor Safety and Reactor Technology, RWTH Aachen University, 52064 Aachen (Germany); Kasselmann, S.; Xhonneux, A.; Tantillo, F.; Trabadela, A.; Lambertz, D. [Forschungszentrum Jülich, 52425 Jülich (Germany)

    2016-09-15

    To simulate the different aspects of High Temperature Reactor (HTR) cores, a variety of specialized computer codes have been developed at Forschungszentrum Jülich (IEK-6) and Aachen University (LRST) in the last decades. In order to preserve knowledge, to overcome present limitations and to make these codes applicable to modern computer clusters, these individual programs are being integrated into a consistent code package. The so-called HTR code package (HCP) couples the related and recently applied physics models in a highly integrated manner and therefore allows to simulate phenomena with higher precision in space and time while at the same time applying state-of-the-art programming techniques and standards. This paper provides an overview of the status of the HCP and reports about first benchmark results for an HCP prototype which couples the fluid dynamics and time dependent neutronics code MGT-3D, the burn up code TNT and the fission product release code STACY. Due to the coupling of MGT-3D and TNT, a first step towards a new reactor operation and accident simulation code was made, where nuclide concentrations calculated by TNT lead to new cross sections, which are fed back into MGT-3D. Selected operation scenarios of the HTR-Module 200 concept plant and the HTTR were chosen to be simulated with the HCP prototype. The fission product release during normal operation conditions will be calculated with STACY based on a core status derived from SERPENT and MGT-3D. Comparisons will be shown against data generated by SERPENT and the legacy codes VSOP99/11, NAKURE and FRESCO-II.

  11. Status inconsistency in groups : How discrepancies between instrumental and expressive status result in symptoms of stress

    NARCIS (Netherlands)

    van de Brake, Hendrik; Grow, André; Dijkstra, Jan Kornelis

    This study examines whether a mismatch between the positions that individuals hold in different status hierarchies results in symptoms of stress. Prior research has focused on inconsistencies between socioeconomic status dimensions (e.g., education and income) and did not find a significant relation

  12. The current status of cyanobacterial nomenclature under the "prokaryotic" and the "botanical" code.

    Science.gov (United States)

    Oren, Aharon; Ventura, Stefano

    2017-10-01

    Cyanobacterial taxonomy developed in the botanical world because Cyanobacteria/Cyanophyta have traditionally been identified as algae. However, they possess a prokaryotic cell structure, and phylogenetically they belong to the Bacteria. This caused nomenclature problems as the provisions of the International Code of Nomenclature for algae, fungi, and plants (ICN; the "Botanical Code") differ from those of the International Code of Nomenclature of Prokaryotes (ICNP; the "Prokaryotic Code"). While the ICN recognises names validly published under the ICNP, Article 45(1) of the ICN has not yet been reciprocated in the ICNP. Different solutions have been proposed to solve the current problems. In 2012 a Special Committee on the harmonisation of the nomenclature of Cyanobacteria was appointed, but its activity has been minimal. Two opposing proposals to regulate cyanobacterial nomenclature were recently submitted, one calling for deletion of the cyanobacteria from the groups of organisms whose nomenclature is regulated by the ICNP, the second to consistently apply the rules of the ICNP to all cyanobacteria. Following a general overview of the current status of cyanobacterial nomenclature under the two codes we present five case studies of genera for which nomenclatural aspects have been discussed in recent years: Microcystis, Planktothrix, Halothece, Gloeobacter and Nostoc.

  13. Current status of the reactor physics code WIMS and recent developments

    International Nuclear Information System (INIS)

    Lindley, B.A.; Hosking, J.G.; Smith, P.J.; Powney, D.J.; Tollit, B.S.; Newton, T.D.; Perry, R.; Ware, T.C.; Smith, P.N.

    2017-01-01

    Highlights: • The current status of the WIMS reactor physics code is presented. • Applications range from 2D lattice calculations up to 3D whole core geometries. • Gamma transport and thermal-hydraulic feedback models added. • Calculations methodologies described for several Gen II, III and IV reactor types. - Abstract: The WIMS modular reactor physics code has been under continuous development for over fifty years. This paper discusses the current status of WIMS and recent developments, in particular developments to the resonance shielding methodology and 3D transport solvers. Traditionally, WIMS is used to perform 2D lattice calculations, typically to generate homogenized reactor physics parameters for a whole core code such as PANTHER. However, with increasing computational resources there has been a growing trend for performing transport calculations on larger problems, up to and including 3D full core models. To this end, a number of the WIMS modules have been parallelised to allow efficient performance for whole core calculations, and WIMS includes a 3D method of characteristics solver with reflective and once-through tracking methods, which can be used to analyse problems of varying size and complexity. A time-dependent flux solver has been incorporated and thermal-hydraulic modelling capability is also being added to allow steady-state and transient coupled calculations to be performed. WIMS has been validated against a range of experimental data and other codes, in particular for water and graphite moderated thermal reactors. Future developments will include improved parallelization, enhancing the thermal-hydraulic feedback models and validating the WIMS/PANTHER code system for BWRs and fast reactors.

  14. Bias with respect to socioeconomic status: A closer look at zip code matching in a pneumococcal vaccine effectiveness study

    Directory of Open Access Journals (Sweden)

    Ruth Link-Gelles

    2016-12-01

    Full Text Available In 2010, 13-valent pneumococcal conjugate vaccine (PCV13 was introduced in the US for prevention of invasive pneumococcal disease in children. Individual-level socioeconomic status (SES is a potential confounder of the estimated effectiveness of PCV13 and is often controlled for in observational studies using zip code as a proxy. We assessed the utility of zip code matching for control of SES in a post-licensure evaluation of the effectiveness of PCV13 (calculated as [1-matched odds ratio]*100. We used a directed acyclic graph to identify subsets of confounders and collected SES variables from birth certificates, geocoding, a parent interview, and follow-up with medical providers. Cases tended to be more affluent than eligible controls (for example, 48.3% of cases had private insurance vs. 44.6% of eligible controls, but less affluent than enrolled controls (52.9% of whom had private insurance. Control of confounding subsets, however, did not result in a meaningful change in estimated vaccine effectiveness (original estimate: 85.1%, 95% CI 74.8–91.9%; adjusted estimate: 82.5%, 95% CI 65.6–91.1%. In the context of a post-licensure vaccine effectiveness study, zip code appears to be an adequate, though not perfect, proxy for individual SES. Keywords: Socioeconomic status, PCV13, Pneumococcus, Pneumococcal vaccine, Vaccine effectiveness, Matched case-control

  15. Towards acute pediatric status epilepticus intervention teams: Do we need "Seizure Codes"?

    Science.gov (United States)

    Stredny, Coral M; Abend, Nicholas S; Loddenkemper, Tobias

    2018-05-01

    To identify areas of treatment delay and barriers to care in pediatric status epilepticus, review ongoing quality improvement initiatives, and provide suggestions for further innovations to improve and standardize these patient care processes. Narrative review of current status epilepticus management algorithms, anti-seizure medication administration and outcomes associated with delays, and initiatives to improve time to treatment. Articles reviewing or reporting quality improvement initiatives were identified through a PubMed search with keywords "status epilepticus," "quality improvement," "guideline adherence," and/or "protocol;" references of included articles were also reviewed. Rapid initiation and escalation of status epilepticus treatment has been associated with shortened seizure duration and more favorable outcomes. Current evidence-based guidelines for management of status epilepticus propose medication algorithms with suggested times for each management step. However, time to antiseizure medication administration for pediatric status epilepticus remains delayed in both the pre- and in-hospital settings. Barriers to timely treatment include suboptimal preventive care, inaccurate seizure detection, infrequent or restricted use of home rescue medications by caregivers and pre-hospital emergency personnel, delayed summoning and arrival of emergency personnel, and use of inappropriately dosed medications. Ongoing quality improvement initiatives in the pre- and in-hospital settings targeting these barriers are reviewed. Improved preventive care, seizure detection, and rescue medication education may advance pre-hospital management, and we propose the use of acute status epilepticus intervention teams to initiate and incorporate in-hospital interventions as time-sensitive "Seizure Code" emergencies. Copyright © 2018 British Epilepsy Association. Published by Elsevier Ltd. All rights reserved.

  16. Analysis of results of AZTRAN and AZKIND codes for a BWR

    International Nuclear Information System (INIS)

    Bastida O, G. E.; Vallejo Q, J. A.; Galicia A, J.; Francois L, J. L.; Xolocostli M, J. V.; Rodriguez H, A.; Gomez T, A. M.

    2016-09-01

    This paper presents an analysis of results obtained from simulations performed with the neutron transport code AZTRAN and the kinetic code of neutron diffusion AZKIND, based on comparisons with models corresponding to a typical BWR, in order to verify the behavior and reliability of the values obtained with said code for its current development. For this, simulations of different geometries were made using validated nuclear codes, such as CASMO, MCNP5 and Serpent. The results obtained are considered adequate since they are comparable with those obtained and reported with other codes, based mainly on the neutron multiplication factor and the power distribution of the same. (Author)

  17. Status of the MELTSPREAD-1 computer code for the analysis of transient spreading of core debris melts

    International Nuclear Information System (INIS)

    Farmer, M.T.; Sienicki, J.J.; Spencer, B.W.; Chu, C.C.

    1992-01-01

    A transient, one dimensional, finite difference computer code (MELTSPREAD-1) has been developed to predict spreading behavior of high temperature melts flowing over concrete and/or steel surfaces submerged in water, or without the effects of water if the surface is initially dry. This paper provides a summary overview of models and correlations currently implemented in the code, code validation activities completed thus far, LWR spreading-related safety issues for which the code has been applied, and the status of documentation for the code

  18. The current status and future plans for the Monte Carlo codes MONK and MCBEND

    International Nuclear Information System (INIS)

    Smith, N.; Shuttleworth, T.; Grimstone, M.; Hutton, L.; Armishaw, M.; Bird, A.; France, N.; Connolly, S.

    2001-01-01

    MONK and MCBEND are software tools used for criticality/reactor physics and shielding/dosimetry/general radiation transport applications respectively. The codes are developed by a collaboration comprising AEA Technology and BNFL, and AEA Technology's ANSWERS Software Service supplies them to customers throughout the world on a commercial basis. In keeping with this commercial nature it is vital that the codes' development programmes evolve to meet the diverse expectations of the current and potential customer base. This involves striving to maintain an acceptable balance in the development of the various components that comprise a modern software package. This paper summarises the current status of MONK and MCBEND by indicating how the task of trying to achieve this difficult balance has been addressed in the recent past and is being addressed for the future. (orig.)

  19. Status of the development of a fully integrated code system for the simulation of high temperature reactor cores

    Energy Technology Data Exchange (ETDEWEB)

    Kasselmann, Stefan, E-mail: s.kasselmann@fz-juelich.de [Institute of Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6), Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Druska, Claudia [Institute of Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6), Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Herber, Stefan [Institute of Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6), Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Lehrstuhl für Reaktorsicherheit und -technik, RWTH Aachen, 52062 Aachen (Germany); Jühe, Stephan [Lehrstuhl für Reaktorsicherheit und -technik, RWTH Aachen, 52062 Aachen (Germany); Keller, Florian; Lambertz, Daniela; Li, Jingjing; Scholthaus, Sarah; Shi, Dunfu [Institute of Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6), Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Xhonneux, Andre; Allelein, Hans-Josef [Institute of Energy and Climate Research, Nuclear Waste Management and Reactor Safety (IEK-6), Forschungszentrum Jülich GmbH, 52425 Jülich (Germany); Lehrstuhl für Reaktorsicherheit und -technik, RWTH Aachen, 52062 Aachen (Germany)

    2014-05-01

    The HTR code package (HCP) is a new code system, which couples a variety of stand-alone codes for the simulation of different aspects of HTR. HCP will allow the steady-state and transient operating conditions of a 3D reactor core to be simulated including new features such as spatially resolved fission product release calculations or production and transport of graphite dust. For this code the latest programming techniques and standards are applied. As a first step an object-oriented data model was developed which features a high level of readability because it is based on problem-specific data types like Nuclide, Reaction, ReactionHandler, CrossSectionSet, etc. Those classes help to encapsulate and therefore hide specific implementations, which are not relevant with respect to physics. HCP will make use of one consistent data library for which an automatic generation tool was developed. The new data library consists of decay information, cross sections, fission yields, scattering matrices etc. for all available nuclides (e.g. ENDF/B-VII.1). The data can be stored in different formats such as binary, ASCII or XML. The new burn up code TNT (Topological Nuclide Transmutation) applies graph theory to represent nuclide chains and to minimize the calculation effort when solving the burn up equations. New features are the use of energy-dependent fission yields or the calculation of thermal power for decay, fission and capture reactions. With STACY (source term analysis code system) the fission product release for steady state as well as accident scenarios can be simulated for each fuel batch. For a full-core release calculation several thousand fuel elements are tracked while passing through the core. This models the stochastic behavior of a pebble bed in a realistic manner. In this paper we report on the current status of the HCP and present first results, which prove the applicability of the selected approach.

  20. Compliance status of product labels to the international code on marketing of breast milk substitutes.

    Science.gov (United States)

    Ergin, Ahmet; Hatipoğlu, Celile; Bozkurt, Ali Ihsan; Erdoğan, Aslı; Güler, Serdar; Ince, Gülberat; Kavurgacı, Nuran; Oz, Ahmet; Yeniay, Mustafa K

    2013-01-01

    The aim of this study was to determine the compliance status of product labels regarding Article 9 of the International Code on Marketing of Breast-milk Substitutes (the Code) in Denizli province, Turkey. A cross-sectional study design was employed to determine the compliance status. The product labels were obtained from a convenience sample of five supermarkets, one store and 5 pharmacies in the City centre and district of Honaz. Using a data collection form prepared by previously published studies, data were collected between July 26, 2010 and August 06, 2010. Data collection form included 13 criteria. In addition, we checked the boxes for the availability of a Turkish written label. Forty product labels of 7 companies were reached and evaluated. These products consisted of 83.0% of the products marketed by these companies in Turkey. Thirty seven (92.5%) of the labels violated Article 9 of the Code in terms of one or more criteria. Thirty four (85.0%) of the labels had photos or pictures idealizing the use of infant formula. Nine (22.5%) had a photo, a picture or any representation of an infant, and five (12.5%) had text which idealize the use of infant formula or discouraging breastfeeding. Eight (20%) did not state that breastfeeding is the best. Four (10%) had a term such as 'similar to breast milk or human milk'. In conclusion, the majority of the product labels of breast milk substitutes marketed in our country violate the Code. It is appropriate that the Turkish Ministry of Health, medical organizations, companies, and NGOs work more actively to increase awareness of this issue.

  1. Relationship between neighborhood socioeconomic status and venous thromboembolism: results from a population-based study.

    Science.gov (United States)

    Kort, D; van Rein, N; van der Meer, F J M; Vermaas, H W; Wiersma, N; Cannegieter, S C; Lijfering, W M

    2017-12-01

    Essentials Literature on socioeconomic status (SES) and incidence of venous thromboembolism (VTE) is scarce. We assessed neighborhood SES with VTE risk in a population of over 1.4 million inhabitants. Higher neighborhood SES was associated with lower incidence of VTE. These findings are helpful to inform policy and resource allocation in health systems. Background The association between socioeconomic status and arterial cardiovascular disease is well established. However, despite its high burden of disability-adjusted life years, little research has been carried out to determine whether socioeconomic status is associated with venous thromboembolism. Objective To determine if neighborhood socioeconomic status is associated with venous thromboembolism in a population-based study from the Netherlands. Methods We identified all patients aged 15 years and older with a first event of venous thromboembolism from inhabitants who lived in the urban districts of The Hague, Leiden and Utrecht in the Netherlands in 2008-2012. Neighborhood socioeconomic status was based on the status score, which combines educational level, income and unemployment on a four-digit postal code level. Incidence rate ratios of venous thromboembolism were calculated for different levels of neighborhood socioeconomic status, with adjustments for age and sex. Results A total of 7373 patients with a first venous thromboembolism (median age 61 years; 50% deep vein thrombosis) were identified among more than 1.4 million inhabitants. Higher neighborhood SES was associated with lower incidence of VTE. In the two highest status score groups (i.e. the 95-99th and > 99th percentile), the adjusted incidence rate ratios were 0.91 (95% confidence interval [CI], 0.84-1.00) and 0.80 (95% CI, 0.69-0.93), respectively, compared with the reference status score group (i.e. 30-70th percentile). Conclusions High neighborhood socioeconomic status is associated with a lower risk of first venous thromboembolism. © 2017

  2. Status of development of a code for predicting the migration of ground additions - MOGRA

    International Nuclear Information System (INIS)

    Amano, Hikaru; Uchida, Shigeo; Matsuoka, Syungo; Ikeda, Hiroshi; Hayashi, Hiroko; Kurosawa, Naohiro

    2003-01-01

    MOGRA (Migration Of GRound Additions) is a migration prediction code for toxic ground additions including radioactive materials in a terrestrial environment. MOGRA consists of computational codes that are applicable to various evaluation target systems, and can be used on personal computers. The computational code has the dynamic compartment analysis block at its core, the graphical user interface (GUI) for computation parameter settings and results displays, data bases and so on. The compartments are obtained by classifying various natural environments into groups that exhibit similar properties. These codes are able to create or delete compartments and set the migration of environmental-load substances between compartments by a simple mouse operation. The system features universality and excellent expandability in the application of computations to various nuclides. (author)

  3. Status and first Results of the CBM TRD Prototype Development

    International Nuclear Information System (INIS)

    Arend, Andreas

    2013-01-01

    The measurement of decay products from rare particles in the CBM experiment defines the requirements for the used detector systems. This report describes the approaches for the Transition Radiation Detector to fulfil these requirements and presents the current status of the prototype development. First results from beam tests with these prototypes are discussed.

  4. Development Status of Diffusion Code RAST-K 2.0 at UNIST

    Energy Technology Data Exchange (ETDEWEB)

    Park, Minyong; Zheng, Youqi; Choe, Jiwon; Zhang, Peng; Lee, Deokjung [UNIST, Ulsan (Korea, Republic of); Lee, Eunki; Shin, Hocheol [KHNP Central Research Institute, Daejeon (Korea, Republic of)

    2016-10-15

    The non-linear scheme was used based on the 2-group CMFD and a three dimensional multi -group unified nodal method (UNM). To consider the history effects, the main heavy isotopes were tracked by micro-depletion module using CRAM. The simplified 1-D single channel thermal hydraulic solver from nTACER is implemented. The θ method was adopted in the transient calculation. To get detailed pin-wise power and burnup distribution, Pin power reconstruction module was implemented. Also automatic control logic to calculate MTC, FTC, control rod worth was implemented. To perform multicycle analysis, restart and shuffling/rotation module has been implemented. To link between CASMO-4E and RAST-K 2.0, CATORA (CASMO TO RAST-K 2.0) code was developed. Unlike the other diffusion codes, RAST-K 2.0 depletion module uses CRAM and extended depletion chain for fission products. Most lattice codes give cumulative fission yield of Pm-149 without considering Pm-148 and Pm-149 capture reaction which will lead to the increase of Sm-149 number density. This paper reports the status of RAST-K 2.0 code development at UNIST. The new code applies a new kernel based on the two-node UNM with CMFD, and θ method for kinetic calculation. Also, the microdepletion calculation is used to consider the history effects. And other modules and functions also implemented such as pin power reconstruction, branch calculation, restart, multi-cycle, and 1-D single channel T/H solver.

  5. Review of the status of validation of the computer codes used in the severe accident source term reassessment study (BMI-2104)

    International Nuclear Information System (INIS)

    Kress, T.S.

    1985-04-01

    The determination of severe accident source terms must, by necessity it seems, rely heavily on the use of complex computer codes. Source term acceptability, therefore, rests on the assessed validity of such codes. Consequently, one element of NRC's recent efforts to reassess LWR severe accident source terms is to provide a review of the status of validation of the computer codes used in the reassessment. The results of this review is the subject of this document. The separate review documents compiled in this report were used as a resource along with the results of the BMI-2104 study by BCL and the QUEST study by SNL to arrive at a more-or-less independent appraisal of the status of source term modeling at this time

  6. The Coding Causes of Death in HIV (CoDe) Project: initial results and evaluation of methodology

    DEFF Research Database (Denmark)

    Kowalska, Justyna D; Friis-Møller, Nina; Kirk, Ole

    2011-01-01

    The Coding Causes of Death in HIV (CoDe) Project aims to deliver a standardized method for coding the underlying cause of death in HIV-positive persons, suitable for clinical trials and epidemiologic studies.......The Coding Causes of Death in HIV (CoDe) Project aims to deliver a standardized method for coding the underlying cause of death in HIV-positive persons, suitable for clinical trials and epidemiologic studies....

  7. Status report on the 'Merging' of the Electron-Cloud Code POSINST with the 3-D Accelerator PIC CODE WARP

    International Nuclear Information System (INIS)

    Vay, J.-L.; Furman, M.A.; Azevedo, A.W.; Cohen, R.H.; Friedman, A.; Grote, D.P.; Stoltz, P.H.

    2004-01-01

    We have integrated the electron-cloud code POSINST [1] with WARP [2]--a 3-D parallel Particle-In-Cell accelerator code developed for Heavy Ion Inertial Fusion--so that the two can interoperate. Both codes are run in the same process, communicate through a Python interpreter (already used in WARP), and share certain key arrays (so far, particle positions and velocities). Currently, POSINST provides primary and secondary sources of electrons, beam bunch kicks, a particle mover, and diagnostics. WARP provides the field solvers and diagnostics. Secondary emission routines are provided by the Tech-X package CMEE

  8. Status of the inservice inspection in codes; Stand der wiederkehrenden Pruefung im Regelwerk

    Energy Technology Data Exchange (ETDEWEB)

    Hienstorfer, W G [TUEV Energie- und Systemtechnik GmbH Baden-Wuerttemberg, Filderstadt (Germany); Hansch, M [Preussische Elektrizitaets-AG (Preussenelektra), Hannover (Germany); Koenig, G [Gemeinschaftskernkraftwerk Neckar GmbH, Neckarwestheim (Germany); Bath, H R [Kerntechnischer Ausschuss (KTA), Salzgitter (Germany)

    1998-11-01

    The body of regulatory nuclear engineering and inspection codes and subordinate codes defines on the one hand the general framework conditions for determination of the scope of inservice inspections, and on the other hand, for some defined components, contains detailed provisions relating to the scope of inservice tests to be made. These provisions are based on operating experience and engineering analyses. In order to establish a basis for optimization, the codes have been reviewed for possible optimization potentials, including a comparative analysis of foreign regulatory codes and approaches and the German codes. The conclusion drawn was that there is room for optimization, which should be done taking into account the following aspects: 1. Instrumentation for inservice monitoring of the state variables of relevance to the integrity of the primary loops has to be adapted, requiring acquisition of data showing local loading conditions and specific risks. 2. Inservice examinations of components and pipework should be optimized on the basis of updated, real-status information, i.e. upon availability of latest data showing verified operational loads and stresses and degradation mechanisms and risks, inspection methods, scopes and intervals can be optimized taking into account manufacturing quality. (orig./CB) [Deutsch] In dem aus gesetzlichen und untergesetzlichen Regelungen bestehenden kerntechnischen Regelwerk werden einerseits allgemeine Randbedingungen fuer die Bestimmung des Umfangs wiederkehrender Pruefungen vorgegeben und andererseits fuer einige Komponenten konkrete Festlegungen zum Pruefumfang getroffen. Diesen Festlegungen zum Pruefumfang lagen Betriebserfahrungen und ingenieurmaessige Analysen zugrunde. Als Grundlage fuer eine Optimierung der bisherigen Pruefumfaenge wurden die diesbezueglichen Moeglichkeiten des deutschen Regelwerks untersucht und ein Vergleich mit der Herangehensweise in den wichtigsten auslaendischen Regelwerken durchgefuehrt. Es zeigt

  9. Raman spectroscopy: in vivo quick response code of skin physiological status

    Science.gov (United States)

    Vyumvuhore, Raoul; Tfayli, Ali; Piot, Olivier; Le Guillou, Maud; Guichard, Nathalie; Manfait, Michel; Baillet-Guffroy, Arlette

    2014-11-01

    Dermatologists need to combine different clinically relevant characteristics for a better understanding of skin health. These characteristics are usually measured by different techniques, and some of them are highly time consuming. Therefore, a predicting model based on Raman spectroscopy and partial least square (PLS) regression was developed as a rapid multiparametric method. The Raman spectra collected from the five uppermost micrometers of 11 healthy volunteers were fitted to different skin characteristics measured by independent appropriate methods (transepidermal water loss, hydration, pH, relative amount of ceramides, fatty acids, and cholesterol). For each parameter, the obtained PLS model presented correlation coefficients higher than R2=0.9. This model enables us to obtain all the aforementioned parameters directly from the unique Raman signature. In addition to that, in-depth Raman analyses down to 20 μm showed different balances between partially bound water and unbound water with depth. In parallel, the increase of depth was followed by an unfolding process of the proteins. The combinations of all these information led to a multiparametric investigation, which better characterizes the skin status. Raman signal can thus be used as a quick response code (QR code). This could help dermatologic diagnosis of physiological variations and presents a possible extension to pathological characterization.

  10. Validation of thermohydraulic codes by comparison of experimental results with computer simulations

    International Nuclear Information System (INIS)

    Madeira, A.A.; Galetti, M.R.S.; Pontedeiro, A.C.

    1989-01-01

    The results obtained by simulation of three cases from CANON depressurization experience, using the TRAC-PF1 computer code, version 7.6, implanted in the VAX-11/750 computer of Brazilian CNEN, are presented. The CANON experience was chosen as first standard problem in thermo-hydraulic to be discussed at ENFIR for comparing results from different computer codes with results obtained experimentally. The ability of TRAC-PF1 code to prevent the depressurization phase of a loss of primary collant accident in pressurized water reactors is evaluated. (M.C.K.) [pt

  11. Status on development and verification of reactivity initiated accident analysis code for PWR (NODAL3)

    International Nuclear Information System (INIS)

    Peng Hong Liem; Surian Pinem; Tagor Malem Sembiring; Tran Hoai Nam

    2015-01-01

    A coupled neutronics thermal-hydraulics code NODAL3 has been developed based on the nodal few-group neutron diffusion theory in 3-dimensional Cartesian geometry for a typical pressurized water reactor (PWR) static and transient analyses, especially for reactivity initiated accidents (RIA). The spatial variables are treated by using a polynomial nodal method (PNM) while for the neutron dynamic solver the adiabatic and improved quasi-static methods are adopted. A simple single channel thermal-hydraulics module and its steam table is implemented into the code. Verification works on static and transient benchmarks are being conducting to assess the accuracy of the code. For the static benchmark verification, the IAEA-2D, IAEA-3D, BIBLIS and KOEBERG light water reactor (LWR) benchmark problems were selected, while for the transient benchmark verification, the OECD NEACRP 3-D LWR Core Transient Benchmark and NEA-NSC 3-D/1-D PWR Core Transient Benchmark (Uncontrolled Withdrawal of Control Rods at Zero Power). Excellent agreement of the NODAL3 results with the reference solutions and other validated nodal codes was confirmed. (author)

  12. Status and recent results of the MAGIC telescope system

    Energy Technology Data Exchange (ETDEWEB)

    Fruck, Christian [Max-Planck-Institut fuer Physik, Muenchen (Germany); Collaboration: MAGIC-Collaboration

    2016-07-01

    MAGIC is an instrument for pointed ground-based observations of the gamma-ray sky in the 50 GeV to 80 TeV regime. The two 17 m diameter Imaging Air Cherenkov Telescopes are located on 2200 m a.s.l. at the Roque de los Muchachos Observatory on the Canary island La Palma. We will report the status and recent technical developments of the instrument, highlight the most important scientific results obtained with observations of Galactic and extragalactic objects, and will summarize future plans.

  13. Status report on geochemical field results from Atlantic study sites

    International Nuclear Information System (INIS)

    Wilson, T.R.S.; Thomson, J.; Hydes, D.J.; Colley, S.

    1983-01-01

    This report summarises the results of preliminary geochemical investigations at three North Atlantic study areas. The two eastern sites, on the Cape Verde abyssal plain (CV2) and east of Great Meteor Seamount (GME) were visited during 1982. The results presented are preliminary. Studies in the western Atlantic, close to the Nares Abyssal Plain study site are more detailed and are presented in a separate paper. The report shows for the first time the relative redox status of the three sites. The differences are unexpectedly large, the most reduced cores being recovered at GME and the most oxidised at CV2. The sporadic nature of Recent sediment accumulation at these sites is also emphasised. In order to place these preliminary results in context their relevance to the production of mathematical system models is discussed in a closing section. The necessity for such models to rest on sound foundations of geochemical understanding is noted. Suggestions on future research priorities are offered for discussion. (author)

  14. Five-way Smoking Status Classification Using Text Hot-Spot Identification and Error-correcting Output Codes

    OpenAIRE

    Cohen, Aaron M.

    2008-01-01

    We participated in the i2b2 smoking status classification challenge task. The purpose of this task was to evaluate the ability of systems to automatically identify patient smoking status from discharge summaries. Our submission included several techniques that we compared and studied, including hot-spot identification, zero-vector filtering, inverse class frequency weighting, error-correcting output codes, and post-processing rules. We evaluated our approaches using the same methods as the i2...

  15. Verification of the Korsar code on results of experiments executed on the PSB-VVER facility

    International Nuclear Information System (INIS)

    Roginskaya, V.L.; Pylev, S.S.; Elkin, I.V.

    2005-01-01

    Full text of publication follows: Paper represents some results of computational research executed within the framework of verification of the KORSAR thermal hydraulic code. This code was designed in the NITI by A.P. Aleksandrov (Russia). The general purpose of the work was development of a nodding scheme of the PSB-VVER integral facility, scheme testing and computational modelling of the experiment 'The PSB-VVER Natural Circulation Test With Stepwise Reduction of the Primary Inventory'. The NC test has been performed within the framework of the OECD PSB-VVER Project (task no. 3). This Project is focused upon the provision of experimental data for codes assessment with regard to VVER analysis. Paper presents a nodding scheme of the PSB-VVER facility and results of pre- and post-test calculations of the specified experiment, obtained with the KORSAR code. The experiment data and the KORSAR pre-test calculation results are in good agreement. A post-test calculation of the experiment with KORSAR code has been performed in order to assess the code capability to simulate the phenomena relevant to the test. The code showed a reasonable prediction of the phenomena measured in the experiment. (authors)

  16. Verification of the Korsar code on results of experiments executed on the PSB-VVER facility

    Energy Technology Data Exchange (ETDEWEB)

    Roginskaya, V.L.; Pylev, S.S.; Elkin, I.V. [NSI RRC ' Kurchatov Institute' , Kurchatov Sq., 1, Moscow, 123182 (Russian Federation)

    2005-07-01

    Full text of publication follows: Paper represents some results of computational research executed within the framework of verification of the KORSAR thermal hydraulic code. This code was designed in the NITI by A.P. Aleksandrov (Russia). The general purpose of the work was development of a nodding scheme of the PSB-VVER integral facility, scheme testing and computational modelling of the experiment 'The PSB-VVER Natural Circulation Test With Stepwise Reduction of the Primary Inventory'. The NC test has been performed within the framework of the OECD PSB-VVER Project (task no. 3). This Project is focused upon the provision of experimental data for codes assessment with regard to VVER analysis. Paper presents a nodding scheme of the PSB-VVER facility and results of pre- and post-test calculations of the specified experiment, obtained with the KORSAR code. The experiment data and the KORSAR pre-test calculation results are in good agreement. A post-test calculation of the experiment with KORSAR code has been performed in order to assess the code capability to simulate the phenomena relevant to the test. The code showed a reasonable prediction of the phenomena measured in the experiment. (authors)

  17. Validation of the WIMSD4M cross-section generation code with benchmark results

    International Nuclear Information System (INIS)

    Deen, J.R.; Woodruff, W.L.; Leal, L.E.

    1995-01-01

    The WIMSD4 code has been adopted for cross-section generation in support of the Reduced Enrichment Research and Test Reactor (RERTR) program at Argonne National Laboratory (ANL). Subsequently, the code has undergone several updates, and significant improvements have been achieved. The capability of generating group-collapsed micro- or macroscopic cross sections from the ENDF/B-V library and the more recent evaluation, ENDF/B-VI, in the ISOTXS format makes the modified version of the WIMSD4 code, WIMSD4M, very attractive, not only for the RERTR program, but also for the reactor physics community. The intent of the present paper is to validate the WIMSD4M cross-section libraries for reactor modeling of fresh water moderated cores. The results of calculations performed with multigroup cross-section data generated with the WIMSD4M code will be compared against experimental results. These results correspond to calculations carried out with thermal reactor benchmarks of the Oak Ridge National Laboratory (ORNL) unreflected HEU critical spheres, the TRX LEU critical experiments, and calculations of a modified Los Alamos HEU D 2 O moderated benchmark critical system. The benchmark calculations were performed with the discrete-ordinates transport code, TWODANT, using WIMSD4M cross-section data. Transport calculations using the XSDRNPM module of the SCALE code system are also included. In addition to transport calculations, diffusion calculations with the DIF3D code were also carried out, since the DIF3D code is used in the RERTR program for reactor analysis and design. For completeness, Monte Carlo results of calculations performed with the VIM and MCNP codes are also presented

  18. Validation of the WIMSD4M cross-section generation code with benchmark results

    Energy Technology Data Exchange (ETDEWEB)

    Deen, J.R.; Woodruff, W.L. [Argonne National Lab., IL (United States); Leal, L.E. [Oak Ridge National Lab., TN (United States)

    1995-01-01

    The WIMSD4 code has been adopted for cross-section generation in support of the Reduced Enrichment Research and Test Reactor (RERTR) program at Argonne National Laboratory (ANL). Subsequently, the code has undergone several updates, and significant improvements have been achieved. The capability of generating group-collapsed micro- or macroscopic cross sections from the ENDF/B-V library and the more recent evaluation, ENDF/B-VI, in the ISOTXS format makes the modified version of the WIMSD4 code, WIMSD4M, very attractive, not only for the RERTR program, but also for the reactor physics community. The intent of the present paper is to validate the WIMSD4M cross-section libraries for reactor modeling of fresh water moderated cores. The results of calculations performed with multigroup cross-section data generated with the WIMSD4M code will be compared against experimental results. These results correspond to calculations carried out with thermal reactor benchmarks of the Oak Ridge National Laboratory (ORNL) unreflected HEU critical spheres, the TRX LEU critical experiments, and calculations of a modified Los Alamos HEU D{sub 2}O moderated benchmark critical system. The benchmark calculations were performed with the discrete-ordinates transport code, TWODANT, using WIMSD4M cross-section data. Transport calculations using the XSDRNPM module of the SCALE code system are also included. In addition to transport calculations, diffusion calculations with the DIF3D code were also carried out, since the DIF3D code is used in the RERTR program for reactor analysis and design. For completeness, Monte Carlo results of calculations performed with the VIM and MCNP codes are also presented.

  19. Status of the general description of fission observables by the GEF code

    CERN Document Server

    Jurado, B

    2014-01-01

    The GEneral Fission (GEF) model treats spontaneous fission and fission up to an excitation energy of about 100 MeV of a wide range of heavy nuclei. GEF makes use of general laws of statistical and quantum mechanics, assuring a high predictive power. It is unique in providing a general description of essentially all fission observables in a consistent way while preserving the correlations between all of them. In this contribution we present some of the physical aspects on which the model is based, give an overview on the results that can be obtained with the code and show an example that illustrates how the GEF code can serve as a framework for revealing the sensitivity of the fission observables to some basic nuclear properties.

  20. The OPERA Long Baseline Experiment: Status and First Results

    CERN Document Server

    Duchesneau, Dominique

    2008-01-01

    OPERA (Oscillation Project with Emulsion tRacking Apparatus)is an international collaboration between Europe and Asia, aiming to give the first direct proof of tau neutrino appearance in a pure muon neutrino beam, in order to validate the hypothesis for atmospheric neutrino oscillations. The first european long baseline neutrino beam called CNGS is produced at CERN and sent in the direction of the Gran Sasso underground laboratory 730 km away, where the OPERA detector is located. Since 2006 the electronic detector part is fully commissioned and running. Cosmic ray events have been recorded on a regular basis and the first neutrino beam events have been observed in the target elements made of very precise emulsion films and lead sheets during the last run in autumn 2007. This paper reviews the status of the detector, the beam performances, the first results from the neutrino event analysis and the prospects.

  1. The VENUS-7 benchmarks. Results from state-of-the-art transport codes and nuclear data

    International Nuclear Information System (INIS)

    Zwermann, Winfried; Pautz, Andreas; Timm, Wolf

    2010-01-01

    For the validation of both nuclear data and computational methods, comparisons with experimental data are necessary. Most advantageous are assemblies where not only the multiplication factors or critical parameters were measured, but also additional quantities like reactivity differences or pin-wise fission rate distributions have been assessed. Currently there is a comprehensive activity to evaluate such measure-ments and incorporate them in the International Handbook of Evaluated Reactor Physics Benchmark Experiments. A large number of such experiments was performed at the VENUS zero power reactor at SCK/CEN in Belgium in the sixties and seventies. The VENUS-7 series was specified as an international benchmark within the OECD/NEA Working Party on Scientific Issues of Reactor Systems (WPRS), and results obtained with various codes and nuclear data evaluations were summarized. In the present paper, results of high-accuracy transport codes with full spatial resolution with up-to-date nuclear data libraries from the JEFF and ENDF/B evaluations are presented. The comparisons of the results, both code-to-code and with the measured data are augmented by uncertainty and sensitivity analyses with respect to nuclear data uncertainties. For the multiplication factors, these are performed with the TSUNAMI-3D code from the SCALE system. In addition, uncertainties in the reactivity differences are analyzed with the TSAR code which is available from the current SCALE-6 version. (orig.)

  2. Results of the recent investigations of the accuracy of C-PORCA code

    International Nuclear Information System (INIS)

    Pos, I.

    2001-01-01

    During the last year it was an essential demand to establish the C-PORCA code accuracy concerning the newly developed BNFL fuel. As it is well known the BNFL fuel assembly developed for the NPP Paks contains fuel pins with gadolinium. These pins are situated near the central tube so their unusual effects to be investigated. At the present investigation the C-PORCA code and the APA-H Westinghouse code system results were compared. During this comparison the differences between node and pin wise power distributions have been calculated as well. The fulfilled test have reinforced the applicability and capability of the C-PORCA code for WWER-440 core analysis (Authors)

  3. Sensitivity Analysis of FEAST-Metal Fuel Performance Code: Initial Results

    International Nuclear Information System (INIS)

    Edelmann, Paul Guy; Williams, Brian J.; Unal, Cetin; Yacout, Abdellatif

    2012-01-01

    This memo documents the completion of the LANL milestone, M3FT-12LA0202041, describing methodologies and initial results using FEAST-Metal. The FEAST-Metal code calculations for this work are being conducted at LANL in support of on-going activities related to sensitivity analysis of fuel performance codes. The objective is to identify important macroscopic parameters of interest to modeling and simulation of metallic fuel performance. This report summarizes our preliminary results for the sensitivity analysis using 6 calibration datasets for metallic fuel developed at ANL for EBR-II experiments. Sensitivity ranking methodology was deployed to narrow down the selected parameters for the current study. There are approximately 84 calibration parameters in the FEAST-Metal code, of which 32 were ultimately used in Phase II of this study. Preliminary results of this sensitivity analysis led to the following ranking of FEAST models for future calibration and improvements: fuel conductivity, fission gas transport/release, fuel creep, and precipitation kinetics. More validation data is needed to validate calibrated parameter distributions for future uncertainty quantification studies with FEAST-Metal. Results of this study also served to point out some code deficiencies and possible errors, and these are being investigated in order to determine root causes and to improve upon the existing code models.

  4. Load monitoring program: Status and results report. Volume 1: Summary

    International Nuclear Information System (INIS)

    1994-06-01

    British Columbia Hydro conducts a monitoring program to provide information on customer needs and values for planning; to measure customer response, energy savings impacts, and load shape impacts due to changes in rate level, rate restructuring, and Power Smart programs; to estimate end-use consumption and load shapes by customer class; and to provide load information for distribution and system load studies. To achieve these objectives, the monitoring program tracks the characteristics and energy use patterns of a sample of BC Hydro residential, commercial, and industrial customers over a period of several years. The entire sample will be surveyed periodically to obtain information on changes in building characteristics, equipment stocks, and energy-use behavior and attitudes. A report is provided on the status of monitoring program activities and some results obtained in 1993/94. For the residential sector, the results include typical load profiles, end-user demographics, and extent of electric space heating and water heating. In the commercial sector, customers were divided into two main groups. The large-building group was relatively well organized in terms of energy needs and participated in Power Smart programs. The small-building group was relatively energy-inefficient and relatively unaware of Power Smart programs. 43 figs., 15 tabs

  5. The 140 GHZ, 1 MW Gyrotron - Status and Recent Results

    Science.gov (United States)

    Gantenbein, G.; Dammertz, G.; Illy, S.; Kern, S.; Leonhardt, W.; Piosczyk, B.; Schmid, M.; Thumm, M.; Braune, H.; Erckmann, V.; Laqua, H. P.; Michel, G.; Kasparek, W.; Lechte, C.; Legrand, F.; Lievin, C.; Prinz, O.

    2009-04-01

    A 10 MW ECRH system is currently under construction for the stellarator W7-X which will be built up and operated by IPP in Greifswald, Germany. The present status of the complete system is reported in [1]. The RF power will be provided by 10 gyrotrons. A European collaboration has been established to develop and build the 10 gyrotrons each with an output power of 1 MW for continuous wave (CW) operation [2]. Nine gyrotrons are being manufactured by Thales Electron Devices (TED), Vélizy, France, one gyrotron was produced by CPI, Palo Alto, CA and passed the acceptance tests at IPP. The acceptance tests of the TED gyrotrons are performed at the test stand at FZK and on site at IPP. The first series tube yielded a total output power of 0.98 MW, with an efficiency of 31 % (without a single stage depressed collector) in short pulse operation and of 0.92 MW in pulses of 1800 s (efficiency of almost 45 % at a depression voltage of 29 kV) [3], The Gaussian mode output power was 0.91 MW. The RF power, measured in a calorimetric load at the end of a 25 m long quasi-optical transmission line with seven mirrors, was 0.87 MW. In this contribution typical results of the next series gyrotrons will be reported.

  6. Development of computer code SIMPSEX for simulation of FBR fuel reprocessing flowsheets: II. additional benchmarking results

    International Nuclear Information System (INIS)

    Shekhar Kumar; Koganti, S.B.

    2003-07-01

    Benchmarking and application of a computer code SIMPSEX for high plutonium FBR flowsheets was reported recently in an earlier report (IGC-234). Improvements and recompilation of the code (Version 4.01, March 2003) required re-validation with the existing benchmarks as well as additional benchmark flowsheets. Improvements in the high Pu region (Pu Aq >30 g/L) resulted in better results in the 75% Pu flowsheet benchmark. Below 30 g/L Pu Aq concentration, results were identical to those from the earlier version (SIMPSEX Version 3, code compiled in 1999). In addition, 13 published flowsheets were taken as additional benchmarks. Eleven of these flowsheets have a wide range of feed concentrations and few of them are β-γ active runs with FBR fuels having a wide distribution of burnup and Pu ratios. A published total partitioning flowsheet using externally generated U(IV) was also simulated using SIMPSEX. SIMPSEX predictions were compared with listed predictions from conventional SEPHIS, PUMA, PUNE and PUBG. SIMPSEX results were found to be comparable and better than the result from above listed codes. In addition, recently reported UREX demo results along with AMUSE simulations are also compared with SIMPSEX predictions. Results of the benchmarking SIMPSEX with these 14 benchmark flowsheets are discussed in this report. (author)

  7. SPACE CHARGE SIMULATION METHODS INCORPORATED IN SOME MULTI - PARTICLE TRACKING CODES AND THEIR RESULTS COMPARISON

    International Nuclear Information System (INIS)

    BEEBE - WANG, J.; LUCCIO, A.U.; D IMPERIO, N.; MACHIDA, S.

    2002-01-01

    Space charge in high intensity beams is an important issue in accelerator physics. Due to the complicity of the problems, the most effective way of investigating its effect is by computer simulations. In the resent years, many space charge simulation methods have been developed and incorporated in various 2D or 3D multi-particle-tracking codes. It has becoming necessary to benchmark these methods against each other, and against experimental results. As a part of global effort, we present our initial comparison of the space charge methods incorporated in simulation codes ORBIT++, ORBIT and SIMPSONS. In this paper, the methods included in these codes are overviewed. The simulation results are presented and compared. Finally, from this study, the advantages and disadvantages of each method are discussed

  8. GRS Method for Uncertainty and Sensitivity Evaluation of Code Results and Applications

    International Nuclear Information System (INIS)

    Glaeser, H.

    2008-01-01

    During the recent years, an increasing interest in computational reactor safety analysis is to replace the conservative evaluation model calculations by best estimate calculations supplemented by uncertainty analysis of the code results. The evaluation of the margin to acceptance criteria, for example, the maximum fuel rod clad temperature, should be based on the upper limit of the calculated uncertainty range. Uncertainty analysis is needed if useful conclusions are to be obtained from best estimate thermal-hydraulic code calculations, otherwise single values of unknown accuracy would be presented for comparison with regulatory acceptance limits. Methods have been developed and presented to quantify the uncertainty of computer code results. The basic techniques proposed by GRS are presented together with applications to a large break loss of coolant accident on a reference reactor as well as on an experiment simulating containment behaviour

  9. SPACE CHARGE SIMULATION METHODS INCORPORATED IN SOME MULTI - PARTICLE TRACKING CODES AND THEIR RESULTS COMPARISON.

    Energy Technology Data Exchange (ETDEWEB)

    BEEBE - WANG,J.; LUCCIO,A.U.; D IMPERIO,N.; MACHIDA,S.

    2002-06-03

    Space charge in high intensity beams is an important issue in accelerator physics. Due to the complicity of the problems, the most effective way of investigating its effect is by computer simulations. In the resent years, many space charge simulation methods have been developed and incorporated in various 2D or 3D multi-particle-tracking codes. It has becoming necessary to benchmark these methods against each other, and against experimental results. As a part of global effort, we present our initial comparison of the space charge methods incorporated in simulation codes ORBIT++, ORBIT and SIMPSONS. In this paper, the methods included in these codes are overviewed. The simulation results are presented and compared. Finally, from this study, the advantages and disadvantages of each method are discussed.

  10. Methodology, status and plans for development and assessment of TUF and CATHENA codes

    Energy Technology Data Exchange (ETDEWEB)

    Luxat, J.C.; Liu, W.S.; Leung, R.K. [Ontario Hydro, Toronto (Canada)] [and others

    1997-07-01

    An overview is presented of the Canadian two-fluid computer codes TUF and CATHENA with specific focus on the constraints imposed during development of these codes and the areas of application for which they are intended. Additionally a process for systematic assessment of these codes is described which is part of a broader, industry based initiative for validation of computer codes used in all major disciplines of safety analysis. This is intended to provide both the licensee and the regulator in Canada with an objective basis for assessing the adequacy of codes for use in specific applications. Although focused specifically on CANDU reactors, Canadian experience in developing advanced two-fluid codes to meet wide-ranging application needs while maintaining past investment in plant modelling provides a useful contribution to international efforts in this area.

  11. Methodology, status and plans for development and assessment of TUF and CATHENA codes

    International Nuclear Information System (INIS)

    Luxat, J.C.; Liu, W.S.; Leung, R.K.

    1997-01-01

    An overview is presented of the Canadian two-fluid computer codes TUF and CATHENA with specific focus on the constraints imposed during development of these codes and the areas of application for which they are intended. Additionally a process for systematic assessment of these codes is described which is part of a broader, industry based initiative for validation of computer codes used in all major disciplines of safety analysis. This is intended to provide both the licensee and the regulator in Canada with an objective basis for assessing the adequacy of codes for use in specific applications. Although focused specifically on CANDU reactors, Canadian experience in developing advanced two-fluid codes to meet wide-ranging application needs while maintaining past investment in plant modelling provides a useful contribution to international efforts in this area

  12. 2D and 3D core-collapse supernovae simulation results obtained with the CHIMERA code

    Energy Technology Data Exchange (ETDEWEB)

    Bruenn, S W; Marronetti, P; Dirk, C J [Physics Department, Florida Atlantic University, 777 W. Glades Road, Boca Raton, FL 33431-0991 (United States); Mezzacappa, A; Hix, W R [Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN 37831-6354 (United States); Blondin, J M [Department of Physics, North Carolina State University, Raleigh, NC 27695-8202 (United States); Messer, O E B [Center for Computational Sciences, Oak Ridge National Laboratory, Oak Ridge, TN 37831-6354 (United States); Yoshida, S, E-mail: bruenn@fau.ed [Max-Planck-Institut fur Gravitationsphysik, Albert Einstein Institut, Golm (Germany)

    2009-07-01

    Much progress in realistic modeling of core-collapse supernovae has occurred recently through the availability of multi-teraflop machines and the increasing sophistication of supernova codes. These improvements are enabling simulations with enough realism that the explosion mechanism, long a mystery, may soon be delineated. We briefly describe the CHIMERA code, a supernova code we have developed to simulate core-collapse supernovae in 1, 2, and 3 spatial dimensions. We then describe the results of an ongoing suite of 2D simulations initiated from a 12, 15, 20, and 25 M{sub o-dot} progenitor. These have all exhibited explosions and are currently in the expanding phase with the shock at between 5,000 and 20,000 km. We also briefly describe an ongoing simulation in 3 spatial dimensions initiated from the 15 M{sub o-dot} progenitor.

  13. Status and Perspective of the Hydraulic Solver development for SPACE code

    International Nuclear Information System (INIS)

    Lee, S. Y.; Oh, M. T.; Park, J. C.; Ahn, S. J.; Park, C. E.; Lee, E. J.; Na, Y. W.

    2008-01-01

    KOPEC has been developing a hydraulic solver for SPACE code. The governing equations for the solver can be obtained through several steps of modeling and approximations from the basic material transport principles. Once the governing equations are fixed, a proper discretization procedure should be followed to get the difference equations that can be solved by well established matrix solvers. Of course, the mesh generation and handling procedures are necessary for the discretization process. At present, the preliminary test version has been constructed and being tested. The selection of the compiler language was debated openly. C++ was chosen as a basis compiler language. But other language such as FORTRAN can be used as it is necessary. The steps mentioned above are explained in the following sections. Test results are presented by other companion papers in this meeting. Future activities will be described in the conclusion section

  14. Methodology, status, and plans for development and assessment of the RELAP5 code

    Energy Technology Data Exchange (ETDEWEB)

    Johnson, G.W.; Riemke, R.A. [Idaho National Engineering Laboratory, Idaho Falls, ID (United States)

    1997-07-01

    RELAP/MOD3 is a computer code used for the simulation of transients and accidents in light-water nuclear power plants. The objective of the program to develop and maintain RELAP5 was and is to provide the U.S. Nuclear Regulatory Commission with an independent tool for assessing reactor safety. This paper describes code requirements, models, solution scheme, language and structure, user interface validation, and documentation. The paper also describes the current and near term development program and provides an assessment of the code`s strengths and limitations.

  15. The status of simulation codes for extraction process using mixer-settler

    Energy Technology Data Exchange (ETDEWEB)

    Byeon, Kee Hoh; Lee, Eil Hee; Kwon, Seong Gil; Kim, Kwang Wook; Yang, Han Beom; Chung, Dong Yong; Lim, Jae Kwan; Shin, Hyun Kyoo; Kim, Soo Ho

    1999-10-01

    We have studied and analyzed the mixer-settler simulation codes such as three kinds of SEPHIS series, PUBG, and EXTRA.M, which is the most recently developed code. All of these are sufficiently satisfactory codes in the fields of process/device modeling, but it is necessary to formulate the accurate distribution data and chemical reaction mechanism for the aspect of accuracy and reliability. In the aspect of application to be the group separation process, the mixer-settler model of these codes have no problems, but the accumulation and formulation of partitioning and reaction equilibrium data of chemical elements used in group separation process is very important. (author)

  16. Assessment of the system code DRUFAN/ATHLET using results of LOBI tests

    International Nuclear Information System (INIS)

    Burwell, J.M.; Kirmse, R.E.; Kyncl, M.; Malhotra, P.K.

    1989-09-01

    Four post-test analyses have been performed by GRS within the Shared Cost Action Programme (SCAP) sponsored by the Commission of the European Communities (contract 3015-86-07 EL ISP D) and by the Bundesminister fuer Forschung und Technologie of the Federal Republic of Germany (Research project RS 739). The four tests were mutually selected by the contractors (CEA, GRS, IKE, Univ. Pisa) of activity No. 3 and by the project organizer. Some of the tests were selected to be analyzed by more than one participant in order to allow comparison between analytical results obtained with different codes or obtained by different code-users. DRUFAN/ATHLET verification analyses were performed by IKE too. The four tests selected for the GRS activity are: - A2-77A (Natural Circulation Test), Analysis with ATHLET - A1-76 (Steam Generator Performance Test), Analysis with DRUFAN - BL-01 (Intermediate Leak), Analysis with ATHLET - A2-81 (Small Leak), Analysis with ATHLET. This final report contains the results of the four post test analysis including the comparison between measured and calculated quantities and the description of the applied codes, the selected model of the LOBI facility and the conclusions drawn for the improvement of the codes models

  17. The CoRoT Exoplanet program: status & results

    Directory of Open Access Journals (Sweden)

    Moutou C.

    2011-02-01

    Full Text Available The CoRoT satellite is the first instrument hunting for planets from space. We will review the status of the CoRoT/Exoplanet program. We will then present the CoRoT exoplanetary systems and how they widen the range of properties of the close-in population and contribute to our understanding of the properties of planets.

  18. International outage coding system for nuclear power plants. Results of a co-ordinated research project

    International Nuclear Information System (INIS)

    2004-05-01

    The experience obtained in each individual plant constitutes the most relevant source of information for improving its performance. However, experience of the level of the utility, country and worldwide is also extremely valuable, because there are limitations to what can be learned from in-house experience. But learning from the experience of others is admittedly difficult, if the information is not harmonized. Therefore, such systems should be standardized and applicable to all types of reactors satisfying the needs of the broad set of nuclear power plant operators worldwide and allowing experience to be shared internationally. To cope with the considerable amount of information gathered from nuclear power plants worldwide, it is necessary to codify the information facilitating the identification of causes of outages, systems or component failures. Therefore, the IAEA established a sponsored Co-ordinated Research Project (CRP) on the International Outage Coding System to develop a general, internationally applicable system of coding nuclear power plant outages, providing worldwide nuclear utilities with a standardized tool for reporting outage information. This TECDOC summarizes the results of this CRP and provides information for transformation of the historical outage data into the new coding system, taking into consideration the existing systems for coding nuclear power plant events (WANO, IAEA-IRS and IAEA PRIS) but avoiding duplication of efforts to the maximum possible extent

  19. MELMRK 2.0: A description of computer models and results of code testing

    International Nuclear Information System (INIS)

    Wittman, R.S.; Denny, V.; Mertol, A.

    1992-01-01

    An advanced version of the MELMRK computer code has been developed that provides detailed models for conservation of mass, momentum, and thermal energy within relocating streams of molten metallics during meltdown of Savannah River Site (SRS) reactor assemblies. In addition to a mechanistic treatment of transport phenomena within a relocating stream, MELMRK 2.0 retains the MOD1 capability for real-time coupling of the in-depth thermal response of participating assembly heat structure and, further, augments this capability with models for self-heating of relocating melt owing to steam oxidation of metallics and fission product decay power. As was the case for MELMRK 1.0, the MOD2 version offers state-of-the-art numerics for solving coupled sets of nonlinear differential equations. Principal features include application of multi-dimensional Newton-Raphson techniques to accelerate convergence behavior and direct matrix inversion to advance primitive variables from one iterate to the next. Additionally, MELMRK 2.0 provides logical event flags for managing the broad range of code options available for treating such features as (1) coexisting flow regimes, (2) dynamic transitions between flow regimes, and (3) linkages between heatup and relocation code modules. The purpose of this report is to provide a detailed description of the MELMRK 2.0 computer models for melt relocation. Also included are illustrative results for code testing, as well as an integrated calculation for meltdown of a Mark 31a assembly

  20. Status of computer codes available in AEOI for reactor physics analysis

    International Nuclear Information System (INIS)

    Karbassiafshar, M.

    1986-01-01

    Many of the nuclear computer codes available in Atomic Energy Organization of Iran AEOI can be used for physics analysis of an operating reactor or design purposes. Grasp of the various methods involved and practical experience with these codes would be the starting point for interesting design studies or analysis of operating conditions of presently existing and future reactors. A review of the objectives and flowchart of commonly practiced procedures in reactor physics analysis of LWRs and related computer codes was made, extrapolating to the nationally and internationally available resources. Finally, effective utilization of the existing facilities is discussed and called upon

  1. Procedural and legal status of the injured party according to the new criminal procedure code of the Republic of Serbia

    Directory of Open Access Journals (Sweden)

    Grubač Momčilo

    2012-01-01

    Full Text Available In this article the author is critically analyzing certain solutions of the new Criminal Procedure Code of the Republic of Serbia from 2011 which consider the injured party and their rights in the criminal proceeding. He states that unlike the previous ones, this Code does not improve the status of the injured party but makes it even worse. The author particularly claims that the legislator yet again failed to establish the right of the injured party to be efficiently compensated in the event of a serious offense from a special fund and immediately after the crime has been committed, but prior to the end of the criminal proceeding. In the provision of the Code which states that the injured party may take over the prosecution and become a prosecutor replacing the Public Prosecutor (subsidiary prosecutor only if the Public Prosecutor withdraws after having confirmed the indictment, however not in the cases of rejection of criminal charges or withdrawal from the prosecution in the previous proceeding, the author sees not only the limitation of the rights of the injured party, but also jeopardy of the public interest. This is due to the fact that, freed from a threat of the subsidiary accusation by the injured party, the Public Prosecutor has gained an absolute and uncontrolled monopoly over the initiation of criminal proceeding. According to the author, the subject of the proceedings will not have any substantial use from some rights which the new Code assigns to the injured party (for example the right to appeal against the judgment on the adjudicated property claim. In conclusion, the author stresses out that in spite of his objections against certain provisions in the Code, the legal status of the injured party is more favorable in the criminal law of Serbia then in many other countries.

  2. Modelling 3-D mechanical phenomena in a 1-D industrial finite element code: results and perspectives

    International Nuclear Information System (INIS)

    Guicheret-Retel, V.; Trivaudey, F.; Boubakar, M.L.; Masson, R.; Thevenin, Ph.

    2005-01-01

    Assessing fuel rod integrity in PWR reactors must enjoin two opposite goals: a one-dimensional finite element code (axial revolution symmetry) is needed to provide industrial results at the scale of the reactor core, while the main risk of cladding failure [e.g. pellet-cladding interaction (PCI)] is based on fully three-dimensional phenomena. First, parametric three-dimensional elastic calculations were performed to identify the relevant parameters (fragment number, contact pellet-cladding conditions, etc.) as regards PCI. Axial fragment number as well as friction coefficient are shown to play a major role in PCI as opposed to other parameters. Next, the main limitations of the one-dimensional hypothesis of the finite element code CYRANO3 are identified. To overcome these limitations, both two- and three-dimensional emulations of CYRANO3 were developed. These developments are shown to significantly improve the results provided by CYRANO3. (authors)

  3. Review of solution approach, methods, and recent results of the RELAP5 system code

    International Nuclear Information System (INIS)

    Trapp, J.A.; Ransom, V.H.

    1983-01-01

    The present RELAP5 code is based on a semi-implicit numerical scheme for the hydrodynamic model. The basic guidelines employed in the development of the semi-implicit numerical scheme are discussed and the numerical features of the scheme are illustrated by analysis for a simple, but analogous, single-equation model. The basic numerical scheme is recorded and results from several simulations are presented. The experimental results and code simulations are used in a complementary fashion to develop insights into nuclear-plant response that would not be obtained if either tool were used alone. Further analysis using the simple single-equation model is carried out to yield insights that are presently being used to implement a more-implicit multi-step scheme in the experimental version of RELAP5. The multi-step implicit scheme is also described

  4. Verification of simulation model with COBRA-IIIP code by confrontment of experimental results

    International Nuclear Information System (INIS)

    Silva Galetti, M.R. da; Pontedeiro, A.C.; Oliveira Barroso, A.C. de

    1985-01-01

    It is presented an evaluation of the COBRA IIIP/MIT code (of thermal hydraulic analysis by subchannels), comparing their results with experimental data obtained in stationary and transient regimes. It was done a study to calculate the spatial and temporal critical heat flux. It is presented a sensitivity study of simulation model related to the turbulent mixture and the number of axial intervals. (M.C.K.) [pt

  5. Comparison of aerosol behavior codes with experimental results from a sodium fire in a containment

    International Nuclear Information System (INIS)

    Lhiaubet, G.; Kissane, M.P.; Seino, H.; Miyake, O.; Himeno, Y.

    1990-01-01

    The containment expert group (CONT), a subgroup of the CEC fast reactor Safety Working Group (SWG), has carried out several studies on the behavior of sodium aerosols which might form in a severe fast reactor accident during which primary sodium leaks into the secondary containment. These studies comprise an intercalibration of measurement devices used to determine the aerosol particle size spectrum, and the analysis and comparison of codes applied to the determination of aerosol behavior in a reactor containment. The paper outlines the results of measurements of typical data made for aerosols produced in a sodium fire and their comparison with results from different codes (PARDISEKO, AEROSIM, CONTAIN, AEROSOLS/B2). The sodium fire experiment took place at CEN-Cadarache (France) in a 400 m 3 vessel. The fire lasted 90 minutes and the aerosol measurements were made over 10 hours at different locations inside the vessel. The results showed that the suspended mass calculated along the time with different codes was in good agreement with the experiment. However, the calculated aerosol deposition on the walls was diverging and always significantly lower than the measured values

  6. Results of aerosol code comparisons with releases from ACE MCCI tests

    International Nuclear Information System (INIS)

    Fink, J.K.; Corradini, M.; Hidaka, A.; Hontanon, E.; Mignanelli, M.A.; Schroedl, E.; Strizhov, V.

    1992-01-01

    Results of aerosol release calculations by six groups from six countries are compared with the releases from ACE MCCI Test L6. The codes used for these calculations included: SOLGASMIX-PV, SOLGASMIX Reactor 1986, CORCON.UW, VANESA 1.01, and CORCON mod2.04/VANESA 1.01. Calculations were performed with the standard VANESA 1.01 code and with modifications to the VANESA code such as the inclusion of various zirconium-silica chemical reactions. Comparisons of results from these calculations were made with Test L6 release fractions for U, Zr, Si, the fission-product elements Te, Ba, Sr, Ce, La, Mo and control materials Ag, In, and Ru. Reasonable agreement was obtained between calculations and Test L6 results for the volatile elements Ag, In and Te. Calculated releases of the low volatility fission products ranged from within an order of magnitude to five orders of magnitude of Test L6 values. Releases were over and underestimated by calculations. Poorest agreements were obtained for Mo and Si

  7. Coupling the MCNP Monte Carlo code and the FISPACT activation code with automatic visualization of the results of simulations

    International Nuclear Information System (INIS)

    Bourauel, Peter; Nabbi, Rahim; Biel, Wolfgang; Forrest, Robin

    2009-01-01

    The MCNP 3D Monte Carlo computer code is used not only for criticality calculations of nuclear systems but also to simulate transports of radiation and particles. The findings so obtained about neutron flux distribution and the associated spectra allow information about materials activation, nuclear heating, and radiation damage to be obtained by means of activation codes such as FISPACT. The stochastic character of particle and radiation transport processes normally links findings to the materials cells making up the geometry model of MCNP. Where high spatial resolution is required for the activation calculations with FISPACT, fine segmentation of the MCNP geometry becomes compulsory, which implies considerable expense for the modeling process. For this reason, an alternative simulation technique has been developed in an effort to automate and optimize data transfer between MCNP and FISPACT. (orig.)

  8. Methodology, status and plans for development and assessment of the code ATHLET

    Energy Technology Data Exchange (ETDEWEB)

    Teschendorff, V.; Austregesilo, H.; Lerchl, G. [Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) mbH Forschungsgelaende, Garching (Germany)

    1997-07-01

    The thermal-hydraulic computer code ATHLET (Analysis of THermal-hydraulics of LEaks and Transients) is being developed by the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) for the analysis of anticipated and abnormal plant transients, small and intermediate leaks as well as large breaks in light water reactors. The aim of the code development is to cover the whole spectrum of design basis and beyond design basis accidents (without core degradation) for PWRs and BWRs with only one code. The main code features are: advanced thermal-hydraulics; modular code architecture; separation between physical models and numerical methods; pre- and post-processing tools; portability. The code has features that are of special interest for applications to small leaks and transients with accident management, e.g. initialization by a steady-state calculation, full-range drift-flux model, dynamic mixture level tracking. The General Control Simulation Module of ATHLET is a flexible tool for the simulation of the balance-of-plant and control systems including the various operator actions in the course of accident sequences with AM measures. The code development is accompained by a systematic and comprehensive validation program. A large number of integral experiments and separate effect tests, including the major International Standard Problems, have been calculated by GRS and by independent organizations. The ATHLET validation matrix is a well balanced set of integral and separate effects tests derived from the CSNI proposal emphasizing, however, the German combined ECC injection system which was investigated in the UPTF, PKL and LOBI test facilities.

  9. Methodology, status and plans for development and assessment of the code ATHLET

    International Nuclear Information System (INIS)

    Teschendorff, V.; Austregesilo, H.; Lerchl, G.

    1997-01-01

    The thermal-hydraulic computer code ATHLET (Analysis of THermal-hydraulics of LEaks and Transients) is being developed by the Gesellschaft fuer Anlagen- und Reaktorsicherheit (GRS) for the analysis of anticipated and abnormal plant transients, small and intermediate leaks as well as large breaks in light water reactors. The aim of the code development is to cover the whole spectrum of design basis and beyond design basis accidents (without core degradation) for PWRs and BWRs with only one code. The main code features are: advanced thermal-hydraulics; modular code architecture; separation between physical models and numerical methods; pre- and post-processing tools; portability. The code has features that are of special interest for applications to small leaks and transients with accident management, e.g. initialization by a steady-state calculation, full-range drift-flux model, dynamic mixture level tracking. The General Control Simulation Module of ATHLET is a flexible tool for the simulation of the balance-of-plant and control systems including the various operator actions in the course of accident sequences with AM measures. The code development is accompained by a systematic and comprehensive validation program. A large number of integral experiments and separate effect tests, including the major International Standard Problems, have been calculated by GRS and by independent organizations. The ATHLET validation matrix is a well balanced set of integral and separate effects tests derived from the CSNI proposal emphasizing, however, the German combined ECC injection system which was investigated in the UPTF, PKL and LOBI test facilities

  10. Five-way smoking status classification using text hot-spot identification and error-correcting output codes.

    Science.gov (United States)

    Cohen, Aaron M

    2008-01-01

    We participated in the i2b2 smoking status classification challenge task. The purpose of this task was to evaluate the ability of systems to automatically identify patient smoking status from discharge summaries. Our submission included several techniques that we compared and studied, including hot-spot identification, zero-vector filtering, inverse class frequency weighting, error-correcting output codes, and post-processing rules. We evaluated our approaches using the same methods as the i2b2 task organizers, using micro- and macro-averaged F1 as the primary performance metric. Our best performing system achieved a micro-F1 of 0.9000 on the test collection, equivalent to the best performing system submitted to the i2b2 challenge. Hot-spot identification, zero-vector filtering, classifier weighting, and error correcting output coding contributed additively to increased performance, with hot-spot identification having by far the largest positive effect. High performance on automatic identification of patient smoking status from discharge summaries is achievable with the efficient and straightforward machine learning techniques studied here.

  11. Comparisons of the simulation results using different codes for ADS spallation target

    International Nuclear Information System (INIS)

    Yu Hongwei; Fan Sheng; Shen Qingbiao; Zhao Zhixiang; Wan Junsheng

    2002-01-01

    The calculations to the standard thick target were made by using different codes. The simulation of the thick Pb target with length of 60 cm, diameter of 20 cm bombarded with 800, 1000, 1500 and 2000 MeV energetic proton beam was carried out. The yields and the spectra of emitted neutron were studied. The spallation target was simulated by SNSP, SHIELD, DCM/CEM (Dubna Cascade Model /Cascade Evaporation Mode) and LAHET codes. The Simulation Results were compared with experiments. The comparisons show good agreement between the experiments and the SNSP simulated leakage neutron yield. The SHIELD simulated leakage neutron spectra are in good agreement with the LAHET and the DCM/CEM simulated leakage neutron spectra

  12. Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

    International Nuclear Information System (INIS)

    Lee, A.G.; Wilkin, G.B.

    1996-03-01

    During the 'Workshop on R and D needs' at the 3rd Meeting of the International Group on Research Reactors (IGORR-III), the participants agreed that it would be useful to compile a survey of the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods various organizations use to verify and validate their codes and libraries. Five organizations, Atomic Energy of Canada Limited (AECL, Canada), China Institute of Atomic Energy (CIAE, People's Republic of China), Japan Atomic Energy Research Institute (JAERI, Japan), Oak Ridge National Laboratories (ORNL, USA), and Siemens (Germany) responded to the survey. The results of the survey are compiled in this report. (author) 36 refs., 3 tabs

  13. Verification of fire and explosion accident analysis codes (facility design and preliminary results)

    International Nuclear Information System (INIS)

    Gregory, W.S.; Nichols, B.D.; Talbott, D.V.; Smith, P.R.; Fenton, D.L.

    1985-01-01

    For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has resulted in three computer codes: FIRAC, EXPAC, and TORAC. These codes are designed to predict the effects of fires, explosions, and tornadoes in nuclear facilities. Particular emphasis is placed on the movement of airborne radioactive material through the gaseous effluent treatment system of a nuclear installation. The design, construction, and calibration of an experimental ventilation system to verify the fire and explosion accident analysis codes are described. The facility features a large industrial heater and several aerosol smoke generators that are used to simulate fires. Both injected thermal energy and aerosol mass can be controlled using this equipment. Explosions are simulated with H 2 /O 2 balloons and small explosive charges. Experimental measurements of temperature, energy, aerosol release rates, smoke concentration, and mass accumulation on HEPA filters can be made. Volumetric flow rate and differential pressures also are monitored. The initial experiments involve varying parameters such as thermal and aerosol rate and ventilation flow rate. FIRAC prediction results are presented. 10 figs

  14. Three-dimensional thermal hydraulic best estimate code BAGIRA: new results of verification

    International Nuclear Information System (INIS)

    Peter Kohut; Sergey D Kalinichenko; Alexander E Kroshilin; Vladimir E Kroshilin; Alexander V Smirnov

    2005-01-01

    Full text of publication follows: BAGIRA is a three-dimensional inhomogeneous two-velocity two-temperature thermal hydraulic code of best estimate, elaborated in VNIIAES for modeling two-phase flows in the primary circuit and steam generators of VVER-type nuclear reactors under various accident, transient or normal operation conditions. In this talk we present verification results of the BAGIRA code, obtained on the basis of different experiments performed on special and integral thermohydraulic experimental facilities as well as on real NPPs. Special attention is paid to the verification of three-dimensional flow models. Besides that we expose new results of the code benchmark analysis made on the basis of two recent LOCA-type experiments - 'Leak 2 x 25% from the hot leg double-side rupture' and 'Leak 3% from the cold leg' - performed on the PSB-VVER integral test facility (Electrogorsk Research and Engineering Center, Electrogorsk, Russia) - the most up-to-date Russian large-scale four-loop unit which has been designed for modelling the primary circuit of VVER-1000 type reactors. (authors)

  15. ATLAS RPC commissioning status and cosmic ray test results

    CERN Document Server

    Bianco, Michele

    2009-01-01

    The muon trigger system of the ATLAS experiment consists of several sub-systems and each of them need to be tested and certified before LHC operation. In the barrel region Resistive Plate Chambers are employed. RPC detector and its level-1 trigger electronics are designed to detect and select high momentum muons with high time resolution and good tracking capability for a total surface of about 4000 m2. The commissioning phase provided an unique opportunity to demonstrate, before LHC start-up, the functionality of the muon trigger components such as detector chambers, level-1 trigger electronics, detector slow control system, data acquisition chain, software and computing. We present the status of ATLAS RPC detector, the problems met during the commissioning and the solutions found and, finally, its performances as obtained by acquiring cosmic rays.

  16. AMENDMENTS TO THE FISCAL CODE REGARDING THE EXPENDITURES AND THE DETERMINATION OF THE EXERCISE RESULT

    Directory of Open Access Journals (Sweden)

    HOLT GHEORGHE

    2017-02-01

    Full Text Available rct Fiscal Code has brought many changes in the structure of the expenses used to calculate the results of the exercise and, thus, the profits tax. It treats the three items of expense categories (deductibles, with limited deductibility and non-deductible, bringing numerous changes in the structure of each of them. Expenses is recorded as decreases in economic benefits during the accounting period as outflows or decreases in assets and increases in the value of debt, which is reflected in the reductions of equity, other than those arising from their distribution to shareholders. The Fiscal Code has brought many changes to tax legislation in Romania, all the titles being affected, a particular importance being awarded to the changes regarding to the expenses deductibility, items that are the subject of this material. The basic concept regarding the deduction of expenses has been reformulated in the Fiscal Code, so that - currently - are deductible expenses that are performed for business purposes, unlike the general rule of deductibility valid until 31 December 2015, that were deductible only those expenses incurred in order to achieve taxable income.

  17. HYDROCOIN [HYDROlogic COde INtercomparison] Level 1: Benchmarking and verification test results with CFEST [Coupled Fluid, Energy, and Solute Transport] code: Draft report

    International Nuclear Information System (INIS)

    Yabusaki, S.; Cole, C.; Monti, A.M.; Gupta, S.K.

    1987-04-01

    Part of the safety analysis is evaluating groundwater flow through the repository and the host rock to the accessible environment by developing mathematical or analytical models and numerical computer codes describing the flow mechanisms. This need led to the establishment of an international project called HYDROCOIN (HYDROlogic COde INtercomparison) organized by the Swedish Nuclear Power Inspectorate, a forum for discussing techniques and strategies in subsurface hydrologic modeling. The major objective of the present effort, HYDROCOIN Level 1, is determining the numerical accuracy of the computer codes. The definition of each case includes the input parameters, the governing equations, the output specifications, and the format. The Coupled Fluid, Energy, and Solute Transport (CFEST) code was applied to solve cases 1, 2, 4, 5, and 7; the Finite Element Three-Dimensional Groundwater (FE3DGW) Flow Model was used to solve case 6. Case 3 has been ignored because unsaturated flow is not pertinent to SRP. This report presents the Level 1 results furnished by the project teams. The numerical accuracy of the codes is determined by (1) comparing the computational results with analytical solutions for cases that have analytical solutions (namely cases 1 and 4), and (2) intercomparing results from codes for cases which do not have analytical solutions (cases 2, 5, 6, and 7). Cases 1, 2, 6, and 7 relate to flow analyses, whereas cases 4 and 5 require nonlinear solutions. 7 refs., 71 figs., 9 tabs

  18. CODES AND PRACTICES OF IMPLEMENTATION OF CORPORATE GOVERNANCE IN ROMANIA AND RESULTS REPORTING

    Directory of Open Access Journals (Sweden)

    GROSU MARIA

    2011-12-01

    Full Text Available Corporate governance refers to the manner in which companies are directed and controlled. Business management was always guided by certain principles, but the current meaning of corporate governance concerns and the contribution that companies must have the overall development of modern society. Romania used quite late in adopting a code of good practice in corporate governance, being driven, in particular, the privatization process, but also the transfer of control and surveillance of political organizations by the Board of Directors (BD. Adoption of codes of corporate governance is necessary to harmonize internal business requirements of a functioning market economy. In addition, the CEE countries, the European Commission adopted an action plan announcing measures to modernize company law and enhance corporate governance. Romania takes steps in this direction by amending the Company Law, and other regulations, although the practice does not necessarily keep pace with the requirements. This study aims on the one hand, an analysis of the evolution of corporate governance codes adopted in Romania, but also an empirical research of the implementation of corporate governance principles of a representative sample of companies listed on the Bucharest Stock Exchange (BSE. Consider relevant research methodology, because the issuer of the Codes of CG in Romania is BSE listed companies requesting their voluntary implementation. Implementation results are summarized and interpreted at the expense of public reports of the companies studied. Most studies undertaken in this direction have been made on multinational companies which respects the rule of corporate governance codes of countries of origin. In addition, many studies also emphasize the fair treatment of stakeholders rather than on models of governance adopted (monist/dualist with implications for optimizing economic objectives but also social. Undertaken research attempts to highlight on the one

  19. Further results on binary convolutional codes with an optimum distance profile

    DEFF Research Database (Denmark)

    Johannesson, Rolf; Paaske, Erik

    1978-01-01

    Fixed binary convolutional codes are considered which are simultaneously optimal or near-optimal according to three criteria: namely, distance profiled, free distanced_{ infty}, and minimum number of weightd_{infty}paths. It is shown how the optimum distance profile criterion can be used to limit...... codes. As a counterpart to quick-look-in (QLI) codes which are not "transparent," we introduce rateR = 1/2easy-look-in-transparent (ELIT) codes with a feedforward inverse(1 + D,D). In general, ELIT codes haved_{infty}superior to that of QLI codes....

  20. The European source-term evaluation code ASTEC: status and applications, including CANDU plant applications

    International Nuclear Information System (INIS)

    Van Dorsselaere, J.P.; Giordano, P.; Kissane, M.P.; Montanelli, T.; Schwinges, B.; Ganju, S.; Dickson, L.

    2004-01-01

    Research on light-water reactor severe accidents (SA) is still required in a limited number of areas in order to confirm accident-management plans. Thus, 49 European organizations have linked their SA research in a durable way through SARNET (Severe Accident Research and management NETwork), part of the European 6th Framework Programme. One goal of SARNET is to consolidate the integral code ASTEC (Accident Source Term Evaluation Code, developed by IRSN and GRS) as the European reference tool for safety studies; SARNET efforts include extending the application scope to reactor types other than PWR (including VVER) such as BWR and CANDU. ASTEC is used in IRSN's Probabilistic Safety Analysis level 2 of 900 MWe French PWRs. An earlier version of ASTEC's SOPHAEROS module, including improvements by AECL, is being validated as the Canadian Industry Standard Toolset code for FP-transport analysis in the CANDU Heat Transport System. Work with ASTEC has also been performed by Bhabha Atomic Research Centre, Mumbai, on IPHWR containment thermal hydraulics. (author)

  1. Cooperative biogas plants. Economic results and analyses. Status report 1998

    International Nuclear Information System (INIS)

    Hjort-Gregersen, K.

    1998-11-01

    The years 1995 - 1998 have been characterised by stabilisation of operation and economy of the Danish co-operative biogas plants. Most of the plants have obtained increasingly better economic results although the increase has been less significant than during earlier periods. There are several reasons for the increase. Most of the plants have been able to increase the sales income because of larger amounts of biomass available resulting in an increased biogas production. Furthermore it has been possible to contain the income level for biomass receipt. Several plants have established gas collection in storage tanks, which has resulted in increased gas yield. The operational stability related to both technique and processes have improved. The operational costs have been stabilised and are under control at most of the plants. The improved economic results have resulted in most of the plants having a satisfactory operation and economy. However, it must be stressed that some of the oldest plants have not been able to settle the investment dept at normal conditions. Also some, even rather new plants, still are in a difficult economic situation. Most of the plants established in the 90'ies have had a good start both operationally and economically. Thus the economic risk of establishing a plant has been reduced compared to earlier years. Generally the prerequisites for establishing a biogas plant are favourable economic conditions and quality assurance of the project. (LN)

  2. Nuclear Reactor Component Code CUPID-I: Numerical Scheme and Preliminary Assessment Results

    International Nuclear Information System (INIS)

    Cho, Hyoung Kyu; Jeong, Jae Jun; Park, Ik Kyu; Kim, Jong Tae; Yoon, Han Young

    2007-12-01

    A component scale thermal hydraulic analysis code, CUPID (Component Unstructured Program for Interfacial Dynamics), is being developed for the analysis of components of a nuclear reactor, such as reactor vessel, steam generator, containment, etc. It adopted three-dimensional, transient, two phase and three-field model. In order to develop the numerical schemes for the three-field model, various numerical schemes have been examined including the SMAC, semi-implicit ICE, SIMPLE, Row Scheme and so on. Among them, the ICE scheme for the three-field model was presented in the present report. The CUPID code is utilizing unstructured mesh for the simulation of complicated geometries of the nuclear reactor components. The conventional ICE scheme that was applied to RELAP5 and COBRA-TF, therefore, were modified for the application to the unstructured mesh. Preliminary calculations for the unstructured semi-implicit ICE scheme have been conducted for a verification of the numerical method from a qualitative point of view. The preliminary calculation results showed that the present numerical scheme is robust and efficient for the prediction of phase changes and flow transitions due to a boiling and a flashing. These calculation results also showed the strong coupling between the pressure and void fraction changes. Thus, it is believed that the semi-implicit ICE scheme can be utilized for transient two-phase flows in a component of a nuclear reactor

  3. Nuclear Reactor Component Code CUPID-I: Numerical Scheme and Preliminary Assessment Results

    Energy Technology Data Exchange (ETDEWEB)

    Cho, Hyoung Kyu; Jeong, Jae Jun; Park, Ik Kyu; Kim, Jong Tae; Yoon, Han Young

    2007-12-15

    A component scale thermal hydraulic analysis code, CUPID (Component Unstructured Program for Interfacial Dynamics), is being developed for the analysis of components of a nuclear reactor, such as reactor vessel, steam generator, containment, etc. It adopted three-dimensional, transient, two phase and three-field model. In order to develop the numerical schemes for the three-field model, various numerical schemes have been examined including the SMAC, semi-implicit ICE, SIMPLE, Row Scheme and so on. Among them, the ICE scheme for the three-field model was presented in the present report. The CUPID code is utilizing unstructured mesh for the simulation of complicated geometries of the nuclear reactor components. The conventional ICE scheme that was applied to RELAP5 and COBRA-TF, therefore, were modified for the application to the unstructured mesh. Preliminary calculations for the unstructured semi-implicit ICE scheme have been conducted for a verification of the numerical method from a qualitative point of view. The preliminary calculation results showed that the present numerical scheme is robust and efficient for the prediction of phase changes and flow transitions due to a boiling and a flashing. These calculation results also showed the strong coupling between the pressure and void fraction changes. Thus, it is believed that the semi-implicit ICE scheme can be utilized for transient two-phase flows in a component of a nuclear reactor.

  4. Validation of Code ASTEC with LIVE-L1 Experimental Results

    International Nuclear Information System (INIS)

    Bachrata, Andrea

    2008-01-01

    The severe accidents with core melting are considered at the design stage of project at Generation 3+ of Nuclear Power Plants (NPP). Moreover, there is an effort to apply the severe accident management to the operated NPP. The one of main goals of severe accidents mitigation is corium localization and stabilization. The two strategies that fulfil this requirement are: the in-vessel retention (e.g. AP-600, AP- 1000) and the ex-vessel retention (e.g. EPR). To study the scenario of in-vessel retention, a large experimental program and the integrated codes have been developed. The LIVE-L1 experimental facility studied the formation of melt pools and the melt accumulation in the lower head using different cooling conditions. Nowadays, a new European computer code ASTEC is being developed jointly in France and Germany. One of the important steps in ASTEC development in the area of in-vessel retention of corium is its validation with LIVE-L1 experimental results. Details of the experiment are reported. Results of the ASTEC (module DIVA) application to the analysis of the test are presented. (author)

  5. Experiences and results multitasking a hydrodynamics code on global and local memory machines

    International Nuclear Information System (INIS)

    Mandell, D.

    1987-01-01

    A one-dimensional, time-dependent Lagrangian hydrodynamics code using a Godunov solution method has been multimasked for the Cray X-MP/48, the Intel iPSC hypercube, the Alliant FX series and the IBM RP3 computers. Actual multitasking results have been obtained for the Cray, Intel and Alliant computers and simulated results were obtained for the Cray and RP3 machines. The differences in the methods required to multitask on each of the machines is discussed. Results are presented for a sample problem involving a shock wave moving down a channel. Comparisons are made between theoretical speedups, predicted by Amdahl's law, and the actual speedups obtained. The problems of debugging on the different machines are also described

  6. CryoSat: Mission Status, Achievements and New Results

    Science.gov (United States)

    Francis, R.; Wingham, D.; Cullen, R.; Parrinello, T.

    2010-12-01

    After 10 years of development and one failed launch attempt the CryoSat mission was successfully launched on 8 April 2010. The main payload instrument, the advanced SIRAL radar altimeter, was switched on just 3 days after launch and made its first measurements during a pass over Antarctica. Although data flow to the expert team at UCL was operational from the start, two more months were needed to iron out some system issues and bugs before data could be released to the calibration and validation teams. The process of further optimising the system performance as well as comparing measurements to known surface data has continued through the commissioning phase, ending in October 2010. The end of the commissioning phase marks the transition to routine operations and the release of data to registered Principal Investigators. The results from SIRAL are unlike those from previous altimeters. Representative results will be described, highlighting improvements and demonstrating the level of detail which can be observed and measured. In addition to its ‘design’ targets CryoSat has made measurements over various ocean and land areas. The ocean results, in particular, are indicative of the measurements which will be delivered by Sentinel-3’s SRAL instrument. These will also be described. The satellite in flight has proved to be using less propellant than foreseen and, based on the commissioning results, the prognosis for its future performance will be outlined.

  7. Cassandra - D7.3.5 - M30 status : Report dissemination results

    NARCIS (Netherlands)

    Klievink, A.J.

    2014-01-01

    This deliverable is a status report on the dissemination activities and results in the CASSANDRA project. These status reports are made regularly, with one more to come at the project’s finish. Together, these make up deliverable D7.3 – Dissemination results. In this report, the results of the

  8. Cassandra - D7.3.4 - M24 status report dissemination results

    NARCIS (Netherlands)

    Klievink, A.J.

    2013-01-01

    This deliverable is a status report on the dissemination activities and results in the CASSANDRA project. These status reports are made regularly, with two more to come. Together, these make up deliverable D7.3 – Dissemination results. In this fifth report, the results of the dissemination

  9. COCOSYS: Status of development and validation of the German containment code system

    International Nuclear Information System (INIS)

    Allelein, H.-J.; Arndt, S.; Klein-Hessling, W.; Schwarz, S.; Spengler, C.; Weber, G.

    2006-01-01

    For the simulation of severe accident propagation in containments of nuclear power plants it is necessary to assess the efficiency of a severe accident measures under conditions as realistic as possible. Therefore the German containment code system COCOSYS is under development and validation at GRS. The main objective is to provide a code system on the basis of mostly mechanistic models for the comprehensive simulation of all relevant processes and plant states during severe accidents in the containment of light water reactors covering the design basis accidents, too. COCOSYS is being used for the identification of possible deficits in plant safety, qualification of the safety reserves of the entire system, assessment of damage-limiting or mitigating accident management measures, support of integral codes in PSA level 2 studies and safety evaluation of new plants. COCOSYS is composed for three main modules, which are separate executable files. The communication is realized via PVM (parallel virtual machine). The thermal hydraulic main module (THY) contains several specific models relevant for the simulation of severe accidents. Beside the usual capabilities to calculate the gas distribution and thermal behavior inside the containment, there are special models for the simulation of Hydrogen deflagration, pressure suppression systems etc. Further detailed models exist for the simulation of safety systems, like catalytic recombiners (PAR's), safety relief valves (used in WWR-440/V-230 type plants), ice condenser model, pump and spray system models for the complete simulation of cooling systems. The aerosol and fission product part (AFP) describes the aerosol behavior of nonsoluble and as well as hygroscopic aerosols, iodine chemistry and fission transport. Further the decay process of nuclides is considered using ORIGIN like routines. The corium concrete interaction (CCI) main module is based on an improved version of WECHSL extended by the ChemApp module for the

  10. The DAFT/FADA Survey status and latest results

    Science.gov (United States)

    Guennou, L.

    2011-12-01

    We present here the latest results obtained from the American French collaboration called the Dark energy American French Team/French American DArk energy Team (DAFT/FADA). The goal of the DAFT/FADA collaboration is to carry out a weak lensing tomography survey of z = 0.4-0.9 rich clusters of galaxies. Unlike supernovae or other methods such as cluster of galaxy counts, weak lensing tomography is purely based on geometry and does not depend on knowledge of the physics of the objects used as distance indicators. In addition, the reason for analyzing observations in the direction of clusters is that the shear signal is enhanced by about 10 over the field. Our work will eventually contain results obtained on 91 rich clusters from the HST archive combined with ground based work to obtain photo-zs. This combination of photo-z and weak lensing tomography will enable us to constrain the equation of state of dark energy. We present here the latest results obtained so far in this study.

  11. Status of SACRD: a data base for fast reactor safety computer codes

    International Nuclear Information System (INIS)

    Greene, N.M.; Flanagan, G.F.; Alter, H.

    1982-01-01

    In 1975 work was initiated to provide a central computerized data collection of evaluated data for use in fast reactor safety computer codes. This data base is called SACRD and is intended to encompass handbook and other nonproblem-dependent data related to LMFBR's, especially at extreme conditions where little or no experimental data are available. Version 1 of the data base was released in the latter part of 1978 and remained the standard version until Version 81, which was released in October 1981

  12. Present status of nucleon-meson transport code NMTC/JAERI

    International Nuclear Information System (INIS)

    Takada, H.; Meigo, S.

    2001-01-01

    The nucleon-meson transport code NMTC/JAM has been developed for the neutronics design study of the joint project for high-intensity proton accelerators with a power of mega-watts. The applicable energy range is extended by the inclusion of the jet AA microscopic transport model (JAM). The nucleon-nucleus cross sections are also updated for accurate transport calculation. The applicability of NMTC/JAM is studied through the analyses of thick target experiments such as neutron transmission through shield and activation reaction rate measurements. (orig.)

  13. Status of the CP lear experiment and first results

    International Nuclear Information System (INIS)

    Santoni, C.; Adler, R.; Angelopoulos, A.; Apostolakis, A.; Aslanides, E.; Backenstoss, G.; Bee, C.B.; Bennet, J.; Beveren, E.V.; Bloch, P.; Bula, C.; Burgun, G.; Carlson, P.; Carvalho, J.; Charalambous, S.; Chardalas, M.; Cobbaert, H.; Dedoussis, S.; Dejardin, M.; Derre, J.; Dodgson, M.; Doussee, J.C.; Duclos, J.; Ealet, A.; Eckart, B.; Faravel, L.; Fassnacht, P.; Faure, J.L.; Felder, C.; Ferreira-Marques, R.; Fetscher, W.; Fidecaro, M.; Filipcic, A.; Francis, D.; Fry, J.; Fuglesang, C.; Gabathuler, E.; Gamet, R.; Garreta, D.; Geralis, T.; Gerber, H.J.; Go, A.; Gumpliger, P.; Guyot, C.; Harrison, P.F.; Hayman, P.J.; Heyes, W.G.; Hollander, R.W.; Jansson, K.; Johner, H.J.; Jon-And, K.; Kerek, A.; Kern, J.; Kettle, P.R.; Kochowski, C.; Kokkas, P.; Kossionides, E.; Kreuger, R.; Lawry, T.; Gac, R. le; Machado, E.; Maley, P.; Manthos, N.; Marel, G.; Marotte, P.; Mikuz, M.; Miller, J.; Montanet, F.; Nakada, T.; Onofre, A.; Pagels, B.; Paradelis, T.; Pavlopoulos, P.; Pelucchi, F.; Pinto da Cunha, J.; Policarpo, A.; Postma, H.; Rickenbach, R.; Roberts, B.L.; Rozaki, E.; Ruf, T.; Sacks, L.; Sakeliou, L.; Sanders, P.; Sarigianis, K.; Schaller, L.; Schopper, A.; Seljak, U.; Szilagyi, S.; Tauscher, L.; Thibault, C.; Touchard, F.; Touramanis, C.; Triantis, F.; Troester, D.A.; Putte, M. van de; Eijk, C.W.W. van; Varner, G.; Vlachos, S.; Weber, P.; Witzig, C.; Zavrtanik, D.; Zimmermann, D.

    1991-01-01

    The aim of the CP LEAR experiment is to study symmetry-violation effects, making use of tagged K 0 's and anti K 0 's. The detector, although missing some electronic components, has been operational for a few weeks at the end of 1989 at the CERN Low-Energy Antiproton Ring (LEAR). At the moment, the analysis of the data is in progress. This paper gives a description of the experimental method and of the detector; the sensitivities of some measurements and some preliminary results are also discussed. (orig.)

  14. Summary of aerosol code-comparison results for LWR aerosol containment tests LA1, LA2, and LA3

    International Nuclear Information System (INIS)

    Wright, A.L.; Wilson, J.H.; Arwood, P.C.

    1987-01-01

    The light-water reactor (LWR) aerosol containment experiments (LACE) are being performed in Richland, Washington, at the Hanford Engineering Development Laboratory under the leadership of an international project board and the Electric Power Research Institute. These tests have two objectives: (1) to investigate, at large scale, the inherent aerosol retention behavior in LWR containments under simulated severe accident conditions, and (2) to provide an experimental data base for validating aerosol behavior and thermal-hydraulic computer codes. Aerosol computer-code comparison activities for the LACE tests are being coordinated at the Oak Ridge National Laboratory. For each of the six experiments, pretest calculations (for code-to-code comparisons) and blind post-test calculations (for code-to-test data comparisons) are being performed. This paper presents a summary of the pretest aerosol-code results for tests LA1, LA2, and LA3

  15. Results and status of the Edelweiss Wimp search experiment

    International Nuclear Information System (INIS)

    Benoit, A.; Berge, L.; Blumer, J.; Broniatowski, A.; Censier, B.; Chabert, L.; Chambon, B.; Chapellier, M.; Chardin, G.; Charvin, P.; Jesus, M. de; Drain, D.; Di Stefano, P.; Dumoulin, L.; Eitel, K.; Fesquet, M.; Firucci, S.; Gascon, J.; Gerbier, G.; Gerlic, E.; Goldbach, C.; Goyot, M.; Gros, M.; Habermahl, F.; Horn, M.; Hadjout, J.P.; Herve, S.; Juillard, A.; Kikuchi, C.; Lesquen, A. de; Luca, M.; Mallet, J.; Marnieros, S.; Martineau, O.; Mosca, L.; Navick, X.F.; Nollez, G.; Pari, P.; Riccio, C.; Sanglard, V.; Stern, M.; Vagneron, L.; Villard, V.

    2005-01-01

    In the Edelweiss experiment, nuclear recoils induced by elastic collisions with WIMPs (weakly interacting massive particle) from the galactic halo are identified in low-temperature Ge detectors where the ratio of the heat and ionization signals provide an event-by-event discrimination of nuclear recoils from the dominant background coming from γ-rays interactions. The Edelweiss experiment is located in the Modane underground facility in order to cut the muon flux drastically. We present here the results obtained during the first part of the experiment named Edelweiss-I that ended in the beginning of 2004. Since october 2002, 3 optimized 320 grams detectors have been simultaneously operated at a regulated temperature of 0.017 K and about 50 kg*day were added to the previous published data. These data are still under analysis but preliminary results concerning the upper limit at 90% CL (confidence level) confirm the limit already published in 2002. The first run of Edelweiss-II is due to begin during summer 2005, we are expecting to gain 2 orders of magnitude in terms of detector sensitivity and reach 0.002 events/day*kg. (A.C.)

  16. Uprated OMS Engine Status-Sea Level Testing Results

    Science.gov (United States)

    Bertolino, J. D.; Boyd, W. C.

    1990-01-01

    The current Space Shuttle Orbital Maneuvering Engine (OME) is pressure fed, utilizing storable propellants. Performance uprating of this engine, through the use of a gas generator driven turbopump to increase operating pressure, is being pursued by the NASA Johnson Space Center (JSC). Component level design, fabrication, and test activities for this engine system have been on-going since 1984. More recently, a complete engine designated the Integrated Component Test Bed (ICTB), was tested at sea level conditions by Aerojet. A description of the test hardware and results of the sea level test program are presented. These results, which include the test condition operating envelope and projected performance at altitude conditions, confirm the capability of the selected Uprated OME (UOME) configuration to meet or exceed performance and operational requirements. Engine flexibility, demonstrated through testing at two different operational mixture ratios, along with a summary of projected Space Shuttle performance enhancements using the UOME, are discussed. Planned future activities, including ICTB tests at simulated altitude conditions, and recommendations for further engine development, are also discussed.

  17. ASTEC V2 severe accident integral code main features, current V2.0 modelling status, perspectives

    International Nuclear Information System (INIS)

    Chatelard, P.; Reinke, N.; Arndt, S.; Belon, S.; Cantrel, L.; Carenini, L.; Chevalier-Jabet, K.; Cousin, F.; Eckel, J.; Jacq, F.; Marchetto, C.; Mun, C.; Piar, L.

    2014-01-01

    The severe accident integral code ASTEC, jointly developed since almost 20 years by IRSN and GRS, simulates the behaviour of a whole nuclear power plant under severe accident conditions, including severe accident management by engineering systems and procedures. Since 2004, the ASTEC code is progressively becoming the reference European severe accident integral code through in particular the intensification of research activities carried out in the frame of the SARNET European network of excellence. The first version of the new series ASTEC V2 was released in 2009 to about 30 organizations worldwide and in particular to SARNET partners. With respect to the previous V1 series, this new V2 series includes advanced core degradation models (issued from the ICARE2 IRSN mechanistic code) and necessary extensions to be applicable to Gen. III reactor designs, notably a description of the core catcher component to simulate severe accidents transients applied to the EPR reactor. Besides these two key-evolutions, most of the other physical modules have also been improved and ASTEC V2 is now coupled to the SUNSET statistical tool to make easier the uncertainty and sensitivity analyses. The ASTEC models are today at the state of the art (in particular fission product models with respect to source term evaluation), except for quenching of a severely damage core. Beyond the need to develop an adequate model for the reflooding of a degraded core, the main other mean-term objectives are to further progress on the on-going extension of the scope of application to BWR and CANDU reactors, to spent fuel pool accidents as well as to accidents in both the ITER Fusion facility and Gen. IV reactors (in priority on sodium-cooled fast reactors) while making ASTEC evolving towards a severe accident simulator constitutes the main long-term objective. This paper presents the status of the ASTEC V2 versions, focussing on the description of V2.0 models for water-cooled nuclear plants

  18. Methodology, status, and plans for development and assessment of the TRAC code

    International Nuclear Information System (INIS)

    Boyack, B.E.; Nelson, R.A.; Jolly-Woodruff, S.

    1996-01-01

    The Transient Reactor Analysis Code (TRAC) is a state-of-the-art, best-estimate, transient system analysis computer code for analyzing geometrically complex multidimensional thermal hydraulic systems, primarily nuclear reactor power plants. TRAC is used by government and industry organizations for design and safety analysis, phenomenological studies, operational transient analysis, evaluating emergency operating procedures, simulator support and operator training, and for assessment of data involving basic experiments, separate effects tests, and plant operations. TRAC will calculate one- and three-dimensional (rectilinear and cylindrical coordinates) fluid flow involving gas, liquid, and mixture states. Although TRAC has many capabilities, it also has limitations. Some limitations arise from its implementation, dating from the 1970s. Rapid advances in hardware and software engineering highlight TRAC's inefficiencies; however, other limitations relate to the level of scientific knowledge regarding two-phase flow physics. These limitations will continue until such time as the fundamental understanding of two-phase flows is extended. Presently, several development activities are either in progress or soon to begin that will fundamentally improve TRAC. Foremost among these are reimplementation of the current TRAC data structures in Fortran 90 and the integrated development of closure packages for large-break loss-of-coolant accident applications

  19. 1980 Annual status report: utilization of research results

    International Nuclear Information System (INIS)

    1981-01-01

    Patents and licences were part of normal JRC activity since its origin: the new feature of this programme is that through an increased JRC activity in this field as well as a structured support to D.G. XIII, the process of utilization can be started at an earlier stage, with the deliberate purpose of achieving practical results as early as possible, through an adequate R and D effort. Key element of this process is the systematic identification, within JRC programme, of those research areas, concepts, ideas, that might present interest for industry and for the public sector. In this respect D.G. XIII by its market survey and contacts with industry is providing JRC with the essential information to carry out this programme

  20. Status and oscillation results of the OPERA experiment

    International Nuclear Information System (INIS)

    Brunet, F.

    2014-01-01

    The OPERA experiment, placed 730 km downstream the CERN neutrino beam to Gran Sasso (CNGS) in the LNGS underground laboratory, is designed to measure muon-neutrino to tau-neutrino oscillations in a direct appearance mode. The hybrid apparatus consists of an emulsion/lead target complemented by electronic detectors. Due to the target structure made of thin lead plates, OPERA is able to detect electromagnetic showers, allowing searches for tau electronic decays and for oscillations from muon-neutrino to electron-neutrino. The experimental set-up and associated facilities used to extract data recorded in the emulsion will be described, with the special procedures aimed at locating interaction vertices and detect short decay topologies. OPERA is taking data since 2008. A first nu-tau interaction candidate was already published in 2010. New results with increased statistics will be presented. In particular, an overview of the studies related to electrons will be shown. (author)

  1. Results from the Veterans Health Administration ICD-10-CM/PCS Coding Pilot Study.

    Science.gov (United States)

    Weems, Shelley; Heller, Pamela; Fenton, Susan H

    2015-01-01

    The Veterans Health Administration (VHA) of the US Department of Veterans Affairs has been preparing for the October 1, 2015, conversion to the International Classification of Diseases, Tenth Revision, Clinical Modification and Procedural Coding System (ICD-10-CM/PCS) for more than four years. The VHA's Office of Informatics and Analytics ICD-10 Program Management Office established an ICD-10 Learning Lab to explore expected operational challenges. This study was conducted to determine the effects of the classification system conversion on coding productivity. ICD codes are integral to VHA business processes and are used for purposes such as clinical studies, performance measurement, workload capture, cost determination, Veterans Equitable Resource Allocation (VERA) determination, morbidity and mortality classification, indexing of hospital records by disease and operations, data storage and retrieval, research purposes, and reimbursement. The data collection for this study occurred in multiple VHA sites across several months using standardized methods. It is commonly accepted that coding productivity will decrease with the implementation of ICD-10-CM/PCS. The findings of this study suggest that the decrease will be more significant for inpatient coding productivity (64.5 percent productivity decrease) than for ambulatory care coding productivity (6.7 percent productivity decrease). This study reveals the following important points regarding ICD-10-CM/PCS coding productivity: 1. Ambulatory care ICD-10-CM coding productivity is not expected to decrease as significantly as inpatient ICD-10-CM/PCS coding productivity. 2. Coder training and type of record (inpatient versus outpatient) affect coding productivity. 3. Inpatient coding productivity is decreased when a procedure requiring ICD-10-PCS coding is present. It is highly recommended that organizations perform their own analyses to determine the effects of ICD-10-CM/PCS implementation on coding productivity.

  2. Fission-product release modelling in the ASTEC integral code: the status of the ELSA module

    International Nuclear Information System (INIS)

    Plumecocq, W.; Kissane, M.P.; Manenc, H.; Giordano, P.

    2003-01-01

    Safety assessment of water-cooled nuclear reactors encompasses potential severe accidents where, in particular, the release of fission products (FPs) and actinides into the reactor coolant system (RCS) is evaluated. The ELSA module is used in the ASTEC integral code to model all releases into the RCS. A wide variety of experiments is used for validation: small-scale CRL, ORNL and VERCORS tests; large-scale Phebus-FP tests; etc. Being a tool that covers intact fuel and degraded states, ELSA is being improved maximizing the use of information from degradation modelling. Short-term improvements will include some treatment of initial FP release due to intergranular inventories and implementing models for release of additional structural materials (Sn, Fe, etc.). (author)

  3. Fission product transport in the primary system, important phenomena, and code status

    International Nuclear Information System (INIS)

    Gieseke, J.A.; Jordan, H.; Kuhlman, M.R.

    1990-01-01

    The purpose of this paper is to identify important issues concerning the transport and deposition of radionuclides in the reactor coolant system (RCS) under accident conditions and to examine how such issues are being treated or should be treated by the various available computer codes. In general, the RCS is a very important section of the transport pathway along which radionuclides move and by which they are attenuated as they travel after being released from the fuel. The RCS can serve as a sink for radionuclides that may deposit from the gas and react with surfaces, or can serve as a repository for materials deposited from the gas which are then available for later release into the transporting gas stream. The RCS may also have thermal hydraulic conditions that foster aerosol growth by condensation or agglomeration, and may provide an environment in which gas phase or heterogeneous chemical reactions may occur

  4. Impact of marital status on survival of gastric adenocarcinoma patients: Results from the Surveillance Epidemiology and End Results (SEER) Database

    OpenAIRE

    Qiu, Miaozhen; Yang, Dajun; Xu, Ruihua

    2016-01-01

    Marital status was found to be an independent prognostic factor for survival in various cancer types. In this study, we used the Surveillance, Epidemiology and End Results database to analyze the survival difference among different marital status in the United States. Gastric adenocarcinoma patients from 2004?2012 were enrolled for study. The 5-year cause specific survival (CSS) was our primary endpoint. Totally 29,074 eligible patients were identified. We found that more male patients were m...

  5. Results of comparative RBMK neutron computation using VNIIEF codes (cell computation, 3D statics, 3D kinetics). Final report

    Energy Technology Data Exchange (ETDEWEB)

    Grebennikov, A.N.; Zhitnik, A.K.; Zvenigorodskaya, O.A. [and others

    1995-12-31

    In conformity with the protocol of the Workshop under Contract {open_quotes}Assessment of RBMK reactor safety using modern Western Codes{close_quotes} VNIIEF performed a neutronics computation series to compare western and VNIIEF codes and assess whether VNIIEF codes are suitable for RBMK type reactor safety assessment computation. The work was carried out in close collaboration with M.I. Rozhdestvensky and L.M. Podlazov, NIKIET employees. The effort involved: (1) cell computations with the WIMS, EKRAN codes (improved modification of the LOMA code) and the S-90 code (VNIIEF Monte Carlo). Cell, polycell, burnup computation; (2) 3D computation of static states with the KORAT-3D and NEU codes and comparison with results of computation with the NESTLE code (USA). The computations were performed in the geometry and using the neutron constants presented by the American party; (3) 3D computation of neutron kinetics with the KORAT-3D and NEU codes. These computations were performed in two formulations, both being developed in collaboration with NIKIET. Formulation of the first problem maximally possibly agrees with one of NESTLE problems and imitates gas bubble travel through a core. The second problem is a model of the RBMK as a whole with imitation of control and protection system controls (CPS) movement in a core.

  6. Simulation of single-phase rod bundle flow. Comparison between CFD-code ESTET, PWR core code THYC and experimental results

    International Nuclear Information System (INIS)

    Mur, J.; Larrauri, D.

    1998-07-01

    Computer simulation of flow in configurations close to pressurized water reactor (PWR) geometry is of great interest for Electricite de France (EDF). Although simulation of the flow through a whole PWR core with an all purpose CFD-code is not yet achievable, such a tool cna be quite useful to perform numerical experiments in order to try and improve the modeling introduced in computer codes devoted to reactor core thermal-hydraulic analysis. Further to simulation in small bare rod bundle configurations, the present study is focused on the simulation, with CFD-code ESTET and PWR core code THYC, of the flow in the experimental configuration VATICAN-1. ESTET simulation results are compared on the one hand to local velocity and concentration measurements, on the other hand with subchannel averaged values calculated by THYC. As far as the comparison with measurements is concerned, ESTET results are quite satisfactory relatively to available experimental data and their uncertainties. The effect of spacer grids and the prediction of the evolution of an unbalanced velocity profile seem to be correctly treated. As far as the comparison with THYC subchannel averaged values is concerned, the difficulty of a direct comparison between subchannel averaged and local values is pointed out. ESTET calculated local values are close to experimental local values. ESTET subchannel averaged values are also close to THYC calculation results. Thus, THYC results are satisfactory whereas their direct comparison to local measurements could show some disagreement. (author)

  7. Sub-millimeter planar imaging with positron emitters: EGS4 code simulation and experimental results

    International Nuclear Information System (INIS)

    Bollini, D.; Del Guerra, A.; Di Domenico, G.

    1996-01-01

    Experimental data for Planar Imaging with positron emitters (pulse height, efficiency and spatial resolution) obtained with two matrices of 25 crystals (2 x 2 x 30 mm 3 each) of YAP:Ce coupled with a Position Sensitive PhotoMultiplier (Hamamatsu R2486-06) have been reproduced with high accuracy using the EGS4 code. Extensive simulation provides a detailed description of the performance of this type of detector as a function of the matrix granularity, the geometry of the detector and detection threshold. We present the Monte Carlo simulation and the preliminary experimental results of a prototype planar imaging system made of two matrices, each one consisting of 400 (2 x 2 x 30 mm 3 ) crystals of YAP-Ce

  8. Comparison and validation of the results of the AZNHEX v.1.0 code with the MCNP code simulating the core of a fast reactor cooled with sodium

    International Nuclear Information System (INIS)

    Galicia A, J.; Francois L, J. L.; Bastida O, G. E.; Esquivel E, J.

    2016-09-01

    The development of the AZTLAN platform for the analysis and design of nuclear reactors is led by Instituto Nacional de Investigaciones Nucleares (ININ) and divided into four working groups, which have well-defined activities to achieve significant progress in this project individually and jointly. Within these working groups is the users group, whose main task is to use the codes that make up the AZTLAN platform to provide feedback to the developers, and in this way to make the final versions of the codes are efficient and at the same time reliable and easy to understand. In this paper we present the results provided by the AZNHEX v.1.0 code when simulating the core of a fast reactor cooled with sodium at steady state. The validation of these results is a fundamental part of the platform development and responsibility of the users group, so in this research the results obtained with AZNHEX are compared and analyzed with those provided by the Monte Carlo code MCNP-5, software worldwide used and recognized. A description of the methodology used with MCNP-5 is also presented for the calculation of the interest variables and the difference that is obtained with respect to the calculated with AZNHEX. (Author)

  9. Comparison of Severe Accident Results Among SCDAP/RELAP5, MAAP, and MELCOR Codes

    International Nuclear Information System (INIS)

    Wang, T.-C.; Wang, S.-J.; Teng, J.-T.

    2005-01-01

    This paper demonstrates a large-break loss-of-coolant accident (LOCA) sequence of the Kuosheng nuclear power plant (NPP) and station blackout sequence of the Maanshan NPP with the SCDAP/RELAP5 (SR5), Modular Accident Analysis Program (MAAP), and MELCOR codes. The large-break sequence initiated with double-ended rupture of a recirculation loop. The main steam isolation valves (MSIVs) closed, the feedwater pump tripped, the reactor scrammed, and the assumed high-pressure and low-pressure spray systems of the emergency core cooling system (ECCS) were not functional. Therefore, all coolant systems to quench the core were lost. MAAP predicts a longer vessel failure time, and MELCOR predicts a shorter vessel failure time for the large-break LOCA sequence. The station blackout sequence initiated with a loss of all alternating-current (ac) power. The MSIVs closed, the feedwater pump tripped, and the reactor scrammed. The motor-driven auxiliary feedwater system and the high-pressure and low-pressure injection systems of the ECCS were lost because of the loss of all ac power. It was also assumed that the turbine-driven auxiliary feedwater pump was not functional. Therefore, the coolant system to quench the core was also lost. MAAP predicts a longer time of steam generator dryout, time interval between top of active fuel and bottom of active fuel, and vessel failure time than those of the SR5 and MELCOR predictions for the station blackout sequence. The three codes give similar results for important phenomena during the accidents, including SG dryout, core uncovery, cladding oxidation, cladding failure, molten pool formulation, debris relocation to the lower plenum, and vessel head failure. This paper successfully demonstrates the large-break LOCA sequence of the Kuosheng NPP and the station blackout sequence of the Maanshan NPP

  10. Mathematical models and illustrative results for the RINGBEARER II monopole/dipole beam-propagation code

    International Nuclear Information System (INIS)

    Chambers, F.W.; Masamitsu, J.A.; Lee, E.P.

    1982-01-01

    RINGBEARER II is a linearized monopole/dipole particle simulation code for studying intense relativistic electron beam propagation in gas. In this report the mathematical models utilized for beam particle dynamics and pinch field computation are delineated. Difficulties encountered in code operations and some remedies are discussed. Sample output is presented detailing the diagnostics and the methods of display and analysis utilized

  11. Recent results on polarizations and the present status of the Fermilab polarized beams

    International Nuclear Information System (INIS)

    Yokosawa, Akihiko.

    1986-01-01

    Experimental results are reviewed on polarization phenomena in nucleon-nucleon scattering at intermediate energies. The present status of S = 0 dibaryon resonances is presented. The status of the Fermilab polarized beam program is presented, including the construction of polarized beam, two polarimeters being installed in the experimental hall, and the experimental program

  12. Uncertainty analysis for results of thermal hydraulic codes of best-estimate-type

    International Nuclear Information System (INIS)

    Alva N, J.

    2010-01-01

    In this thesis, some fundamental knowledge is presented about uncertainty analysis and about diverse methodologies applied in the study of nuclear power plant transient event analysis, particularly related to thermal hydraulics phenomena. These concepts and methodologies mentioned in this work come from a wide bibliographical research in the nuclear power subject. Methodologies for uncertainty analysis have been developed by quite diverse institutions, and they have been widely used worldwide for application to results from best-estimate-type computer codes in nuclear reactor thermal hydraulics and safety analysis. Also, the main uncertainty sources, types of uncertainties, and aspects related to best estimate modeling and methods are introduced. Once the main bases of uncertainty analysis have been set, and some of the known methodologies have been introduced, it is presented in detail the CSAU methodology, which will be applied in the analyses. The main objective of this thesis is to compare the results of an uncertainty and sensibility analysis by using the Response Surface Technique to the application of W ilks formula, apply through a loss coolant experiment and an event of rise in a BWR. Both techniques are options in the part of uncertainty and sensibility analysis of the CSAU methodology, which was developed for the analysis of transients and accidents at nuclear power plants, and it is the base of most of the methodologies used in licensing of nuclear power plants practically everywhere. Finally, the results of applying both techniques are compared and discussed. (Author)

  13. Battelle integrity of nuclear piping program. Summary of results and implications for codes/standards

    International Nuclear Information System (INIS)

    Miura, Naoki

    2005-01-01

    The BINP(Battelle Integrity of Nuclear Piping) program was proposed by Battelle to elaborate pipe fracture evaluation methods and to improve LBB and in-service flaw evaluation criteria. The program has been conducted from October 1998 to September 2003. In Japan, CRIEPI participated in the program on behalf of electric utilities and fabricators to catch up the technical backgrounds for possible future revision of LBB and in-service flaw evaluation standards and to investigate the issues needed to be reflected to current domestic standards. A series of the results obtained from the program has been well utilized for the new LBB Regulatory Guide Program by USNRC and for proposal of revised in-service flaw evaluation criteria to the ASME Code Committee. The results were assessed whether they had implications for the existing or future domestic standards. As a result, the impact of many of these issues, which were concerned to be adversely affected to LBB approval or allowable flaw sizes in flaw evaluation criteria, was found to be relatively minor under actual plant conditions. At the same time, some issues that needed to be resolved to address advanced and rational standards in the future were specified. (author)

  14. ADREA-I: A transient three dimensional transport code for atmospheric and other applications - some preliminary results

    International Nuclear Information System (INIS)

    Bartzis, G.

    1985-02-01

    In this work a general description of the ADREA-I code is presented and some preliminary results are discussed. The ADREA-I is a transient three dimensional computer code aimed at transport analysis with particular emphasis on atmospheric dispersion under any realistic terrain conditions (complex or not) applicable to the planetary boundary layer in a distance extending up to a hundred kilometers or more. The complex geometry applications and the reasonable results obtained constitute a solid indication of the broad capability of the code. (author)

  15. Potential Job Creation in Nevada as a Result of Adopting New Residential Building Energy Codes

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Michael J.; Niemeyer, Jackie M.

    2013-09-01

    Are there advantages to states that adopt the most recent model building energy codes other than saving energy? For example, can the construction activity and energy savings associated with code-compliant housing units become significant sources of job creation for states if new building energy codes are adopted to cover residential construction? , The U.S. Department of Energy (DOE) Building Energy Codes Program (BECP) asked Pacific Northwest National Laboratory (PNNL) to research and ascertain whether jobs would be created in individual states based on their adoption of model building energy codes. Each state in the country is dealing with high levels of unemployment, so job creation has become a top priority. Many programs have been created to combat unemployment with various degrees of failure and success. At the same time, many states still have not yet adopted the most current versions of the International Energy Conservation Code (IECC) model building energy code, when doing so could be a very effective tool in creating jobs to assist states in recovering from this economic downturn.

  16. Potential Job Creation in Tennessee as a Result of Adopting New Residential Building Energy Codes

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Michael J.; Niemeyer, Jackie M.

    2013-09-01

    Are there advantages to states that adopt the most recent model building energy codes other than saving energy? For example, can the construction activity and energy savings associated with code-compliant housing units become significant sources of job creation for states if new building energy codes are adopted to cover residential construction? , The U.S. Department of Energy (DOE) Building Energy Codes Program (BECP) asked Pacific Northwest National Laboratory (PNNL) to research and ascertain whether jobs would be created in individual states based on their adoption of model building energy codes. Each state in the country is dealing with high levels of unemployment, so job creation has become a top priority. Many programs have been created to combat unemployment with various degrees of failure and success. At the same time, many states still have not yet adopted the most current versions of the International Energy Conservation Code (IECC) model building energy code, when doing so could be a very effective tool in creating jobs to assist states in recovering from this economic downturn.

  17. Potential Job Creation in Rhode Island as a Result of Adopting New Residential Building Energy Codes

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Michael J.; Niemeyer, Jackie M.

    2013-09-01

    Are there advantages to states that adopt the most recent model building energy codes other than saving energy? For example, can the construction activity and energy savings associated with code-compliant housing units become significant sources of job creation for states if new building energy codes are adopted to cover residential construction? , The U.S. Department of Energy (DOE) Building Energy Codes Program (BECP) asked Pacific Northwest National Laboratory (PNNL) to research and ascertain whether jobs would be created in individual states based on their adoption of model building energy codes. Each state in the country is dealing with high levels of unemployment, so job creation has become a top priority. Many programs have been created to combat unemployment with various degrees of failure and success. At the same time, many states still have not yet adopted the most current versions of the International Energy Conservation Code (IECC) model building energy code, when doing so could be a very effective tool in creating jobs to assist states in recovering from this economic downturn.

  18. Potential Job Creation in Minnesota as a Result of Adopting New Residential Building Energy Codes

    Energy Technology Data Exchange (ETDEWEB)

    Scott, Michael J.; Niemeyer, Jackie M.

    2013-09-01

    Are there advantages to states that adopt the most recent model building energy codes other than saving energy? For example, can the construction activity and energy savings associated with code-compliant housing units become significant sources of job creation for states if new building energy codes are adopted to cover residential construction? , The U.S. Department of Energy (DOE) Building Energy Codes Program (BECP) asked Pacific Northwest National Laboratory (PNNL) to research and ascertain whether jobs would be created in individual states based on their adoption of model building energy codes. Each state in the country is dealing with high levels of unemployment, so job creation has become a top priority. Many programs have been created to combat unemployment with various degrees of failure and success. At the same time, many states still have not yet adopted the most current versions of the International Energy Conservation Code (IECC) model building energy code, when doing so could be a very effective tool in creating jobs to assist states in recovering from this economic downturn.

  19. Code comparison results for the loft LP-FP-2 experiment

    International Nuclear Information System (INIS)

    Merilo, M.; Mecham, D.C.

    1991-01-01

    Computer code calculations are compared with thermal hydraulic and fission product release, transport, and deposition data obtained from the OECD-LOFT LP-FP-2 experiment. Except for the MAAP code, which is a fully integrated severe accident code, the thermalhydraulic and fission product behavior were calculated with different codes. Six organizations participated in the thermal hydraulic portion of the code comparison exercise. These calculations were performed with RELAP 5, SCDAP/RELAP 5, and MAAP. The comparisons show generally well developed capabilities to determine the thermal-hydraulic conditions during the early stages of a severe core damage accident. Four participants submitted detailed fission product behavior calculations. Except for MAAP, as stated previously, the fission product inventory, core damage, fission product release, transport and deposition were calculated independently with different codes. Much larger differences than observed for the thermalhydraulic comparison were evident. The fission product inventory calculations were generally in good agreement with each other. Large differences were observed for release fractions and amounts of deposition. Net release calculations from the primary system were generally accurate within a factor of two or three for the more important fission products

  20. Apar-T: code, validation, and physical interpretation of particle-in-cell results

    Science.gov (United States)

    Melzani, Mickaël; Winisdoerffer, Christophe; Walder, Rolf; Folini, Doris; Favre, Jean M.; Krastanov, Stefan; Messmer, Peter

    2013-10-01

    simulations. The other is that the level of electric field fluctuations scales as 1/ΛPIC ∝ p. We provide a corresponding exact expression, taking into account the finite superparticle size. We confirm both expectations with simulations. Fourth, we compare the Vlasov-Maxwell theory, often used for code benchmarking, to the PIC model. The former describes a phase-space fluid with Λ = + ∞ and no correlations, while the PIC plasma features a small Λ and a high level of correlations when compared to a real plasma. These differences have to be kept in mind when interpreting and validating PIC results against the Vlasov-Maxwell theory and when modeling real physical plasmas.

  1. Current Status of Experimental and Theoretical Work on Sodium/Fuel Interaction (SFI) at Karlsruhe 'Code Developments'

    International Nuclear Information System (INIS)

    Beutel, H.; Bojarsky, E.; Reiser, H.; Caldarola, L.; Jacobs, H.; Zyszkowski, W.

    1976-01-01

    presence of non condensable gases. For the heat transfer process an effective thermal conductivity of the liquid/vapour mixture accounts for partial vapour blanketing of the fuel particles. Numerical results are in general consistent with those obtainable from the first code. A survey of the various fragmentation mechanisms of UO 2 in sodium was done. It was concluded that 'vapour bubble and collapse' seems to be the most probable fragmentation mechanism in the case of UO 2 /sodium systems. For this reason work was focussed on modelling this mechanism. A preliminary model was given. Work is progressing. It is planned to couple the FCI theoretical model No. 1 developed at Karlsruhe to the american REXCO code which is available at Ispra. Work is being completed. The FCI subroutine is already available

  2. Coupling External Radiation Transport Code Results to the GADRAS Detector Response Function

    International Nuclear Information System (INIS)

    Mitchell, Dean J.; Thoreson, Gregory G.; Horne, Steven M.

    2014-01-01

    Simulating gamma spectra is useful for analyzing special nuclear materials. Gamma spectra are influenced not only by the source and the detector, but also by the external, and potentially complex, scattering environment. The scattering environment can make accurate representations of gamma spectra difficult to obtain. By coupling the Monte Carlo Nuclear Particle (MCNP) code with the Gamma Detector Response and Analysis Software (GADRAS) detector response function, gamma spectrum simulations can be computed with a high degree of fidelity even in the presence of a complex scattering environment. Traditionally, GADRAS represents the external scattering environment with empirically derived scattering parameters. By modeling the external scattering environment in MCNP and using the results as input for the GADRAS detector response function, gamma spectra can be obtained with a high degree of fidelity. This method was verified with experimental data obtained in an environment with a significant amount of scattering material. The experiment used both gamma-emitting sources and moderated and bare neutron-emitting sources. The sources were modeled using GADRAS and MCNP in the presence of the external scattering environment, producing accurate representations of the experimental data.

  3. Results and code prediction comparisons of lithium-air reaction and aerosol behavior tests

    International Nuclear Information System (INIS)

    Jeppson, D.W.

    1986-03-01

    The Hanford Engineering Development Laboratory (HEDL) Fusion Safety Support Studies include evaluation of potential safety and environmental concerns associated with the use of liquid lithium as a breeder and coolant for fusion reactors. Potential mechanisms for volatilization and transport of radioactive metallic species associated with breeder materials are of particular interest. Liquid lithium pool-air reaction and aerosol behavior tests were conducted with lithium masses up to 100 kg within the 850-m 3 containment vessel in the Containment Systems Test Facility. Lithium-air reaction rates, aerosol generation rates, aerosol behavior and characterization, as well as containment atmosphere temperature and pressure responses were determined. Pool-air reaction and aerosol behavior test results were compared with computer code calculations for reaction rates, containment atmosphere response, and aerosol behavior. The volatility of potentially radioactive metallic species from a lithium pool-air reaction was measured. The response of various aerosol detectors to the aerosol generated was determined. Liquid lithium spray tests in air and in nitrogen atmospheres were conducted with lithium temperatures of about 427 0 and 650 0 C. Lithium reaction rates, containment atmosphere response, and aerosol generation and characterization were determined for these spray tests

  4. Methodology of the Integrated Analysis of Company's Financial Status and Its Performance Results

    OpenAIRE

    Mackevičius, Jonas; Valkauskas, Romualdas

    2010-01-01

    Information about company's financial status and its performance results is very important for the objective evaluation of company's position in the market and competitive possibilities in the future. Such information is provided in the financial statement. It is important to apply and investigate this information properly. The methodology of company's financial status and performance results integrated analysis is recommended in this article. This methodology consists of these three elements...

  5. Offshore Code Comparison Collaboration within IEA Wind Task 23: Phase IV Results Regarding Floating Wind Turbine Modeling; Preprint

    Energy Technology Data Exchange (ETDEWEB)

    Jonkman, J.; Larsen, T.; Hansen, A.; Nygaard, T.; Maus, K.; Karimirad, M.; Gao, Z.; Moan, T.; Fylling, I.

    2010-04-01

    Offshore wind turbines are designed and analyzed using comprehensive simulation codes that account for the coupled dynamics of the wind inflow, aerodynamics, elasticity, and controls of the turbine, along with the incident waves, sea current, hydrodynamics, and foundation dynamics of the support structure. This paper describes the latest findings of the code-to-code verification activities of the Offshore Code Comparison Collaboration, which operates under Subtask 2 of the International Energy Agency Wind Task 23. In the latest phase of the project, participants used an assortment of codes to model the coupled dynamic response of a 5-MW wind turbine installed on a floating spar buoy in 320 m of water. Code predictions were compared from load-case simulations selected to test different model features. The comparisons have resulted in a greater understanding of offshore floating wind turbine dynamics and modeling techniques, and better knowledge of the validity of various approximations. The lessons learned from this exercise have improved the participants' codes, thus improving the standard of offshore wind turbine modeling.

  6. Offshore code comparison collaboration continuation within IEA Wind Task 30: Phase II results regarding a floating semisubmersible wind system

    DEFF Research Database (Denmark)

    Robertson, Amy; Jonkman, Jason M.; Vorpahl, Fabian

    2014-01-01

    Offshore wind turbines are designed and analyzed using comprehensive simulation tools (or codes) that account for the coupled dynamics of the wind inflow, aerodynamics, elasticity, and controls of the turbine, along with the incident waves, sea current, hydrodynamics, mooring dynamics, and founda......Offshore wind turbines are designed and analyzed using comprehensive simulation tools (or codes) that account for the coupled dynamics of the wind inflow, aerodynamics, elasticity, and controls of the turbine, along with the incident waves, sea current, hydrodynamics, mooring dynamics......, and foundation dynamics of the support structure. This paper describes the latest findings of the code-to-code verification activities of the Offshore Code Comparison Collaboration Continuation project, which operates under the International Energy Agency Wind Task 30. In the latest phase of the project......, participants used an assortment of simulation codes to model the coupled dynamic response of a 5-MW wind turbine installed on a floating semisubmersible in 200 m of water. Code predictions were compared from load case simulations selected to test different model features. The comparisons have resulted...

  7. Status report on multigroup cross section generation code development for high-fidelity deterministic neutronics simulation system

    International Nuclear Information System (INIS)

    Yang, W.S.; Lee, C.H.

    2008-01-01

    Under the fast reactor simulation program launched in April 2007, development of an advanced multigroup cross section generation code was initiated in July 2007, in conjunction with the development of the high-fidelity deterministic neutron transport code UNIC. The general objectives are to simplify the existing multi-step schemes and to improve the resolved and unresolved resonance treatments. Based on the review results of current methods and the fact that they have been applied successfully to fast critical experiment analyses and fast reactor designs for last three decades, the methodologies of the ETOE-2/MC 2 -2/SDX code system were selected as the starting set of methodologies for multigroup cross section generation for fast reactor analysis. As the first step for coupling with the UNIC code and use in a parallel computing environment, the MC 2 -2 code was updated by modernizing the memory structure and replacing old data management package subroutines and functions with FORTRAN 90 based routines. Various modifications were also made in the ETOE-2 and MC 2 -2 codes to process the ENDF/B-VII.0 data properly. Using the updated ETOE-2/MC 2 -2 code system, the ENDF/B-VII.0 data was successfully processed for major heavy and intermediate nuclides employed in sodium-cooled fast reactors. Initial verification tests of the MC 2 -2 libraries generated from ENDF/B-VII.0 data were performed by inter-comparison of twenty-one group infinite dilute total cross sections obtained from MC 2 -2, VIM, and NJOY. For almost all nuclides considered, MC 2 -2 cross sections agreed very well with those from VIM and NJOY. Preliminary validation tests of the ENDF/B-VII.0 libraries of MC 2 -2 were also performed using a set of sixteen fast critical benchmark problems. The deterministic results based on MC 2 -2/TWODANT calculations were in good agreement with MCNP solutions within ∼0.25% Δρ, except a few small LANL fast assemblies. Relative to the MCNP solution, the MC 2 -2/TWODANT

  8. Status report on multigroup cross section generation code development for high-fidelity deterministic neutronics simulation system.

    Energy Technology Data Exchange (ETDEWEB)

    Yang, W. S.; Lee, C. H. (Nuclear Engineering Division)

    2008-05-16

    Under the fast reactor simulation program launched in April 2007, development of an advanced multigroup cross section generation code was initiated in July 2007, in conjunction with the development of the high-fidelity deterministic neutron transport code UNIC. The general objectives are to simplify the existing multi-step schemes and to improve the resolved and unresolved resonance treatments. Based on the review results of current methods and the fact that they have been applied successfully to fast critical experiment analyses and fast reactor designs for last three decades, the methodologies of the ETOE-2/MC{sup 2}-2/SDX code system were selected as the starting set of methodologies for multigroup cross section generation for fast reactor analysis. As the first step for coupling with the UNIC code and use in a parallel computing environment, the MC{sup 2}-2 code was updated by modernizing the memory structure and replacing old data management package subroutines and functions with FORTRAN 90 based routines. Various modifications were also made in the ETOE-2 and MC{sup 2}-2 codes to process the ENDF/B-VII.0 data properly. Using the updated ETOE-2/MC{sup 2}-2 code system, the ENDF/B-VII.0 data was successfully processed for major heavy and intermediate nuclides employed in sodium-cooled fast reactors. Initial verification tests of the MC{sup 2}-2 libraries generated from ENDF/B-VII.0 data were performed by inter-comparison of twenty-one group infinite dilute total cross sections obtained from MC{sup 2}-2, VIM, and NJOY. For almost all nuclides considered, MC{sup 2}-2 cross sections agreed very well with those from VIM and NJOY. Preliminary validation tests of the ENDF/B-VII.0 libraries of MC{sup 2}-2 were also performed using a set of sixteen fast critical benchmark problems. The deterministic results based on MC{sup 2}-2/TWODANT calculations were in good agreement with MCNP solutions within {approx}0.25% {Delta}{rho}, except a few small LANL fast assemblies

  9. Current status of modeling fission gas behaviour in the Karlsruhe code LANGZEIT/KURZZEIT

    International Nuclear Information System (INIS)

    Vaeth, L.

    1980-12-01

    The programme LANGZEIT/KURZZEIT has been recently extended to describe intragranular bubble coalescence and volume equilibration, to model intergranular gas behaviour and transient release from closed porosity. The model is described and the results of some comparisons with transient experiments are discussed. Further necessary refinements of the model are outlined. (orig.) [de

  10. Status report on the 'Merging' of the Electron-Cloud Code POSINST with the 3-D Accelerator PIC CODE WARP

    Energy Technology Data Exchange (ETDEWEB)

    Vay, J.-L.; Furman, M.A.; Azevedo, A.W.; Cohen, R.H.; Friedman, A.; Grote, D.P.; Stoltz, P.H.

    2004-04-19

    We have integrated the electron-cloud code POSINST [1] with WARP [2]--a 3-D parallel Particle-In-Cell accelerator code developed for Heavy Ion Inertial Fusion--so that the two can interoperate. Both codes are run in the same process, communicate through a Python interpreter (already used in WARP), and share certain key arrays (so far, particle positions and velocities). Currently, POSINST provides primary and secondary sources of electrons, beam bunch kicks, a particle mover, and diagnostics. WARP provides the field solvers and diagnostics. Secondary emission routines are provided by the Tech-X package CMEE.

  11. Energy Consumption Model and Measurement Results for Network Coding-enabled IEEE 802.11 Meshed Wireless Networks

    DEFF Research Database (Denmark)

    Paramanathan, Achuthan; Rasmussen, Ulrik Wilken; Hundebøll, Martin

    2012-01-01

    This paper presents an energy model and energy measurements for network coding enabled wireless meshed networks based on IEEE 802.11 technology. The energy model and the energy measurement testbed is limited to a simple Alice and Bob scenario. For this toy scenario we compare the energy usages...... for a system with and without network coding support. While network coding reduces the number of radio transmissions, the operational activity on the devices due to coding will be increased. We derive an analytical model for the energy consumption and compare it to real measurements for which we build...... a flexible, low cost tool to be able to measure at any given node in a meshed network. We verify the precision of our tool by comparing it to a sophisticated device. Our main results in this paper are the derivation of an analytical energy model, the implementation of a distributed energy measurement testbed...

  12. Results of a survey on accident and safety analysis codes, benchmarks, verification and validation methods

    International Nuclear Information System (INIS)

    Lee, A.G.; Wilkin, G.B.

    1995-01-01

    This report is a compilation of the information submitted by AECL, CIAE, JAERI, ORNL and Siemens in response to a need identified at the 'Workshop on R and D Needs' at the IGORR-3 meeting. The survey compiled information on the national standards applied to the Safety Quality Assurance (SQA) programs undertaken by the participants. Information was assembled for the computer codes and nuclear data libraries used in accident and safety analyses for research reactors and the methods used to verify and validate the codes and libraries. Although the survey was not comprehensive, it provides a basis for exchanging information of common interest to the research reactor community

  13. Simulating Coupling Complexity in Space Plasmas: First Results from a new code

    Science.gov (United States)

    Kryukov, I.; Zank, G. P.; Pogorelov, N. V.; Raeder, J.; Ciardo, G.; Florinski, V. A.; Heerikhuisen, J.; Li, G.; Petrini, F.; Shematovich, V. I.; Winske, D.; Shaikh, D.; Webb, G. M.; Yee, H. M.

    2005-12-01

    The development of codes that embrace 'coupling complexity' via the self-consistent incorporation of multiple physical scales and multiple physical processes in models has been identified by the NRC Decadal Survey in Solar and Space Physics as a crucial necessary development in simulation/modeling technology for the coming decade. The National Science Foundation, through its Information Technology Research (ITR) Program, is supporting our efforts to develop a new class of computational code for plasmas and neutral gases that integrates multiple scales and multiple physical processes and descriptions. We are developing a highly modular, parallelized, scalable code that incorporates multiple scales by synthesizing 3 simulation technologies: 1) Computational fluid dynamics (hydrodynamics or magneto-hydrodynamics-MHD) for the large-scale plasma; 2) direct Monte Carlo simulation of atoms/neutral gas, and 3) transport code solvers to model highly energetic particle distributions. We are constructing the code so that a fourth simulation technology, hybrid simulations for microscale structures and particle distributions, can be incorporated in future work, but for the present, this aspect will be addressed at a test-particle level. This synthesis we will provide a computational tool that will advance our understanding of the physics of neutral and charged gases enormously. Besides making major advances in basic plasma physics and neutral gas problems, this project will address 3 Grand Challenge space physics problems that reflect our research interests: 1) To develop a temporal global heliospheric model which includes the interaction of solar and interstellar plasma with neutral populations (hydrogen, helium, etc., and dust), test-particle kinetic pickup ion acceleration at the termination shock, anomalous cosmic ray production, interaction with galactic cosmic rays, while incorporating the time variability of the solar wind and the solar cycle. 2) To develop a coronal

  14. Comparison of Analytical and Measured Performance Results on Network Coding in IEEE 802.11 Ad-Hoc Networks

    DEFF Research Database (Denmark)

    Zhao, Fang; Médard, Muriel; Hundebøll, Martin

    2012-01-01

    CATWOMAN that can run on standard WiFi hardware. We present an analytical model to evaluate the performance of COPE in simple networks, and our results show the excellent predictive quality of this model. By closely examining the performance in two simple topologies, we observe that the coding gain results...

  15. Validation of one-dimensional module of MARS 2.1 computer code by comparison with the RELAP5/MOD3.3 developmental assessment results

    International Nuclear Information System (INIS)

    Lee, Y. J.; Bae, S. W.; Chung, B. D.

    2003-02-01

    This report records the results of the code validation for the one-dimensional module of the MARS 2.1 thermal hydraulics analysis code by means of result-comparison with the RELAP5/MOD3.3 computer code. For the validation calculations, simulations of the RELAP5 code development assessment problem, which consists of 22 simulation problems in 3 categories, have been selected. The results of the 3 categories of simulations demonstrate that the one-dimensional module of the MARS 2.1 code and the RELAP5/MOD3.3 code are essentially the same code. This is expected as the two codes have basically the same set of field equations, constitutive equations and main thermal hydraulic models. The results suggests that the high level of code validity of the RELAP5/MOD3.3 can be directly applied to the MARS one-dimensional module

  16. Preliminary In-vivo Results For Spatially Coded Synthetic Transmit Aperture Ultrasound Based On Frequency Division

    DEFF Research Database (Denmark)

    Gran, Fredrik; Hansen, Kristoffer Lindskov; Jensen, Jørgen Arendt

    2006-01-01

    This paper investigates the possibility of using spatial coding based on frequency division for in-vivo synthetic transmit aperture (STA) ultrasound imaging. When using spatial encoding for STA, it is possible to use several transmitters simultaneously and separate the signals at the receiver....... This increases the maximum transmit power compared to conventional STA, where only one transmitter can be active. The signal-to-noise-ratio can therefore he increased and better penetration can be obtained. For frequency division, the coding is achieved by designing a number of transmit waveforms with disjoint...... spectral support, spanning the passband of the ultrasound transducer. The signals can therefore he separated at the receiver using matched filtering. The method is tested using a commercial linear array transducer with a center frequency of 9 MHz and 68% fractional bandwidth. In this paper, the transmit...

  17. Design of an Object-Oriented Turbomachinery Analysis Code: Initial Results

    Science.gov (United States)

    Jones, Scott M.

    2015-01-01

    Performance prediction of turbomachines is a significant part of aircraft propulsion design. In the conceptual design stage, there is an important need to quantify compressor and turbine aerodynamic performance and develop initial geometry parameters at the 2-D level prior to more extensive Computational Fluid Dynamics (CFD) analyses. The Object-oriented Turbomachinery Analysis Code (OTAC) is being developed to perform 2-D meridional flowthrough analysis of turbomachines using an implicit formulation of the governing equations to solve for the conditions at the exit of each blade row. OTAC is designed to perform meanline or streamline calculations; for streamline analyses simple radial equilibrium is used as a governing equation to solve for spanwise property variations. While the goal for OTAC is to allow simulation of physical effects and architectural features unavailable in other existing codes, it must first prove capable of performing calculations for conventional turbomachines. OTAC is being developed using the interpreted language features available in the Numerical Propulsion System Simulation (NPSS) code described by Claus et al (1991). Using the NPSS framework came with several distinct advantages, including access to the pre-existing NPSS thermodynamic property packages and the NPSS Newton-Raphson solver. The remaining objects necessary for OTAC were written in the NPSS framework interpreted language. These new objects form the core of OTAC and are the BladeRow, BladeSegment, TransitionSection, Expander, Reducer, and OTACstart Elements. The BladeRow and BladeSegment consumed the initial bulk of the development effort and required determining the equations applicable to flow through turbomachinery blade rows given specific assumptions about the nature of that flow. Once these objects were completed, OTAC was tested and found to agree with existing solutions from other codes; these tests included various meanline and streamline comparisons of axial

  18. Comparison of computer code calculations with experimental results obtained in the NSPP series of experiments

    International Nuclear Information System (INIS)

    Tobias, M.L.

    1987-01-01

    Experiments were done on several aerosols in air atmospheres at varying temperatures and humidity conditions of interest in forming a data base for testing aerosol behavior models used as part of the process of evaluating the ''source term'' in light water reactor accidents. This paper deals with the problems of predicting the observed experimental data for suspended aerosol concentration with aerosol calculational codes. Comparisons of measured versus predicted data are provided

  19. Chiefly Symmetric: Results on the Scalability of Probabilistic Model Checking for Operating-System Code

    Directory of Open Access Journals (Sweden)

    Marcus Völp

    2012-11-01

    Full Text Available Reliability in terms of functional properties from the safety-liveness spectrum is an indispensable requirement of low-level operating-system (OS code. However, with evermore complex and thus less predictable hardware, quantitative and probabilistic guarantees become more and more important. Probabilistic model checking is one technique to automatically obtain these guarantees. First experiences with the automated quantitative analysis of low-level operating-system code confirm the expectation that the naive probabilistic model checking approach rapidly reaches its limits when increasing the numbers of processes. This paper reports on our work-in-progress to tackle the state explosion problem for low-level OS-code caused by the exponential blow-up of the model size when the number of processes grows. We studied the symmetry reduction approach and carried out our experiments with a simple test-and-test-and-set lock case study as a representative example for a wide range of protocols with natural inter-process dependencies and long-run properties. We quickly see a state-space explosion for scenarios where inter-process dependencies are insignificant. However, once inter-process dependencies dominate the picture models with hundred and more processes can be constructed and analysed.

  20. The OECD/NEA/NSC PBMR400 MW coupled neutronics thermal hydraulics transient benchmark - Steady-state results and status

    International Nuclear Information System (INIS)

    Reitsma, F.; Han, J.; Ivanov, K.; Sartori, E.

    2008-01-01

    The PBMR is a High-Temperature Gas-cooled Reactor (HTGR) concept developed to be built in South Africa. The analysis tools used for core neutronic design and core safety analysis need to be verified and validated. Since only a few pebble-bed HTR experimental facilities or plant data are available the use of code-to-code comparisons are an essential part of the V and V plans. As part of this plan the PBMR 400 MW design and a representative set of transient cases is defined as an OECD benchmark. The scope of the benchmark is to establish a series of well-defined multi-dimensional computational benchmark problems with a common given set of cross-sections, to compare methods and tools in coupled neutronics and thermal hydraulics analysis with a specific focus on transient events. The OECD benchmark includes steady-state and transients cases. Although the focus of the benchmark is on the modelling of the transient behaviour of the PBMR core, it was also necessary to define some steady-state cases to ensure consistency between the different approaches before results of transient cases could be compared. This paper describes the status of the benchmark project and shows the results for the three steady state exercises defined as a standalone neutronics calculation, a standalone thermal-hydraulic core calculation, and a coupled neutronics/thermal-hydraulic simulation. (authors)

  1. Rod behaviour under base load, load follow and frequency control operation: CYRANO 2 code predictions versus experimental results

    International Nuclear Information System (INIS)

    Gautier, B.; Raybaud, A.

    1984-01-01

    The French PWR reactors are now currently operating under load follow and frequency control. In order to demonstrate that these operating conditions were not able to increase the fuel failure rate, fuel rod behaviour calculations have been performed by E.D.F. with CYRANO 2 code. In parallel with these theoretical calculations, code predictions have been compared to experimental results. The paper presents some of the comparisons performed on 17x17 fuel irradiated in FESSENHEIM 2 up to 30 GWd/tU under base load operation and in the CAP reactor under load follow and frequency control conditions. It is shown that experimental results can be predicted with a reasonable accuracy by CYRANO 2 code. The experimental work was carried out under joint R and D programs by EDF, FRAGEMA, CEA, and WESTINGHOUSE (CAP program by French partners only). (author)

  2. Gamma spectroscopy modelization intercomparison of the modelization results using two different codes (MCNP, and Pascalys-mercure)

    International Nuclear Information System (INIS)

    Luneville, L.; Chiron, M.; Toubon, H.; Dogny, S.; Huver, M.; Berger, L.

    2001-01-01

    The research performed in common these last 3 years by the French Atomic Commission CEA, COGEMA and Eurisys Mesures had for main subject the realization of a complete tool of modelization for the largest range of realistic cases, the Pascalys modelization software. The main purpose of the modelization was to calculate the global measurement efficiency, which delivers the most accurate relationship between the photons emitted by the nuclear source in volume, punctual or deposited form and the germanium hyper pure detector, which detects and analyzes the received photons. It has been stated since long time that experimental global measurement efficiency becomes more and more difficult to address especially for complex scene as we can find in decommissioning and dismantling or in case of high activities for which the use of high activity reference sources become difficult to use for both health physics point of view and regulations. The choice of a calculation code is fundamental if accurate modelization is searched. MCNP represents the reference code but its use is long time calculation consuming and then not practicable in line on the field. Direct line-of-sight point kernel code as the French Atomic Commission 3-D analysis Mercure code can represent the practicable compromise between the most accurate MCNP reference code and the realistic performances needed in modelization. The comparison between the results of Pascalys-Mercure and MCNP code taking in account the last improvements of Mercure in the low energy range where the most important errors can occur, is presented in this paper, Mercure code being supported in line by the recent Pascalys 3-D modelization scene software. The incidence of the intrinsic efficiency of the Germanium detector is also approached for the total efficiency of measurement. (authors)

  3. Upregulation of long non-coding RNA TUG1 correlates with poor prognosis and disease status in osteosarcoma.

    Science.gov (United States)

    Ma, Bing; Li, Meng; Zhang, Lei; Huang, Ming; Lei, Jun-Bin; Fu, Gui-Hong; Liu, Chun-Xin; Lai, Qi-Wen; Chen, Qing-Quan; Wang, Yi-Lian

    2016-04-01

    The pathogenesis of osteosarcoma involves complex genetic and epigenetic factors. This study was to explore the impact and clinical relevance of long non-coding RNA (lncRNA), Taurine up-regulated gene 1 (TUG1) on patients with osteosarcoma. Seventy-six osteosarcoma tissues and matched adjacent normal tissues were included for analysis. The plasma samples were obtained from 29 patients with osteosarcoma at pre-operation and post-operation, 42 at newly diagnosed, 18 who experienced disease progression or relapse, 45 post-treatment, 36 patients with benign bone tumor, and 20 healthy donors. Quantitative real-time reverse transcript polymerase chain reactions were used to assess the correlation of the expression levels of TUG1 with clinical parameters of osteosarcoma patients. TUG1 was significantly overexpressed in the osteosarcoma tissues compared with matched adjacent normal tissues (P TUG1 strongly correlated with poor prognosis and was an independent prognostic indicator for overall survival (HR = 2.78, 95% CI = 1.29-6.00, P = 0.009) and progression-free survival (HR = 1.81, 95% CI = 1.01-3.54, P = 0.037). Our constructed nomogram containing TUG1 had more predictive accuracy than that without TUG1 (c-index 0.807 versus 0.776, respectively). In addition, for plasma samples, TUG1 expression levels were obviously decreased in post-operative patients (mean ΔCT -4.98 ± 0.22) compared with pre-operation patients (mean ΔCT -6.09 ± 0.74), and the changes of TUG1 expression levels were significantly associated with disease status. Receiver operating characteristic (ROC) curve analysis demonstrated that TUG1 could distinguish patients with osteosarcoma from healthy individuals compared with alkaline phosphatase (ALP) (the area under curve 0.849 versus 0.544). TUG1 was overexpressed in patients with osteosarcoma and strongly correlated with disease status. In addition, TUG1 may serve as a molecular indicator in maintaining surveillance

  4. Does health promotion need a Code of Ethics? Results from an IUHPE mixed method survey.

    Science.gov (United States)

    Bull, Torill; Riggs, Elisha; Nchogu, Sussy N

    2012-09-01

    Health promotion is an ethically challenging field involving constant reflection of values across multiple cultures of what is regarded as good and bad health promotion practice. While many disciplines are guided by a Code of Ethics (CoE) no such guide is available to health promoters. The International Union for Health Promotion and Education (IUHPE) has been nominated as a suitable candidate for developing such a code. It is within this context that the IUHPE Student and Early Career Network (ISECN), through its Ethics Working Group, has taken up the challenge of preparing the foundations for a CoE for health promotion. An online survey comprising open and closed-answer questions was used to gather the opinions of IUHPE members regarding the need for a CoE for health promotion. The quantitative data were calculated with descriptive analyses. A thematic analysis approach was used to analyze and interpret the qualitative data. IUHPE members (n = 236) from all global regions responded to the survey. The majority (52%) of the respondents had 11 years' experience or more in the field of health promotion. Ethical dilemmas were commonly encountered. The need for a CoE for health promotion was expressed by 83% of respondents. Respondents also offered their views of possibilities, ideas and challenges regarding the development of a CoE for health promotion. Considering that health promoters encounter ethical dilemmas frequently in their practice, this study reinforces the need to develop a CoE for the field. The recommendations from the survey provide a good basis for future work to develop such a code.

  5. Increasing asthma mortality in Denmark 1969-88 not a result of a changed coding practice

    DEFF Research Database (Denmark)

    Juel, K; Pedersen, P A

    1992-01-01

    We have studied asthma mortality in Denmark from 1969 to 1988. Age standardized mortality rates calculated in three age groups, 10-34, 35-59, and greater than or equal to 60 years, disclosed similar trends. Increasing mortality from asthma in the mid-1970s to 1988 was seen in all three age groups...... with higher mortality in 1979-88 as compared with 1969-78 of 95%, 55%, and 69%, respectively. Since the eighth revision of the International Classification of Diseases (ICD8) was used in Denmark over the entire 20-year period, changes in coding practice due to change of classification system cannot explain...

  6. Calculation of conversion coefficients Hp(3)/K air using the PENELOPE Monte Carlo code and comparison with MCNP calculation results

    International Nuclear Information System (INIS)

    Daures, J.; Gouriou, J.; Bordy, J.M.

    2010-01-01

    The authors report calculations performed using the MNCP and PENELOPE codes to determine the Hp(3)/K air conversion coefficient which allows the Hp(3) dose equivalent to be determined from the measured value of the kerma in the air. They report the definition of the phantom, a 20 cm diameter and 20 cm high cylinder which is considered as representative of a head. Calculations are performed for an energy range corresponding to interventional radiology or cardiology (20 keV-110 keV). Results obtained with both codes are compared

  7. Transduplication resulted in the incorporation of two protein-coding sequences into the Turmoil-1 transposable element of C. elegans

    Directory of Open Access Journals (Sweden)

    Pupko Tal

    2008-10-01

    Full Text Available Abstract Transposable elements may acquire unrelated gene fragments into their sequences in a process called transduplication. Transduplication of protein-coding genes is common in plants, but is unknown of in animals. Here, we report that the Turmoil-1 transposable element in C. elegans has incorporated two protein-coding sequences into its inverted terminal repeat (ITR sequences. The ITRs of Turmoil-1 contain a conserved RNA recognition motif (RRM that originated from the rsp-2 gene and a fragment from the protein-coding region of the cpg-3 gene. We further report that an open reading frame specific to C. elegans may have been created as a result of a Turmoil-1 insertion. Mutations at the 5' splice site of this open reading frame may have reactivated the transduplicated RRM motif. Reviewers This article was reviewed by Dan Graur and William Martin. For the full reviews, please go to the Reviewers' Reports section.

  8. RSAP - A Code for Display of Neutron Cross Section Data and SAMMY Fit Results

    International Nuclear Information System (INIS)

    Sayer, R.O.

    2001-01-01

    RSAP is a computer code for display of neutron cross section data and selected SAMMY output. SAMMY is a multilevel R-matrix code for fitting neutron time-of-flight cross-section data using Bayes' method. RSAP, which runs on the Digital Unix Alpha platform, reads ORELA Data Files (ODF) created by SAMMY and uses graphics routines from the PLPLOT package. In addition, RSAP can read data and/or computed values from ASCII files with a format specified by the user. Plot output may be displayed in an X window, sent to a postscript file (rsap.ps), or sent to a color postscript file (rsap.psc). Thirteen plot types are supported, allowing the user to display cross section data, transmission data, errors, theory, Bayes fits, and residuals in various combinations. In this document the designations theory and Bayes refer to the initial and final theoretical cross sections, respectively, as evaluated by SAMMY. Special plot types include Bayes/Data, Theory--Data, and Bayes--Data. Output from two SAMMY runs may be compared by plotting the ratios Theory2/Theory1 and Bayes2/Bayes1 or by plotting the differences (Theory2-Theory1) and (Bayes2-Bayes1)

  9. Status of reactor physics activities on cross section generation and functionalization for the prismatic very high temperature reactor, and development of spatially-heterogeneous codes

    International Nuclear Information System (INIS)

    Lee, C. H.; Zhong, Z.; Taiwo, T. A.; Yang, W. S.; Smith, M. A.; Palmiotti, G.

    2006-01-01

    The cross section generation methodology and procedure for design and analysis of the prismatic Very High Temperature Gas-cooled Reactor (VHTR) core have been addressed for the DRAGON and REBUS-3/DIF3D code suite. Approaches for tabulation and functionalization of cross sections have been investigated and implemented. The cross sections are provided at different burnup and fuel and moderator temperature states. In the tabulation approach, the multigroup cross sections are tabulated as a function of the state variables so that a cross section file is able to cover the range of core operating conditions. Cross sections for points between tabulated data points are fitted simply by linear interpolation. For the functionalization approach, an investigation of the applicability of quadratic polynomials and linear coupling for fuel and moderator temperature changes has been conducted, based on the observation that cross sections are monotonically changing with fuel or moderator temperatures. Preliminary results show that the functionalization makes it possible to cover a wide range of operating temperature conditions with only six sets of data per burnup, while maintaining a good accuracy and significantly reducing the size of the cross section file. In these approaches, the number of fission products has been minimized to a few nuclides (I/Xe/Pm/Sm and a lumped fission product) to reduce the overall computation time without sacrificing solution accuracy. Discontinuity factors (DFs) based on nodal equivalence theory have been introduced to accurately represent the significant change in neutron spectrum at the interface of the fuel and reflector regions as well as between different fuel blocks (e.g., fuel elements with burnable poisons or control rods). Using the DRAGON code, procedures have been established for generating cross sections for fuel and reflector blocks with and without control absorbers. The preliminary results indicate that the solution accuracy is improved

  10. Bridge Programs in Illinois: Results of the 2010 Illinois Bridge Status Survey

    Science.gov (United States)

    Taylor, J. L.; Harmon, T.

    2010-01-01

    This report provides a summary of major results of the Illinois Bridge Status Survey, administered online between April and June 2010. The purpose of the survey was to understand the extent to which bridge programs are being implemented in Illinois, as well as to build an online directory of bridge programs. Bridge programs are an emerging…

  11. Review of solution approach, methods, and recent results of the TRAC-PF1 system code

    International Nuclear Information System (INIS)

    Mahaffy, J.H.; Liles, D.R.; Knight, T.D.

    1983-01-01

    The current version of the Transient Reactor Analysis Code (TRAC-PF1) was created to improve on the capabilities of its predecessor (TRAC-PD2) for analyzing slow reactor transients such as small-break loss-of-coolant accidents. TRAC-PF1 continues to use a semi-implicit finite-difference method for modeling three-dimensional flows in the reactor vessel. However, it contains a new stability-enhancing two-step (SETS) finite-difference tecnique for one-dimensional flow calculations. This method is not restricted by a material Courant stability condition, allowing much larger time-step sizes during slow transients than would a semi-implicit method. These have been successfully applied to the analysis of a variety of experiments and hypothetical plant transients covering a full range of two-phase flow regimes

  12. Benchmarking Reactor Systems Studies by Comparison of EU and Japanese System Code Results for Different DEMO Concepts

    Energy Technology Data Exchange (ETDEWEB)

    Kemp, R.; Ward, D.J., E-mail: richard.kemp@ccfe.ac.uk [EURATOM/CCFE Association, Culham Centre for Fusion Energy, Abingdon (United Kingdom); Nakamura, M.; Tobita, K. [Japan Atomic Energy Agency, Rokkasho (Japan); Federici, G. [EFDA Garching, Max Plank Institut fur Plasmaphysik, Garching (Germany)

    2012-09-15

    Full text: Recent systems studies work within the Broader Approach framework has focussed on benchmarking the EU systems code PROCESS against the Japanese code TPC for conceptual DEMO designs. This paper describes benchmarking work for a conservative, pulsed DEMO and an advanced, steady-state, high-bootstrap fraction DEMO. The resulting former machine is an R{sub 0} = 10 m, a = 2.5 m, {beta}{sub N} < 2.0 device with no enhancement in energy confinement over IPB98. The latter machine is smaller (R{sub 0} = 8 m, a = 2.7 m), with {beta}{sub N} = 3.0, enhanced confinement, and high bootstrap fraction f{sub BS} = 0.8. These options were chosen to test the codes across a wide range of parameter space. While generally in good agreement, some of the code outputs differ. In particular, differences have been identified in the impurity radiation models and flux swing calculations. The global effects of these differences are described and approaches to identifying the best models, including future experiments, are discussed. Results of varying some of the assumptions underlying the modelling are also presented, demonstrating the sensitivity of the solutions to technological limitations and providing guidance for where further research could be focussed. (author)

  13. Inflammaging and Frailty Status Do Not Result in an Increased Extracellular Vesicle Concentration in Circulation

    Directory of Open Access Journals (Sweden)

    Ainhoa Alberro

    2016-07-01

    Full Text Available In the last decades extracellular vesicles (EVs have emerged as key players for intercellular communication. In the case of inflammation, several studies have reported that EV levels are increased in circulation during inflammatory episodes. Based on this, we investigated whether aging results in elevated EV number, as a basal proinflammatory status termed “inflammaging” has been described in aged individuals. Moreover, we also hypothesized that frailty and dependence conditions of the elderly could affect EV concentration in plasma. Results showed that inflammaging, frailty or dependence status do not result in EV increase, at least in the total number of EVs in circulation. These results open a new perspective for investigating the role of EVs in human aging and in the inflammaging process.

  14. Inflammaging and Frailty Status Do Not Result in an Increased Extracellular Vesicle Concentration in Circulation.

    Science.gov (United States)

    Alberro, Ainhoa; Sáenz-Cuesta, Matías; Muñoz-Culla, Maider; Mateo-Abad, Maider; Gonzalez, Esperanza; Carrasco-Garcia, Estefania; Araúzo-Bravo, Marcos J; Matheu, Ander; Vergara, Itziar; Otaegui, David

    2016-07-20

    In the last decades extracellular vesicles (EVs) have emerged as key players for intercellular communication. In the case of inflammation, several studies have reported that EV levels are increased in circulation during inflammatory episodes. Based on this, we investigated whether aging results in elevated EV number, as a basal proinflammatory status termed "inflammaging" has been described in aged individuals. Moreover, we also hypothesized that frailty and dependence conditions of the elderly could affect EV concentration in plasma. Results showed that inflammaging, frailty or dependence status do not result in EV increase, at least in the total number of EVs in circulation. These results open a new perspective for investigating the role of EVs in human aging and in the inflammaging process.

  15. Impact of marital status on survival of gastric adenocarcinoma patients: Results from the Surveillance Epidemiology and End Results (SEER) Database.

    Science.gov (United States)

    Qiu, Miaozhen; Yang, Dajun; Xu, Ruihua

    2016-02-15

    Marital status was found to be an independent prognostic factor for survival in various cancer types. In this study, we used the Surveillance, Epidemiology and End Results database to analyze the survival difference among different marital status in the United States. Gastric adenocarcinoma patients from 2004-2012 were enrolled for study. The 5-year cause specific survival (CSS) was our primary endpoint. Totally 29,074 eligible patients were identified. We found that more male patients were married than female. Asian patients had the highest percentages of married than the other races. More married patients were covered by the insurance. Married patients had better 5-year CSS than unmarried, 30.6% vs 25.7%, P married and unmarried patients, hazard ratio: 1.09 (95% confidence interval: 1.01-1.17), P = 0.027. The survival difference was significant in the insured but not in the uninsured patients. Widowed patients had the worst prognosis compared with other groups even though they had more stage I disease and more well / moderate differentiated tumors. These results indicated that unmarried gastric adenocarcinoma patients were at greater risk of cancer specific mortality. We recommend every patient should have access to best available gastric cancer therapy.

  16. Socioeconomic Status and Stroke Prevalence in Morocco: Results from the Rabat-Casablanca Study

    Science.gov (United States)

    Engels, Thomas; Baglione, Quentin; Audibert, Martine; Viallefont, Anne; Mourji, Fouzi; El Alaoui Faris, Mustapha

    2014-01-01

    Background Stroke is a growing public health concern in low- and middle- income countries. Improved knowledge about the association between socioeconomic status and stroke in these countries would enable the development of effective stroke prevention and management strategies. This study presents the association between socioeconomic status and the prevalence of stroke in Morocco, a lower middle-income country. Methods Data on the prevalence of stroke and stroke-related risk factors were collected during a large population-based survey. The diagnosis of stroke in surviving patients was confirmed by neurologists while health, demographic, and socioeconomic characteristics of households were collected using structured questionnaires. We used Multiple Correspondence Analysis to develop a wealth index based on characteristics of the household dwelling as well as ownership of selected assets. We used logistic regressions controlling for multiple variables to assess the statistical association between socioeconomic status and stroke. Findings Our results showed a significant association between household socioeconomic status and the prevalence of stroke. This relationship was non-linear, with individuals from both the poorest (mainly rural) and richest (mainly urban) households having a lower prevalence of stroke as compared to individuals with medium wealth level. The latter belonged mainly to urban households with a lower socioeconomic status. When taking into account the urban population only, we observed that a third of poorest households experienced a significantly higher prevalence of stroke compared to the richest third (OR = 2.06; CI 95%: 1.09; 3.89). Conclusion We conclude that individuals from the most deprived urban households bear a higher risk of stroke than the rest of the population in Morocco. This result can be explained to a certain extent by the higher presence of behavioral risk factors in this specific category of the population, which leads in

  17. Socioeconomic status and stroke prevalence in Morocco: results from the Rabat-Casablanca study.

    Directory of Open Access Journals (Sweden)

    Thomas Engels

    Full Text Available BACKGROUND: Stroke is a growing public health concern in low- and middle- income countries. Improved knowledge about the association between socioeconomic status and stroke in these countries would enable the development of effective stroke prevention and management strategies. This study presents the association between socioeconomic status and the prevalence of stroke in Morocco, a lower middle-income country. METHODS: Data on the prevalence of stroke and stroke-related risk factors were collected during a large population-based survey. The diagnosis of stroke in surviving patients was confirmed by neurologists while health, demographic, and socioeconomic characteristics of households were collected using structured questionnaires. We used Multiple Correspondence Analysis to develop a wealth index based on characteristics of the household dwelling as well as ownership of selected assets. We used logistic regressions controlling for multiple variables to assess the statistical association between socioeconomic status and stroke. FINDINGS: Our results showed a significant association between household socioeconomic status and the prevalence of stroke. This relationship was non-linear, with individuals from both the poorest (mainly rural and richest (mainly urban households having a lower prevalence of stroke as compared to individuals with medium wealth level. The latter belonged mainly to urban households with a lower socioeconomic status. When taking into account the urban population only, we observed that a third of poorest households experienced a significantly higher prevalence of stroke compared to the richest third (OR = 2.06; CI 95%: 1.09; 3.89. CONCLUSION: We conclude that individuals from the most deprived urban households bear a higher risk of stroke than the rest of the population in Morocco. This result can be explained to a certain extent by the higher presence of behavioral risk factors in this specific category of the population

  18. First results of saturation curve measurements of heat-resistant steel using GEANT4 and MCNP5 codes

    International Nuclear Information System (INIS)

    Hoang, Duc-Tam; Tran, Thien-Thanh; Le, Bao-Tran; Vo, Hoang-Nguyen; Chau, Van-Tao; Tran, Kim-Tuyet; Huynh, Dinh-Chuong

    2015-01-01

    A gamma backscattering technique is applied to calculate the saturation curve and the effective mass attenuation coefficient of material. A NaI(Tl) detector collimated by collimator of large diameter is modeled by Monte Carlo technique using both MCNP5 and GEANT4 codes. The result shows a good agreement in response function of the scattering spectra for the two codes. Based on such spectra, the saturation curve of heat-resistant steel is determined. The results represent a strong confirmation that it is appropriate to use the detector collimator of large diameter to obtain the scattering spectra and this work is also the basis of experimental set-up for determining the thickness of material. (author)

  19. FURTHER IMPROVEMENT OF THE INVESTMENT CLIMATE IN RUSSIA AS A RESULT OF MODERNIZATION OF THE RUSSIAN CIVIL CODE

    Directory of Open Access Journals (Sweden)

    V. Musin

    2014-01-01

    Full Text Available This article traces the history, and discusses some of the recent changes in the Russian Federation Civil Code, which result in a more favorable business climate inRussia. In particular, it discusses the development of changes related to the documentation of contracts, expansion in the durations and uses of powers of attorney, and the modernization of the statute of limitations period for bringing an action.">Russia >

  20. Analysis of results of AZTRAN and AZKIND codes for a BWR; Analisis de resultados de los codigos AZTRAN y AZKIND para un BWR

    Energy Technology Data Exchange (ETDEWEB)

    Bastida O, G. E.; Vallejo Q, J. A.; Galicia A, J.; Francois L, J. L. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Paseo Cuauhnahuac 8532, 62550 Jiutepec, Morelos (Mexico); Xolocostli M, J. V.; Rodriguez H, A.; Gomez T, A. M., E-mail: gbo729@yahoo.com.mx [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    This paper presents an analysis of results obtained from simulations performed with the neutron transport code AZTRAN and the kinetic code of neutron diffusion AZKIND, based on comparisons with models corresponding to a typical BWR, in order to verify the behavior and reliability of the values obtained with said code for its current development. For this, simulations of different geometries were made using validated nuclear codes, such as CASMO, MCNP5 and Serpent. The results obtained are considered adequate since they are comparable with those obtained and reported with other codes, based mainly on the neutron multiplication factor and the power distribution of the same. (Author)

  1. Comparison of Crack Growth Test Results at Elevated Temperature and Design Code Material Properties for Grade 91 Steel

    Energy Technology Data Exchange (ETDEWEB)

    Lee, Hyeong-Yeon; Kim, Woo-Gon; Kim, Nak-Hyun [Korea Atomic Energy Reserach Institute, Daejeon (Korea, Republic of)

    2015-01-15

    The material properties of crack growth models at an elevated temperature were derived from the results of numerous crack growth tests for Mod.9Cr-1Mo (ASME Grade 91) steel specimens under fatigue loading and creep loading at an elevated temperature. These crack growth models were needed for defect assessment under creep-fatigue loading. The mathematical crack growth rate models for fatigue crack growth (FCG) and creep crack growth (CCG) were determined based on the test results, and the models were compared with those of the French design code RCCMRx to investigate the conservatism of the code. The French design code RCC-MRx provides an FCG model and a CCG model for Grade 91 steel in Section III Tome 6. It was shown that the FCG model of RCC-MRx is conservative, while the CCG model is non-conservative compared with the present test data. Thus, it was shown that further validation of the property was required. Mechanical strength tests and creep tests were also conducted, and the test results were compared with those of RCC-MRx.

  2. Comparison of the results of several heat transfer computer codes when applied to a hypothetical nuclear waste repository

    International Nuclear Information System (INIS)

    Claiborne, H.C.; Wagner, R.S.; Just, R.A.

    1979-12-01

    A direct comparison of transient thermal calculations was made with the heat transfer codes HEATING5, THAC-SIP-3D, ADINAT, SINDA, TRUMP, and TRANCO for a hypothetical nuclear waste repository. With the exception of TRUMP and SINDA (actually closer to the earlier CINDA3G version), the other codes agreed to within +-5% for the temperature rises as a function of time. The TRUMP results agreed within +-5% up to about 50 years, where the maximum temperature occurs, and then began an oscillary behavior with up to 25% deviations at longer times. This could have resulted from time steps that were too large or from some unknown system problems. The available version of the SINDA code was not compatible with the IBM compiler without using an alternative method for handling a variable thermal conductivity. The results were about 40% low, but a reasonable agreement was obtained by assuming a uniform thermal conductivity; however, a programming error was later discovered in the alternative method. Some work is required on the IBM version to make it compatible with the system and still use the recommended method of handling variable thermal conductivity. TRANCO can only be run as a 2-D model, and TRUMP and CINDA apparently required longer running times and did not agree in the 2-D case; therefore, only HEATING5, THAC-SIP-3D, and ADINAT were used for the 3-D model calculations. The codes agreed within +-5%; at distances of about 1 ft from the waste canister edge, temperature rises were also close to that predicted by the 3-D model

  3. Validation and verification of MCNP6 against intermediate and high-energy experimental data and results by other codes

    International Nuclear Information System (INIS)

    Mashnik, Stepan G.

    2011-01-01

    MCNP6, the latest and most advanced LANL transport code representing a recent merger of MCNP5 and MCNPX, has been Validated and Verified (V and V) against a variety of intermediate and high-energy experimental data and against results by different versions of MCNPX and other codes. In the present work, we V and V MCNP6 using mainly the latest modifications of the Cascade-Exciton Model (CEM) and of the Los Alamos version of the Quark-Gluon String Model (LAQGSM) event generators CEM03.02 and LAQGSM03.03. We found that MCNP6 describes reasonably well various reactions induced by particles and nuclei at incident energies from 18 MeV to about 1 TeV per nucleon measured on thin and thick targets and agrees very well with similar results obtained with MCNPX and calculations by CEM03.02, LAQGSM03.01 (03.03), INCL4 + ABLA, and Bertini INC + Dresner evaporation, EPAX, ABRABLA, HIPSE, and AMD, used as stand alone codes. Most of several computational bugs and more serious physics problems observed in MCNP6/X during our V and V have been fixed; we continue our work to solve all the known problems before MCNP6 is distributed to the public. (author)

  4. Benchmarking the cad-based attila discrete ordinates code with experimental data of fusion experiments and to the results of MCNP code in simulating ITER

    International Nuclear Information System (INIS)

    Youssef, M. Z.

    2007-01-01

    Attila is a newly developed finite element code based on Sn neutron, gamma, and charged particle transport in 3-D geometry in which unstructured tetrahedral meshes are generated to describe complex geometry that is based on CAD input (Solid Works, Pro/Engineer, etc). In the present work we benchmark its calculation accuracy by comparing its prediction to the measured data inside two experimental mock-ups bombarded with 14 MeV neutrons. The results are also compared to those based on MCNP calculations. The experimental mock-ups simulate parts of the International Thermonuclear Experimental Reactor (ITER) in-vessel components, namely: (1) the Tungsten mockup configuration (54.3 cm x 46.8 cm x 45 cm), and (2) the ITER shielding blanket followed by the SCM region (simulated by alternating layers of SS316 and copper). In the latter configuration, a high aspect ratio rectangular streaming channel was introduced (to simulate steaming paths between ITER blanket modules) which ends with a rectangular cavity. The experiments on these two fusion-oriented integral experiments were performed at the Fusion Neutron Generator (FNG) facility, Frascati, Italy. In addition, the nuclear performance of the ITER MCNP 'Benchmark' CAD model has been performed with Attila to compare its results to those obtained with CAD-based MCNP approach developed by several ITER participants. The objective of this paper is to compare results based on two distinctive 3-D calculation tools using the same nuclear data, FENDL2.1, and the same response functions of several reaction rates measured in ITER mock-ups and to enhance confidence from the international neutronics community in the Attila code and how it can precisely quantify the nuclear field in large and complex systems, such as ITER. Attila has the advantage of providing a full flux mapping visualization everywhere in one run where components subjected to excessive radiation level and strong streaming paths can be identified. In addition, the

  5. The effect of functional status of the ovaries on the embryological results of controlled ovarian hyperstimulation

    Directory of Open Access Journals (Sweden)

    Grzegorz Mrugacz

    2013-12-01

    Full Text Available Introduction: Controlled ovarian hyperstimulation is an integral part of infertility treatment. Despite many years of use, some aspects of controlled ovarian stimulation have not yet been clarified, especially the role of the functional status of the ovaries before hormonal stimulation. Aim of the research: To assess the effect of the functional status of the ovaries on the embryological results of controlled ovarian hyperstimulation. Material and methods: The retrospective study included female patients treated for infertility. The patients were divided into two groups depending on the ultrasonographic appearance of the ovaries before controlled ovarian hyperstimulation. Patients with small antral follicles 0.05. The numbers of A, C, D quality embryos were comparable between the groups (p > 0.05. There were more B quality embryos in group I than II (p > 0.05. The embryo growth rate was significantly faster in group I than II. Conclusions: The results of the present study indicate that the functional status of the ovaries before controlled ovarian hyperstimulation plays a pivotal role in treatment outcome.

  6. New Results on the Effect of Mothers’ Working Hours on Children’s Overweight Status

    DEFF Research Database (Denmark)

    Greve, Jane

    in exploring possible bias due to omitted variable bias. In contrast to the existing literature this paper shows that an increase in mothers’ working hours has a reducing effect on child weight. Subgroup analyses on formal and informal daycare suggest that the quality of childcare determines the effect...... weight. This paper uses the Danish Longitudinal Survey of Children (DALSC) merged with Danish register data from 1995 to 2002 to explore whether a causal relationship exists between maternal working hours and Danish children’s overweight status at age 7½. The instrumental variables technique is used......, as results show that maternal employment has a reducing effect on children’s overweight status in formal daycare (kindergarten). For children in informal daycare (family daycare), maternal employment has no significant effect....

  7. Description of premixing with the MC3D code including molten jet behavior modeling. Comparison with FARO experimental results

    Energy Technology Data Exchange (ETDEWEB)

    Berthoud, G.; Crecy, F. de; Meignen, R.; Valette, M. [CEA-G, DRN/DTP/SMTH, 17 rue des Martyrs, 38054 Grenoble Cedex 9 (France)

    1998-01-01

    The premixing phase of a molten fuel-coolant interaction is studied by the way of mechanistic multidimensional calculation. Beside water and steam, corium droplet flow and continuous corium jet flow are calculated independent. The 4-field MC3D code and a detailed hot jet fragmentation model are presented. MC3D calculations are compared to the FARO L14 experiment results and are found to give satisfactory results; heat transfer and jet fragmentation models are still to be improved to predict better final debris size values. (author)

  8. Verification of results of core physics on-line simulation by NGFM code

    International Nuclear Information System (INIS)

    Zhao Yu; Cao Xinrong; Zhao Qiang

    2008-01-01

    Nodal Green's Function Method program NGFM/TNGFM has been trans- planted to windows system. The 2-D and 3-D benchmarks have been checked by this program. And the program has been used to check the results of QINSHAN-II reactor simulation. It is proved that the NGFM/TNGFM program is applicable for reactor core physics on-line simulation system. (authors)

  9. MABEL-2: a code to analyse cladding deformation in a loss-of-coolant accident: status February 1980

    International Nuclear Information System (INIS)

    Gittus, J.H.; Haste, T.J.; Bowring, R.W.; Cooper, C.A.

    1980-02-01

    MABEL-2 calculates the deformation of a single fuel rod. This rod is surrounded by 8 other rods on a square lattice whose behaviour is specified via Input Data options. A 2-D (r,theta) conduction model is used for the fuel rod, the cladding creep is calculated from the CANSWEL-2 model and the feedback effect of clad strain on heat transfer to the coolant is obtained from subchannel analysis of the coolant passages surrounding the rod. The coding of the first version of MABEL-2 has been completed except for work to optimise the iteration convergence, minimise the running time and generally tidy up the coding. (author)

  10. Equilibrium optimization code OPEQ and results of applying it to HT-7U

    International Nuclear Information System (INIS)

    Zha Xuejun; Zhu Sizheng; Yu Qingquan

    2003-01-01

    The plasma equilibrium configuration has a strong impact on the confinement and MHD stability in tokamaks. For designing a tokamak device, it is an important issue to determine the sites and currents of poloidal coils which have some constraint conditions from physics and engineering with a prescribed equilibrium shape of the plasma. In this paper, an effective method based on multi-variables equilibrium optimization is given. The method can optimize poloidal coils when the previously prescribed plasma parameters are treated as an object function. We apply it to HT-7U equilibrium calculation, and obtain good results

  11. Research status and some results of numerical system to study regional environment: SPEEDI-MP

    International Nuclear Information System (INIS)

    Chino, Masamichi

    2004-01-01

    Research status and some results of 'Numerical system to study regional environment: SPEEDI-MP', which reproduces circulations of materials in the atmospheric, oceanic and terrestrial environments, are introduced. The purpose of this system are the development of various environmental models, the connection of atmospheric, oceanic and terrestrial models and the construction of research bases for numerical environmental studies. In addition to the accurate prediction of environmental behavior of radionuclides, the system has been applied to the non-nuclear fields, e.g., numerical analysis of environmental effects to volcanic gases from Miyake Jima, real-time prediction of the migration of rice planthoppers from Eastern Asia. (author)

  12. Application of PHEBUS results to benchmarking of nuclear plant safety codes

    International Nuclear Information System (INIS)

    Birchley, J.; Cripps, R.; Guentay, S.; Hosemann, J.P.

    2001-01-01

    The PHEBUS Fission Product project comprises six nuclear reactor severe accident simulations, using prototypic core materials and representative geometry and boundary conditions for the coolant loop and containment. The data thus produced are being used to benchmark the computer tools used for nuclear plant accident analysis to reduce the excessive conservatism typical for estimates of the radiological source term. A set of calculations has been carried out to simulate the results of experiment PHEBUS FPT-1 through each of its main stages, using computer models and methods analogous to those currently employed at PSI for assessments of Swiss nuclear plants. Good agreement for the core degradation and containment behaviour builds confidence in the models, while some open questions remain concerning some aspects of the release of fission products from the fuel, their transport and chemical speciation. Of potentially great importance to the reduction in source term estimates is the formation of the non-volatile species, silver iodide. Current investigations are focused on the uncertainty concerning fission product behaviour and the stability of silver iodide under irradiation. (author)

  13. Computational results with a branch and cut code for the capacitated vehicle routing problem

    Energy Technology Data Exchange (ETDEWEB)

    Augerat, P.; Naddef, D. [Institut National Polytechnique, 38 - Grenoble (France); Belenguer, J.M.; Benavent, E.; Corberan, A. [Valencia Univ. (Spain); Rinaldi, G. [Consiglio Nazionale delle Ricerche, Rome (Italy)

    1995-09-01

    The Capacitated Vehicle Routing Problem (CVRP) we consider in this paper consists in the optimization of the distribution of goods from a single depot to a given set of customers with known demand using a given number of vehicles of fixed capacity. There are many practical routing applications in the public sector such as school bus routing, pick up and mail delivery, and in the private sector such as the dispatching of delivery trucks. We present a Branch and Cut algorithm to solve the CVRP which is based in the partial polyhedral description of the corresponding polytope. The valid inequalities used in our method can ne found in Cornuejols and Harche (1993), Harche and Rinaldi (1991) and in Augerat and Pochet (1995). We concentrated mainly on the design of separation procedures for several classes of valid inequalities. The capacity constraints (generalized sub-tour eliminations inequalities) happen to play a crucial role in the development of a cutting plane algorithm for the CVRP. A large number of separation heuristics have been implemented and compared for these inequalities. There has been also implemented heuristic separation algorithms for other classes of valid inequalities that also lead to significant improvements: comb and extended comb inequalities, generalized capacity inequalities and hypo-tour inequalities. The resulting cutting plane algorithm has been applied to a set of instances taken from the literature and the lower bounds obtained are better than the ones previously known. Some branching strategies have been implemented to develop a Branch an Cut algorithm that has been able to solve large CVRP instances, some of them which had never been solved before. (authors). 32 refs., 3 figs., 10 tabs.

  14. Comparisons of numerical simulations with ASTRID code against experimental results in rod bundle geometry for boiling flows

    International Nuclear Information System (INIS)

    Larrauri, D.; Briere, E.

    1997-12-01

    After different validation simulations of flows through cylindrical and annular channels, a subcooled boiling flow through a rod bundle has been simulated with ASTRID Steam-Water of software. The experiment simulated is called Poseidon. It is a vertical rectangular channel with three heating rods inside. The thermohydraulic conditions of the simulated flow were close to the DNB conditions. The simulation results were analysed and compared against the available measurements of liquid and wall temperatures. ASTRID Steam-Water produced satisfactory results. The wall and the liquid temperatures were well predicted in the different parts of the flow. The void fraction reached 40 % in the vicinity of the heating rods. The distribution of the different calculated variables showed that a three-dimensional simulation gives essential information for the analysis of the physical phenomena involved in this kind of flow. The good results obtained in Poseidon geometry will encourage future rod bundle flow simulations and analyses with ASTRID Steam-Water code. (author)

  15. Offshore code comparison collaboration continuation (OC4), phase I - Results of coupled simulations of an offshore wind turbine with jacket support structure

    DEFF Research Database (Denmark)

    Popko, Wojciech; Vorpahl, Fabian; Zuga, Adam

    2012-01-01

    In this paper, the exemplary results of the IEA Wind Task 30 "Offshore Code Comparison Collaboration Continuation" (OC4) Project - Phase I, focused on the coupled simulation of an offshore wind turbine (OWT) with a jacket support structure, are presented. The focus of this task has been the verif......In this paper, the exemplary results of the IEA Wind Task 30 "Offshore Code Comparison Collaboration Continuation" (OC4) Project - Phase I, focused on the coupled simulation of an offshore wind turbine (OWT) with a jacket support structure, are presented. The focus of this task has been...... the verification of OWT modeling codes through code-to-code comparisons. The discrepancies between the results are shown and the sources of the differences are discussed. The importance of the local dynamics of the structure is depicted in the simulation results. Furthermore, attention is given to aspects...

  16. Nutritional status and its correlates in Equatorial Guinean preschool children: results from a nationally representative survey.

    Science.gov (United States)

    Custodio, Estefanía; Descalzo, Miguel Angel; Roche, Jesús; Sánchez, Ignacio; Molina, Laura; Lwanga, Magdalena; Bernis, Cristina; Villamor, Eduardo; Baylin, Ana

    2008-03-01

    In Equatorial Guinea, as a result of the recent growth of the oil industry, there is an opportunity to address important public health problems through public and private initiatives. To propose effective nutrition and public health strategies, it is important first to have reliable information on the nutritional status of the population and the underlying factors affecting it. To assess the nutritional status and the prevalence of anemia among Equatoguinean children in a nationally representative sample and to identify the risk factors associated with the nutritional problems detected. The study was a cross-sectional survey using a multistaged, stratified, cluster-selected sample. The survey included a sociodemographic, health, and dietary questionnaire and measurement of hematocrit and anthropometric features, from which nutritional indicators based on the National Center for Health Statistics (NCHS) reference and the World Health Organization (WHO) standards were calculated. Logistic regression models were used for the multivariate analysis. A total of 552 children aged 0 to 60 months were surveyed. The overall prevalence of stunting (hemoglobin hemoglobin education, should be undertaken.

  17. HIV status: the prima facie right not to know the result.

    Science.gov (United States)

    Chan, Tak Kwong

    2016-02-01

    When a patient regains consciousness from Cryptococcus meningitis, the clinician may offer an HIV test (in case it has not already been done) (scenario 1) or offer to tell the patient his HIV status (in case the test has already been performed with a positive result while the patient was unconscious) (scenario 2). Youngs and Simmonds proposed that the patient has the prima facie right to refuse an HIV test in scenario 1 but not the prima facie right not to be told the HIV status in scenario 2. I submit that the claims to the right of refusal in both scenarios are similarly strong as they should both be grounded in privacy, self determination or dignity. But a conscientious agent should bear in mind that members of the public also have the right not to be harmed. When the circumstance allows, a proper balance of the potential benefits and harm for all the competing parties should guide the clinical decision as to whose right should finally prevail. Where a full ethical analysis is not possible, the presumption should favour respecting the patient's right of refusal in both scenarios. Published by the BMJ Publishing Group Limited. For permission to use (where not already granted under a licence) please go to http://www.bmj.com/company/products-services/rights-and-licensing/

  18. [Nutritional screening before surgery for esophageal cancer - current status and evaluation results].

    Science.gov (United States)

    Shimakawa, Takeshi; Asaka, Shinich; Sagawa, Masano; Shimazaki, Asako; Yamaguchi, Kentaro; Usui, Takebumi; Yokomizo, Hajime; Shiozawa, Shunichi; Yoshimatsu, Kazuhiko; Katsube, Takao; Naritaka, Yoshihiko

    2014-10-01

    The incidence of postoperative complications and mortality are usually higher in patients with preoperative malnutrition. Malnutrition often preexists, particularly in patients undergoing surgery for esophageal cancer, which is substantially invasive. It is therefore important to understand the nutritional condition of patients and actively control perioperative nutrition.Our hospital has been providing nutritional status screening for patients before resection of esophageal cancer, and we report the current status and evaluation results in this article.This screening included 158 patients requiring radical resection of esophageal cancer.Age, comorbidity with diabetes, body mass index(BMI), serum albumin(Alb), Onodera's prognostic nutritional index(PNI), and Glasgow prognostic score(GPS)were used as nutritional indicators to stratify patients for analysis.Evaluation parameters included the incidence of postoperative complications(any complication, pulmonary complications, psychiatric disorder, and anastomotic leakage)and rates of long-term postoperative hospitalization.The analysis indicated that age, BMI, serum Alb, PNI, and GPS are useful for predicting the onset of postoperative complications and prolonged postoperative hospitalization.For such patients, more active nutritional control should be provided.

  19. ACTPol: Status and preliminary CMB polarization results from the Atacama Cosmology Telescope

    Science.gov (United States)

    Koopman, Brian

    2014-03-01

    The Atacama Cosmology Telescope Polarimeter (ACTPol) is a polarization sensitive upgrade for the Atacama Cosmology Telescope, located at an elevation of 5190 m on Cerro Toco in Chile. In summer 2013, ACTPol achieved first light with one third of the final detector configuration. The remaining two thirds of the detector array will be installed during spring 2014, enabling full sensitivity, high resolution, observations at both 90 GHz and 150 GHz. Using approximately 3,000 transition-edge sensor bolometers, ACTPol will enable measurements of small angular scale polarization anisotropies in the Cosmic Microwave Background (CMB). I will present a status update for the ACTPol receiver and some preliminary results. ACTPol measurements will allow us to probe the spectral index of inflation as well as to constrain early dark energy and the sum of neutrino masses.

  20. How do primary care doctors in England and Wales code and manage people with chronic kidney disease? Results from the National Chronic Kidney Disease Audit.

    Science.gov (United States)

    Kim, Lois G; Cleary, Faye; Wheeler, David C; Caplin, Ben; Nitsch, Dorothea; Hull, Sally A

    2017-10-16

    In the UK, primary care records are electronic and require doctors to ascribe disease codes to direct care plans and facilitate safe prescribing. We investigated factors associated with coding of chronic kidney disease (CKD) in patients with reduced kidney function and the impact this has on patient management. We identified patients meeting biochemical criteria for CKD (two estimated glomerular filtration rates 90 days apart) from 1039 general practitioner (GP) practices in a UK audit. Clustered logistic regression was used to identify factors associated with coding for CKD and improvement in coding as a result of the audit process. We investigated the relationship between coding and five interventions recommended for CKD: achieving blood pressure targets, proteinuria testing, statin prescription and flu and pneumococcal vaccination. Of 256 000 patients with biochemical CKD, 30% did not have a GP CKD code. Males, older patients, those with more severe CKD, diabetes or hypertension or those prescribed statins were more likely to have a CKD code. Among those with continued biochemical CKD following audit, these same characteristics increased the odds of improved coding. Patients without any kidney diagnosis were less likely to receive optimal care than those coded for CKD [e.g. odds ratio for meeting blood pressure target 0.78 (95% confidence interval 0.76-0.79)]. Older age, male sex, diabetes and hypertension are associated with coding for those with biochemical CKD. CKD coding is associated with receiving key primary care interventions recommended for CKD. Increased efforts to incentivize CKD coding may improve outcomes for CKD patients. © The Author 2017. Published by Oxford University Press on behalf of ERA-EDTA.

  1. The InterFrost benchmark of Thermo-Hydraulic codes for cold regions hydrology - first inter-comparison results

    Science.gov (United States)

    Grenier, Christophe; Roux, Nicolas; Anbergen, Hauke; Collier, Nathaniel; Costard, Francois; Ferrry, Michel; Frampton, Andrew; Frederick, Jennifer; Holmen, Johan; Jost, Anne; Kokh, Samuel; Kurylyk, Barret; McKenzie, Jeffrey; Molson, John; Orgogozo, Laurent; Rivière, Agnès; Rühaak, Wolfram; Selroos, Jan-Olof; Therrien, René; Vidstrand, Patrik

    2015-04-01

    The impacts of climate change in boreal regions has received considerable attention recently due to the warming trends that have been experienced in recent decades and are expected to intensify in the future. Large portions of these regions, corresponding to permafrost areas, are covered by water bodies (lakes, rivers) that interact with the surrounding permafrost. For example, the thermal state of the surrounding soil influences the energy and water budget of the surface water bodies. Also, these water bodies generate taliks (unfrozen zones below) that disturb the thermal regimes of permafrost and may play a key role in the context of climate change. Recent field studies and modeling exercises indicate that a fully coupled 2D or 3D Thermo-Hydraulic (TH) approach is required to understand and model the past and future evolution of landscapes, rivers, lakes and associated groundwater systems in a changing climate. However, there is presently a paucity of 3D numerical studies of permafrost thaw and associated hydrological changes, and the lack of study can be partly attributed to the difficulty in verifying multi-dimensional results produced by numerical models. Numerical approaches can only be validated against analytical solutions for a purely thermic 1D equation with phase change (e.g. Neumann, Lunardini). When it comes to the coupled TH system (coupling two highly non-linear equations), the only possible approach is to compare the results from different codes to provided test cases and/or to have controlled experiments for validation. Such inter-code comparisons can propel discussions to try to improve code performances. A benchmark exercise was initialized in 2014 with a kick-off meeting in Paris in November. Participants from USA, Canada, Germany, Sweden and France convened, representing altogether 13 simulation codes. The benchmark exercises consist of several test cases inspired by existing literature (e.g. McKenzie et al., 2007) as well as new ones. They

  2. Kinetic instabilities of thin current sheets: Results of two-and-one-half-dimensional Vlasov code simulations

    International Nuclear Information System (INIS)

    Silin, I.; Buechner, J.

    2003-01-01

    Nonlinear triggering of the instability of thin current sheets is investigated by two-and-one-half- dimensional Vlasov code simulations. A global drift-resonant instability (DRI) is found, which results from the lower-hybrid-drift waves penetrating from the current sheet edges to the center where they resonantly interact with unmagnetized ions. This resonant nonlinear instability grows faster than a Kelvin-Helmholtz instability obtained in previous studies. The DRI is either asymmetric or symmetric mode or a combination of the two, depending on the relative phase of the lower-hybrid-drift waves at the edges of the current sheet. With increasing particle mass ratio the wavenumber of the fastest-growing mode increases as kL z ∼(m i /m e ) 1/2 /2 and the growth rate of the DRI saturates at a finite level

  3. The ALI-ARMS Code for Modeling Atmospheric non-LTE Molecular Band Emissions: Current Status and Applications

    Science.gov (United States)

    Kutepov, A. A.; Feofilov, A. G.; Manuilova, R. O.; Yankovsky, V. A.; Rezac, L.; Pesnell, W. D.; Goldberg, R. A.

    2008-01-01

    The Accelerated Lambda Iteration (ALI) technique was developed in stellar astrophysics at the beginning of 1990s for solving the non-LTE radiative transfer problem in atomic lines and multiplets in stellar atmospheres. It was later successfully applied to modeling the non-LTE emissions and radiative cooling/heating in the vibrational-rotational bands of molecules in planetary atmospheres. Similar to the standard lambda iterations ALI operates with the matrices of minimal dimension. However, it provides higher convergence rate and stability due to removing from the iterating process the photons trapped in the optically thick line cores. In the current ALI-ARMS (ALI for Atmospheric Radiation and Molecular Spectra) code version additional acceleration of calculations is provided by utilizing the opacity distribution function (ODF) approach and "decoupling". The former allows replacing the band branches by single lines of special shape, whereas the latter treats non-linearity caused by strong near-resonant vibration-vibrational level coupling without additional linearizing the statistical equilibrium equations. Latest code application for the non-LTE diagnostics of the molecular band emissions of Earth's and Martian atmospheres as well as for the non-LTE IR cooling/heating calculations are discussed.

  4. DRACCAR, a new 3D-thermal mechanical computer code to simulate LOCA transient on nuclear power plants. Status of the development and the validation

    International Nuclear Information System (INIS)

    Georges, Repetto; Francois, Jacq; Francois, Barre; Francois, Lamare; Jean-Marc, Ricaud

    2009-01-01

    IRSN is developing the DRACCAR computational software within the scope of its safety analyses on pressurised water reactors (PWR). This software is used to study loss-of-coolant accidents in the reactor core (LOCA) or in a spent fuel storage tank, for example. During such an accident, the coolant vaporises and the fuel rods dry out, which leads to an increase of their temperature, a swelling and fuel cladding failure. This swelling is responsible for major blockage in port of the core and can jeopardize the possibility of core cooling by means of back-up systems. The 3D multi-rod software is designed to model a fuel assembly so as to assess rod cooling and the blockage rate caused by deformed rods, by taking into account mechanical and thermal interactions between rods. The software can provide a consistent interpretation of the entire experimental database for a 'single-rod' configuration or a 'rod-bundle' configuration with either real or simulator fuel, transpose these results onto a reactor scale to determine what kind of research still needs to be conducted and finally, carry out safety studies. The models developed for this software cover: Heat transfers by conduction, convection and radiation. Oxidation of Zircaloy elements (cladding, guide tubes, inner shroud layer..) as well as hydriding process which can change mechanical properties. Thermomechanical behavior of fuel cladding (deformation and failure), including bowing phenomenon. Thermohydraulics on the scale of an assembly (to couple with an appropriate software), including a reflooding model. Fuel relocation and release of fission gases. A first version (DRACCAR V1) was delivered in March 2008 and is being validated on the basis of available experimental data (EDGAR, PHEBUS LOCA, PERICLES, REBEKA, HALDEN, etc.). A second version will be released in 2012 for which a coupling, in particular in the frame of the European NURISP project, is planned to an advanced sub-channel thermal-hydraulics code CATHARE

  5. Ultra-high energy cosmic rays. Results and status of the Pierre Auger Observatory

    Energy Technology Data Exchange (ETDEWEB)

    Peters, Christine [III. Physikalisches Institut A, RWTH Aachen University (Germany); Collaboration: Pierre-Auger-Collaboration

    2016-07-01

    The Pierre Auger Observatory is the world's largest experiment detecting extensive air showers initiated by cosmic rays at the highest energies. An area of 3000 km{sup 2} is instrumented by 1660 water Cherenkov detector stations, and 27 fluorescence telescopes overlook the atmosphere above the surface detector array. A hybrid detection principle is achieved by utilizing information of both detectors. A major upgrade of the experiment (AugerPrime) has been decided adding a third detector type, scintillator detector stations located on the water Cherenkov tanks. Thereby, the composition sensitivity of the Pierre Auger Observatory is extended by an improved determination of the muonic shower component. Additionally, underground muon detectors (AMIGA) are deployed. The experiment has been further extended by antennas measuring the emission of radio signals from air showers (AERA). An overview about recent results and the current status of the experiment are given in this talk. Highlights are updated results, e.g. on the energy spectrum, chemical composition or proton-air cross section.

  6. The status of diabetes control in Malaysia: results of DiabCare 2008.

    Science.gov (United States)

    Mafauzy, M; Hussein, Z; Chan, S P

    2011-08-01

    DiabCare Malaysia 2008 evaluated the current status of diabetes care in Malaysia as a continuation of similar cross-sectional studies conducted previously in 1997, 1998, 2001 and 2003. The current study recruited 1670 patients from general hospitals, diabetes clinics and referral clinics to study current scenario of diabetes management. We report the results of type 2 diabetic population who constituted 92.8% (n = 1549). Results showed deteriorating glycaemic control with mean HbA1c of 8.66 +/- 2.09% with only 22% of the patients achieving ADA target of 2.6 mmol/L; 19.8% had triglycerides > 2.2 mmol/L; 27.4% had HDL exercise and self testing of blood glucose. In conclusion, majority of the patients were still not satisfactorily controlled. There is an urgent need for effective remedial measures to increase adherence to practice guidelines and to educate both patients and healthcare personnel on importance of achieving clinical targets for metabolic control.

  7. Fuel model studies. Comparison of our present version of GAPCON-THERMAL-2 with results from the EPRI code comparison study. Partial report

    International Nuclear Information System (INIS)

    Malen, K.; Jansson, L.

    1978-08-01

    Runs with our present version of GAPCON-THERMAL-2 have been compared to results from the EPRI code comparison study. Usually also our version of GAPCON predicts high temperatures, 100-300 K or 10-15% higher than average code predictions and experimental results. The well-known temperaturegas release instablility is found also with GAPCON. In this case one identifies the gas release limits 1400 deg C and 1700 deg C as instablility points. (author)

  8. Coronal mass ejection hits mercury: A.I.K.E.F. hybrid-code results compared to MESSENGER data

    Science.gov (United States)

    Exner, W.; Heyner, D.; Liuzzo, L.; Motschmann, U.; Shiota, D.; Kusano, K.; Shibayama, T.

    2018-04-01

    Mercury is the closest orbiting planet around the sun and is therefore embedded in an intensive and highly varying solar wind. In-situ data from the MESSENGER spacecraft of the plasma environment near Mercury indicates that a coronal mass ejection (CME) passed the planet on 23 November 2011 over the span of the 12 h MESSENGER orbit. Slavin et al. (2014) derived the upstream parameters of the solar wind at the time of that orbit, and were able to explain the observed MESSENGER data in the cusp and magnetopause segments of MESSENGER's trajectory. These upstream parameters will be used for our first simulation run. We use the hybrid code A.I.K.E.F. which treats ions as individual particles and electrons as a mass-less fluid, to conduct hybrid simulations of Mercury's magnetospheric response to the impact of the CME on ion gyro time scales. Results from the simulation are in agreement with magnetic field measurements from the inner day-side magnetosphere and the bow-shock region. However, at the planet's nightside, Mercury's plasma environment seemed to be governed by different solar wind conditions, in conclusion, Mercury's interaction with the CME is not sufficiently describable by only one set of upstream parameters. Therefore, to simulate the magnetospheric response while MESSENGER was located in the tail region, we use parameters obtained from the MHD solar wind simulation code SUSANOO (Shiota et al. (2014)) for our second simulation run. The parameters of the SUSANOO model achieve a good agreement of the data concerning the plasma tail crossing and the night-side approach to Mercury. However, the polar and closest approach are hardly described by both upstream parameters, namely, neither upstream dataset is able to reproduce the MESSENGER crossing of Mercury's magnetospheric cusp. We conclude that the respective CME was too variable on the timescale of the MESSENGER orbit to be described by only two sets of upstream conditions. Our results suggest locally strong

  9. Dietary iron intake and iron status of German female vegans: results of the German vegan study.

    Science.gov (United States)

    Waldmann, Annika; Koschizke, Jochen W; Leitzmann, Claus; Hahn, Andreas

    2004-01-01

    As shown in previous studies vegetarians and especially vegans are at risk for iron deficiency. Our study evaluated the iron status of German female vegans. In this cross-sectional study, the dietary intakes of 75 vegan women were assessed by two 9-day food frequency questionnaires. The iron status was analyzed on the basis of blood parameters. Mean daily iron intake was higher than recommended by the German Nutrition Society. Still 42% of the female vegans or = 50 years (old women, OW). In all, 40% (tri-index model (TIM) 20%) of the YW and 12% (TIM 12%) of the OW were considered iron-deficient based on either serum ferritin levels of vegan diet should have their iron status monitored and should consider taking iron supplements in case of a marginal status. Copyright 2004 S. Karger AG, Basel

  10. Comparative analysis of the results obtained by computer code ASTEC V2 and RELAP 5.3.2 for small leak ID 80 for VVER 1000

    International Nuclear Information System (INIS)

    Atanasova, B.; Grudev, P.

    2011-01-01

    The purpose of this report is to present the results obtained by simulation and subsequent analysis of emergency mode for small leak with ID 80 for WWER 1000/B320 - Kozloduy NPP Units 5 and 6. Calculations were performed with the ASTEC v2 computer code used for calculation of severe accident, which was designed by French and German groups - IRSN and GRS. Integral RELAP5 computer code is used as a reference for comparison of results. The analyzes are focused on the processes occurring in reactor internals phase of emergency mode with significant core damage. The main thermohydraulic parameters, start of reactor core degradation and subsequent fuel relocalization till reactor vessel failure are evaluated in the analysis. RELAP5 computer code is used as a reference code to compare the results obtained till early core degradation that occurs after core stripping and excising of fuel temperature above 1200 0 C

  11. THE GLOBAL TANDEM-X DEM: PRODUCTION STATUS AND FIRST VALIDATION RESULTS

    Directory of Open Access Journals (Sweden)

    M. Huber

    2012-07-01

    Full Text Available The TanDEM-X mission will derive a global digital elevation model (DEM with satellite SAR interferometry. Two radar satellites (TerraSAR-X and TanDEM-X will map the Earth in a resolution and accuracy with an absolute height error of 10m and a relative height error of 2m for 90% of the data. In order to fulfill the height requirements in general two global coverages are acquired and processed. Besides the final TanDEM-X DEM, an intermediate DEM with reduced accuracy is produced after the first coverage is completed. The last step in the whole workflow for generating the TanDEM-X DEM is the calibration of remaining systematic height errors and the merge of single acquisitions to 1°x1° DEM tiles. In this paper the current status of generating the intermediate DEM and first validation results based on GPS tracks, laser scanning DEMs, SRTM data and ICESat points are shown for different test sites.

  12. The estimate reproductive health status of populations exposured in low doses in result of Chernobyl disaster

    International Nuclear Information System (INIS)

    Ljaginskaja, A.M.; Izhewskij, P.W.; Golovko, O.V.

    1996-01-01

    In general the results achieved show that in the population living on the territories contaminated with radionuclides the most distinct negative dynamic of reproductive health than in the control areas is observed dourly the post-accidental period. The highest intensively of the negative dynamic and for certain the lower (than in the control) absolute indices of the reproductive health are revealed in the population living on the territory with 137 Cs contamination from 5 Ci/km 2 to 15 Ci/km 2 Under the equal conditions of 137 Cs contamination of soil the most distinct decrease of indices of the reproductive health was revealed in the areas with the most original level of the reproductive health that witness about the important role of the original level of the reproductive health in forming the effects of the exposure of the population. In the structure of the chosen indices of the reproductive health the loading place according to the intensively of the negative dynamic takes the indices characterising UPO and the status of the newborns, that is the indices reflecting the somatic stochastic effects of radiation influence. (author)

  13. Perturbations in carotenoid and porphyrin status result in differential photooxidative stress signaling and antioxidant responses.

    Science.gov (United States)

    Park, Joon-Heum; Jung, Sunyo

    2018-02-12

    We examined differential photooxidative stress signaling and antioxidant responses in rice plants treated with norflurazon (NF) and oxyfluorfen (OF), which are inhibitors of carotenoid and porphyrin biosynthesis, respectively. Plants treated with OF markedly increased levels of cellular leakage and malondialdehyde, compared with NF-treated plants, showing that OF plants suffered greater oxidative damage with respect to membrane integrity. The enhanced production of H 2 O 2 in response to OF, but not NF, indicates the important role of H 2 O 2 in activation of photooxidative stress signaling in OF plants. In response to NF and OF, the increased levels of free salicylic acid as well as maintenance of the redox ratio of ascorbate and glutathione pools to a certain level are considered to be crucial factors in the protection against photooxidation. Plants treated with OF greatly up-regulated catalase (CAT) activity and Cat transcript levels, compared with NF-treated plants. Interestingly, NF plants showed no noticeable increase in oxidative metabolism, although they did show considerable increases in ascorbate peroxidase (APX) and peroxidase activities and transcript levels of APX, as in OF plants. Our results suggest that perturbations in carotenoid and porphyrin status by NF and OF can be sensed by differential photooxidative stress signaling, such as that involving H 2 O 2 , redox state of ascorbate and glutathione, and salicylic acid, which may be responsible for at least part of the induction of ROS-scavenging enzymes. Copyright © 2018 Elsevier Inc. All rights reserved.

  14. "Know Your Status": results from a novel, student-run HIV testing initiative on college campuses.

    Science.gov (United States)

    Milligan, Caitlin; Cuneo, C Nicholas; Rutstein, Sarah E; Hicks, Charles

    2014-08-01

    Know Your Status (KYS), a novel, student-run program offered free HIV-testing at a private university (PU) and community college (CC). Following completion of surveys of risk behaviors/reasons for seeking testing, students were provided with rapid, oral HIV-testing. We investigated testing history, risk behaviors, and HIV prevalence among students tested during the first three years of KYS. In total, 1408 tests were conducted, 5 were positive: 4/408 CC, 1/1000 PU (1% vs. 0.1%, p=0.01). Three positives were new diagnoses, all black men-who-have-sex-with-men (MSM). Over 50% of students were tested for the first time and 59% reported risk behaviors. CC students were less likely to have used condoms at last sex (a surrogate for risk behavior) compared to PU (OR 0.73, CI [0.54, 0.98]). Race, sexual identity, and sex were not associated with condom use. These results demonstrate that KYS successfully recruited large numbers of previously untested, at-risk students, highlighting the feasibility and importance of testing college populations.

  15. Comparison of ASME Code NB-3200 and NB-3600 results for fatigue analysis of B31.1 branch nozzles

    International Nuclear Information System (INIS)

    Nitzel, M.E.; Ware, A.G.; Morton, D.K.

    1996-01-01

    Fatigue analyses wre conducted on two reactor coolant system branch nozzles in an operating PWR designed to the B31.1 Code, for which no explicit fatigue analysis was required by the licensing basis. These analyses were performed as part of resolving issues connected with NRC's Fatigue Action Plan to determine if the cumulative usage factor (CUF) for these nozzles, using the 1992 ASME Code and representative PWR transients, were comparable to nozzles designed and analyzed to the ASME Code. Both NB-3200 and NB-3600 ASME Code methods were used. NB-3200 analyses included the development of finite element models for each nozzle. Although detailed thermal transients were not available for the plant analyzed, representative transients from similar PWRs were applied in each method. CUFs calculated using NB-3200 methods were significantly less than using NB-3600. The paper points out differences in analysis methods and highlights difficulties and unknowns in performing more detailed analyses to reduce conservative assumptions

  16. A multidisciplinary audit of clinical coding accuracy in otolaryngology: financial, managerial and clinical governance considerations under payment-by-results.

    Science.gov (United States)

    Nouraei, S A R; O'Hanlon, S; Butler, C R; Hadovsky, A; Donald, E; Benjamin, E; Sandhu, G S

    2009-02-01

    To audit the accuracy of otolaryngology clinical coding and identify ways of improving it. Prospective multidisciplinary audit, using the 'national standard clinical coding audit' methodology supplemented by 'double-reading and arbitration'. Teaching-hospital otolaryngology and clinical coding departments. Otolaryngology inpatient and day-surgery cases. Concordance between initial coding performed by a coder (first cycle) and final coding by a clinician-coder multidisciplinary team (MDT; second cycle) for primary and secondary diagnoses and procedures, and Health Resource Groupings (HRG) assignment. 1250 randomly-selected cases were studied. Coding errors occurred in 24.1% of cases (301/1250). The clinician-coder MDT reassigned 48 primary diagnoses and 186 primary procedures and identified a further 209 initially-missed secondary diagnoses and procedures. In 203 cases, patient's initial HRG changed. Incorrect coding caused an average revenue loss of 174.90 pounds per patient (14.7%) of which 60% of the total income variance was due to miscoding of a eight highly-complex head and neck cancer cases. The 'HRG drift' created the appearance of disproportionate resource utilisation when treating 'simple' cases. At our institution the total cost of maintaining a clinician-coder MDT was 4.8 times lower than the income regained through the double-reading process. This large audit of otolaryngology practice identifies a large degree of error in coding on discharge. This leads to significant loss of departmental revenue, and given that the same data is used for benchmarking and for making decisions about resource allocation, it distorts the picture of clinical practice. These can be rectified through implementing a cost-effective clinician-coder double-reading multidisciplinary team as part of a data-assurance clinical governance framework which we recommend should be established in hospitals.

  17. CORRELATION BETWEEN NUTRITIONAL STATUS AND CLINICAL RESULTS IN PATIENTS UNDERGOING SPINAL SURGERY

    Directory of Open Access Journals (Sweden)

    SAMUEL MACHADO MARTINS

    Full Text Available ABSTRACT Objective: To investigate the relationship between preoperative vitamin D and albumin levels and postoperative quality of life in patients undergoing spinal surgery. Methods: Patients undergoing thoracic and lumbar spine surgery were evaluated in this prospective study. Their vitamin D and albumin levels were assessed before surgery and quality of life was measured by two questionnaires, Oswestry Disability Index (ODI and Scoliosis Research Society - 22 (SRS-22, one year after the procedure. Data on infection occurrence and healing time were collected. Preoperative nutritional values and patients’ quality of life were analyzed using the chi-square test and ANOVA for albumin and vitamin D, respectively. The relationship among nutritional status, healing time, and the occurrence of infection was evaluated by the Pearson correlation coefficient. Results: Forty-six patients were included and their mean nutritional values were 19.1 (6.6 ng/mL for vitamin D and 3.9 (0.6 g/dL for albumin [mean (standard deviation]. No association was found between vitamin D and quality of life of patients measured by ODI (p=0.534 and SRS-22 (p=0.739 questionnaires. There was also no association between albumin levels and quality of life measured by ODI (p=0.259 and SRS-22 (p=0.076 questionnaires. No correlation was found between the healing time or occurrence of infection and nutritional values. Conclusions: There was no association between vitamin D and albumin levels and the surgical result, according to the patient’s perception, besides the occurrence of complications with the surgical wound.

  18. Socioeconomic status and stomach cancer incidence in men: Results from the Netherlands Cohort Study

    NARCIS (Netherlands)

    Loon, A.J.M. van; Goldbohm, R.A.; Brandt, P.A. van den

    1998-01-01

    Study objective - To study the association between socioeconomic status (SES) and stomach cancer incidence (cardia and non-cardia) and the role of lifestyle factors in explaining this association. Design - Prospective cohort study on diet and cancer that started in 1986. Data were collected by means

  19. Student Performance and Family Socioeconomic Status: Results from a Survey of Compulsory Education in Western China

    Science.gov (United States)

    Liu, Xiaofei; Lu, Ke

    2008-01-01

    This study used fifteen-year-old ninth-grade students from rural areas of five provinces in western China as samples to carry out research on the relationship between the socioeconomic status of Chinese families and student academic performance. Based on parents' educational background, occupation, family economic conditions, and other factors,…

  20. Preliminary results of the global audit of treatment of refractory status epilepticus.

    Science.gov (United States)

    Ferlisi, M; Hocker, S; Grade, M; Trinka, E; Shorvon, S

    2015-08-01

    The treatment of refractory and super refractory status epilepticus is a "terra incognita" from the point of view of evidence-based medicine. As randomized or controlled studies that are sufficiently powered are not feasible in relation to the many therapies and treatment approaches available, we carried out an online multinational audit (registry) in which neurologists or intensivists caring for patients with status epilepticus may prospectively enter patients who required general anesthesia to control the status epilepticus (SE). To date, 488 cases from 44 different countries have been collected. Most of the patients had no history of epilepsy and had a cryptogenic etiology. First-line treatment was delayed and not in line with current guidelines. The most widely used anesthetic of first choice was midazolam (59%), followed by propofol and barbiturates. Ketamine was used in most severe cases. Other therapies were administered in 35% of the cases, mainly steroids and immunotherapy. Seizure control was achieved in 74% of the patients. Twenty-two percent of patients died during treatment, and four percent had treatment actively withdrawn because of an anticipated poor outcome. The neurological outcome was good in 36% and poor in 39.3% of cases, while 25% died during hospitalization. Factors that positively influenced outcome were younger age, history of epilepsy, and low number of different anesthetics tried. This article is part of a Special Issue entitled "Status Epilepticus". Copyright © 2015. Published by Elsevier Inc.

  1. Current status and results of the PBMR -Pebble Box- benchmark within the framework of the IAEA CRP5 - 341

    International Nuclear Information System (INIS)

    Reitsma, F.; Tyobeka, B.

    2010-01-01

    The verification and validation of computer codes used in the analysis of high temperature gas cooled pebble bed reactor systems has not been an easy goal to achieve. A limited amount of tests and operating reactor measurements are available. Code-to-code comparisons for realistic pebble bed reactor designs often exhibit differences that are difficult to explain and are often blamed on the complexity of the core models or the variety of analysis methods and cross section data sets employed. For this reason, within the framework of the IAEA CRP5, the 'Pebble Box' benchmark was formulated as a simple way to compare various treatments of neutronics phenomena. The problem is comprised of six test cases which were designed to investigate the treatments and effects of leakage and heterogeneity. This paper presents the preliminary results of the benchmark exercise as received during the CRP and suggests possible future steps towards the resolution of discrepancies between the results. Although few participants took part in the benchmarking exercise, the results presented here show that there is still a need for further evaluation and in-depth understanding in order to build the confidence that all the different methods, codes and cross-section data sets have the capability to handle the various neutronics effects for such systems. (authors)

  2. Change in MS-DRG assignment and hospital reimbursement as a result of Centers for Medicare & Medicaid changes in payment for hospital-acquired conditions: is it coding or quality?

    Science.gov (United States)

    McNutt, Robert; Johnson, Tricia J; Odwazny, Richard; Remmich, Zachary; Skarupski, Kimberly; Meurer, Steven; Hohmann, Samuel; Harting, Brian

    2010-01-01

    In October 2008, the Centers for Medicare & Medicaid Services reduced payments to hospitals for a group of hospital-acquired conditions (HACs) not documented as present on admission (POA). It is unknown what proportion of Medicare severity diagnosis related group (MS-DRG) assignments will change when the International Classification of Disease, 9th Revision, Clinical Modification (ICD-9-CM) diagnosis code for the HAC is not taken into account even before considering the POA status. The primary objectives were to estimate the proportion of cases that change MS-DRG assignment when HACs are removed from the calculation, the subsequent changes in reimbursement to hospitals, and the attenuation in changes in MS-DRG assignment after factoring in those that may be POA. Last, we explored the effect of the numbers of ICD-9-CM diagnosis codes on MS-DRG assignment. We obtained 2 years of discharge data from academic medical centers that were members of the University Health System Consortium and identified all cases with 1 of 7 HACs coded through ICD-9-CM diagnosis codes. We calculated the MS-DRG for each case with and without the HAC and, hence, the proportion where MS-DRG assignment changed. Next, we used a bootstrap method to calculate the range in the proportion of cases changing assignment to account for POA status. Changes in reimbursement were estimated by using the 2008 MS-DRG weights payment formula. Of 184,932 cases with at least 1 HAC, 27.6% (n = 52,272) would experience a change in MS-DRG assignment without the HAC factored into the assignment. After taking into account those conditions that were potentially POA, 7.5% (n = 14,176) of the original cases would change MS-DRG assignment, with an average loss in reimbursement per case ranging from $1548 with a catheter-associated urinary tract infection to $7310 for a surgical site infection. These reductions would translate into a total reimbursement loss of $50 261,692 (range: $38 330,747-$62 344,360) for the 86

  3. Surviving "Payment by Results": a simple method of improving clinical coding in burn specialised services in the United Kingdom.

    Science.gov (United States)

    Wallis, Katy L; Malic, Claudia C; Littlewood, Sonia L; Judkins, Keith; Phipps, Alan R

    2009-03-01

    Coding inpatient episodes plays an important role in determining the financial remuneration of a clinical service. Insufficient or incomplete data may have very significant consequences on its viability. We created a document that improves the coding process in our Burns Centre. At Yorkshire Regional Burns Centre an inpatient summary sheet was designed to prospectively record and present essential information on a daily basis, for use in the coding process. The level of care was also recorded. A 3-month audit was conducted to assess the efficacy of the new forms. Forty-nine patients were admitted to the Burns Centre with a mean age of 27.6 years and TBSA ranging from 0.5% to 65%. The total stay in the Burns Centre was 758 days, of which 22% were at level B3-B5 and 39% at level B2. The use of the new discharge document identified potential income of about 500,000 GB pound sterling at our local daily tariffs for high dependency and intensive care. The new form is able to ensure a high quality of coding with a possible direct impact on the financial resources accrued for burn care.

  4. Barriers to data quality resulting from the process of coding health information to administrative data: a qualitative study.

    Science.gov (United States)

    Lucyk, Kelsey; Tang, Karen; Quan, Hude

    2017-11-22

    Administrative health data are increasingly used for research and surveillance to inform decision-making because of its large sample sizes, geographic coverage, comprehensivity, and possibility for longitudinal follow-up. Within Canadian provinces, individuals are assigned unique personal health numbers that allow for linkage of administrative health records in that jurisdiction. It is therefore necessary to ensure that these data are of high quality, and that chart information is accurately coded to meet this end. Our objective is to explore the potential barriers that exist for high quality data coding through qualitative inquiry into the roles and responsibilities of medical chart coders. We conducted semi-structured interviews with 28 medical chart coders from Alberta, Canada. We used thematic analysis and open-coded each transcript to understand the process of administrative health data generation and identify barriers to its quality. The process of generating administrative health data is highly complex and involves a diverse workforce. As such, there are multiple points in this process that introduce challenges for high quality data. For coders, the main barriers to data quality occurred around chart documentation, variability in the interpretation of chart information, and high quota expectations. This study illustrates the complex nature of barriers to high quality coding, in the context of administrative data generation. The findings from this study may be of use to data users, researchers, and decision-makers who wish to better understand the limitations of their data or pursue interventions to improve data quality.

  5. HAMLET -Human Model MATROSHKA for Radiation Exposure Determination of Astronauts -Current status and results

    Science.gov (United States)

    Reitz, Guenther; Berger, Thomas; Bilski, Pawel; Burmeister, Soenke; Labrenz, Johannes; Hager, Luke; Palfalvi, Jozsef K.; Hajek, Michael; Puchalska, Monika; Sihver, Lembit

    contribute essentially to radiation risk estimations for future interplanetary space exploration by humans, putting them on a solid experimental and theoretical basis. The talk will give an overview of the current status of the MATROSHKA data evaluation and results and comparisons of the first three MTR experimental phases (MTR-1, 2A and 2B). The HAMLET project is funded by the European Commission under the EUs Seventh Frame-work Programme (FP7) under Project Nr: 218817 and coordinated by the German Aerospace Center (DLR) http://www-fp7-hamlet.eu

  6. On the Representation of Aquifer Compressibility in General Subsurface Flow Codes: How an Alternate Definition of Aquifer Compressibility Matches Results from the Groundwater Flow Equation

    Science.gov (United States)

    Birdsell, D.; Karra, S.; Rajaram, H.

    2017-12-01

    The governing equations for subsurface flow codes in deformable porous media are derived from the fluid mass balance equation. One class of these codes, which we call general subsurface flow (GSF) codes, does not explicitly track the motion of the solid porous media but does accept general constitutive relations for porosity, density, and fluid flux. Examples of GSF codes include PFLOTRAN, FEHM, STOMP, and TOUGH2. Meanwhile, analytical and numerical solutions based on the groundwater flow equation have assumed forms for porosity, density, and fluid flux. We review the derivation of the groundwater flow equation, which uses the form of Darcy's equation that accounts for the velocity of fluids with respect to solids and defines the soil matrix compressibility accordingly. We then show how GSF codes have a different governing equation if they use the form of Darcy's equation that is written only in terms of fluid velocity. The difference is seen in the porosity change, which is part of the specific storage term in the groundwater flow equation. We propose an alternative definition of soil matrix compressibility to correct for the untracked solid velocity. Simulation results show significantly less error for our new compressibility definition than the traditional compressibility when compared to analytical solutions from the groundwater literature. For example, the error in one calculation for a pumped sandstone aquifer goes from 940 to <70 Pa when the new compressibility is used. Code users and developers need to be aware of assumptions in the governing equations and constitutive relations in subsurface flow codes, and our newly-proposed compressibility function should be incorporated into GSF codes.

  7. Socioeconomic status and smoking among thai adults: results of the National Thai Food Consumption Survey.

    Science.gov (United States)

    Jitnarin, Nattinee; Kosulwat, Vongsvat; Rojroongwasinkul, Nipa; Boonpraderm, Atitada; Haddock, Christopher K; Poston, Walker S C

    2011-09-01

    The authors examined the relationship between socioeconomic status and smoking in Thai adults. A nationally representative sample of 7858 Thais adults (18 years and older) was surveyed during 2004 to 2005. Four demographic/socioeconomic indicators were examined in logistic models: gender, education, occupational status, and annual household income. Overall, 22.2% of the participants were smokers. Men were more likely to be smokers across all age groups and regions. Compared with nonsmokers, current smokers were less educated, more likely to be employed, but had lower household income. When stratified by gender, education and job levels were strongly associated with smoking prevalence among males. A significant relationship was found between annual household income and smoking. Those who lived under the poverty line were more likely to smoke than persons who lived above the poverty line in both genders. The present study demonstrated that socioeconomic factors, especially education level and occupational class, have a strong influence on smoking behavior in Thai adults.

  8. Paths to Lawful Immigration Status: Results and Implications from the PERSON Survey

    Directory of Open Access Journals (Sweden)

    Tom K. Wong

    2014-12-01

    Full Text Available Anecdotal evidence suggests that a significant percentage of unauthorized immigrants are potentially eligible for some sort of immigration relief, but they either do not know it or are not able to pursue lawful immigration status for other reasons. However, no published study that we are aware of has systematically analyzed this question. The purpose of this study is thus to evaluate and quantify the number of unauthorized immigrants who, during the course of seeking out legal services, have been determined to be potentially eligible for some sort of immigration benefit or relief that provides lawful immigration status. Using the recent implementation of the Deferred Action for Childhood Arrivals (DACA program as a laboratory for this work, this study attempts to answer the question of the number of unauthorized immigrants who, without knowing it, may already be potentially eligible for lawful immigration status. In surveying 67 immigrant-serving organizations that provide legal services, we find that 14.3 percent of those found to be eligible for DACA were also found to be eligible for some other form of immigration relief—put otherwise, 14.3 percent of individuals that were found to be eligible for DACA, which provides temporary relief from deportation, may now be on a path towards lawful permanent residency. We find that the most common legal remedies available to these individuals are family-based petitions (25.5 percent, U-Visas (23.9 percent, and Special Immigrant Juvenile Status (12.6 percent. These findings make clear that—with comprehensive immigration reform legislation or eligibility for administrative relief —legal screening can have significant and long-lasting implications on the lives of unauthorized immigrants and their families.

  9. Validation of One-Dimensional Module of MARS-KS1.2 Computer Code By Comparison with the RELAP5/MOD3.3/patch3 Developmental Assessment Results

    International Nuclear Information System (INIS)

    Bae, S. W.; Chung, B. D.

    2010-07-01

    This report records the results of the code validation for the one-dimensional module of the MARS-KS thermal hydraulics analysis code by means of result-comparison with the RELAP5/MOD3.3 computer code. For the validation calculations, simulations of the RELAP5 Code Developmental Assessment Problem, which consists of 22 simulation problems in 3 categories, have been selected. The results of the 3 categories of simulations demonstrate that the one-dimensional module of the MARS code and the RELAP5/MOD3.3 code are essentially the same code. This is expected as the two codes have basically the same set of field equations, constitutive equations and main thermal hydraulic models. The result suggests that the high level of code validity of the RELAP5/MOD3.3 can be directly applied to the MARS one-dimensional module

  10. Some uncertainty results obtained by the statistical version of the KARATE code system related to core design and safety analysis

    Energy Technology Data Exchange (ETDEWEB)

    Panka, Istvan; Hegyi, Gyoergy; Maraczy, Csaba; Temesvari, Emese [Hungarian Academy of Sciences, Budapest (Hungary). Reactor Analysis Dept.

    2017-11-15

    The best-estimate KARATE code system has been widely used for core design calculations and simulations of slow transients of VVER reactors. Recently there has been an increasing need for assessing the uncertainties of such calculations by propagating the basic input uncertainties of the models through the full calculation chain. In order to determine the uncertainties of quantities of interest during the burnup, the statistical version of the KARATE code system has been elaborated. In the first part of the paper, the main features of the new code system are discussed. The applied statistical method is based on Monte-Carlo sampling of the considered input data taking into account mainly the covariance matrices of the cross sections and/or the technological uncertainties. In the second part of the paper, only the uncertainties of cross sections are considered and an equilibrium cycle related to a VVER-440 type reactor is investigated. The burnup dependence of the uncertainties of some safety related parameters (e.g. critical boron concentration, rod worth, feedback coefficients, assembly-wise radial power and burnup distribution) are discussed and compared to the recently used limits.

  11. Present status of reactor physics in the United States and Japan-I. 5. Development of the MVP Monte Carlo Code at JAERI

    International Nuclear Information System (INIS)

    Mori, T.; Okumura, K.; Nagaya, Y.

    2001-01-01

    neutrons was used as a source spectrum, and the source neutrons were assumed to be emitted uniformly in a sharp cone of 5.94x10 -4 sr taking account of the geometry of the collimator. The experimental arrangement, thickness of the test shields, measured neutron source spectrum, and peak fluxes of source neutrons per proton beam charge (μC) are given in Ref. 7. The calculated neutron spectra for 20-, 4-, and 100-cm thick iron shields are compared in Fig. 1 with the measured ones. Good agreement is obtained for thinner cases. For the 100-cm thick shield, on the other hand, the calculation gives higher fluxes by a factor of ∼2 compared with the measurement, although errors of both measured and calculated results are fairly large. This overestimation is quite similar to that by the MCNPX calculation using the same cross-section library. For coupled neutron, proton, and meson transport calculations by MVP, collision analysis routines using evaluated nuclear data in the ENDF-6 format and macroscopic transport routines based on the model of the NMTC/JAERI nucleon-meson transport code have been developed, and their benchmark tests have just started. To treat a higher-energy region where no evaluated nuclear data are available, we have started to implement the Bertini and the Jet AA Microscopic Transport models into the MVP code. The combined code, whose energy range is extended up to 200 GeV, is called JAERI High Energy Transport. To simulate the Feynman-α experiment, which is one of time domain noise analyses, some functions were added to the MVP code to make the analog Monte Carlo simulation. The number of neutrons from each fission event can be sampled from the distribution given by Terrell. Scatter, capture, fission, and absorption detectors are available. A periodic-time boundary condition is used to describe stationary neutron sources including neutrons from spontaneous fission whose number should be selected from Terrell's distribution at each event. The MVP code

  12. Regional energy observatory. Energy status - greenhouse effect in the Aquitaine region. First results

    International Nuclear Information System (INIS)

    2003-06-01

    The IDEA organization (information about the environmental development in Aquitaine region) has created an energy observatory, the mission of which is to supply regularly a reliable, objective and useful information about energy and greenhouse effect in the Aquitaine region (SW France). This document presents: the end-use energy consumption, the sectorial statuses (residential, tertiary sector, industry, agriculture, transports), the energy production and the renewable energy sources in Aquitaine region. Details are given in separate files at the end of the document for the 5 departements of Aquitaine (Dordogne, Gironde, Landes, Lot-et-Garonne, Pyrennees Atlantiques). (J.S.)

  13. Cartilage status in FAI patients - results from the Danish Hip Arthroscopy Registry (DHAR)

    DEFF Research Database (Denmark)

    Lund, Bent; Nielsen, Torsten Grønbech; Lind, Martin

    2017-01-01

    management is not fully elucidated. This study from the Danish Hip Arthroscopy Registry (DHAR) will try to show data on the cartilage status from a large cohort. Data from a national registry potentially represent large amounts of population-based epidemiological information from multiple centres...... severe acetabular cartilage injury. DISCUSSION: The majority of patients with femoroacetabular impingement (FAI) undergoing hip arthroscopy have significant cartilage changes at the time of surgery primarily at the acetabulum and to a lesser degree at the femoral head. During FAI surgery the majority...

  14. Women's status and family planning: results from a focus group survey.

    Science.gov (United States)

    Gu, B; Xie, Z

    1994-02-01

    Focus group discussions were conducted in China's Pingluo County, Ningxia Hui Autonomous Region, and Sihui County, Guangdong Province among reproductive age women with only daughters, mothers-in-law, unmarried women aged 23 years and older, and women business persons and cadres. The topic of discussion was the status of women, gender differences in employment, education, marriage, family life, childbearing, and elderly care in counties that have above average fertility rates. There were also several groups of men, mixed gender groups with husbands working away from home, local family planning workers, and rural intellectuals. The findings showed that there is more access to education for girls and a higher employment rate for young women. Daughters receive education to the highest level affordable. Enrollments are equal for boys and girls. Women's employment is not challenged by husbands, and work is available in a variety of locations. Business ownership and operation is encouraged. By middle age, women generally do not work in enterprises, but at home or on contracted farmland. Equal rights within the family are generally accepted. Husbands turn over their salary to wives for family expenses. Girls receive the same care after birth as boys. Women's status is improving. Improvements in social status have also involved sacrifices. Women complained that the workload on the farm has increased with adult males away working in cities. Women bear the burden of family planning, including in some cases side effects from oral pills and recovery from sterilizations. One women remarked that there were burdens in bearing children, taking oral pills, having IUD insertions, and having induced abortions; men should bear 50% of the responsibility. The burden of women without sons is harder, and women may also feel inferior as the last in their family line. One family with 6 daughters accepted the fine of RMB 7000 yuan for having another child, which turned out to be a son. One

  15. Chernobyl NPP accident consequences cleaning up participants in Ukraine -health status epidemiologic study main results

    International Nuclear Information System (INIS)

    Buzunov, V.; Omelyanetz, N.; Strapko, N.; Ledoschuck, B.; Krasnikova, L.; Kartushin, G.

    1996-01-01

    The Epidemiologic Studies System for Chernobyl NPP Accident consequences cleaning up participants (CNPP ACCP) health status was worked out and than improving in Ukraine after the CNPP Accident. The State Register of Ukraine both with several other Registers are the organizational, methodological and informational basis here. The ACCP health status worsening ,-was registered in dynamics through the post-accidental period i.e. the nervous system, digestive system, blood circulation system, respiratory system, bone-muscular system, endocrine and genitourinary systems chronic non-tumoral pathology both with mental disorders amount increase. In cohort study the differences of morbidity formation were fixed among emergency workers with different radiation exposure doses. The dependence of leukemia morbidity on presence in 30-km zone duration was noticed, it's access manifested 5 years after the participance in ACC. The ACCP disablement increase with main reason of general somatic diseases, and annual mortality growth are registered. But that doesn't exceed the mortality rate among population of working age in Ukraine

  16. Socioeconomic status, psychological resources, and inflammatory markers: Results from the MIDUS study.

    Science.gov (United States)

    Elliot, Ari J; Chapman, Benjamin P

    2016-11-01

    Our objective was to investigate interactions of psychological resources and socioeconomic status (SES)-as well as potential gender differences and the explanatory role of childhood and adult stress exposures, health behaviors, and negative and positive affect-in predicting markers of systemic inflammation. We utilized a sample of adults from the Midlife Development in the U.S. (MIDUS) study who provided biomarker data (N = 1,152). SES was operationalized as a composite of education, income, and occupational prestige, and the psychological resources construct was operationalized as a latent factor measured with optimism, perceived control, and self-esteem. Linear regression models examined these 2 factors and their interaction in predicting interleukin-6 (IL-6) and C-reactive protein (CRP) measured on average 2 years later, as well as 3-way interactions involving gender and the impact of covariate adjustment. Psychological resources interacted with SES in men (for IL-6: p low SES was moderately attenuated upon adjustment for negative affect. Socioeconomic status might modulate the linkage between psychological resources and systemic inflammation in men. At lower levels of SES, resources may be related to lower inflammation in part through lower negative affect. Associations with higher inflammation at higher SES add to growing evidence suggesting that adaptive psychological characteristics may be associated with markers of poorer physiological function under certain conditions. (PsycINFO Database Record (c) 2016 APA, all rights reserved).

  17. Different reasons, different results: implications of migration by gender and family status.

    Science.gov (United States)

    Geist, Claudia; McManus, Patricia A

    2012-02-01

    Previous research on migration and gendered career outcomes centers on couples and rarely examines the reason for the move. The implicit assumption is usually that households migrate in response to job opportunities. Based on a two-year panel from the Current Population Survey, this article uses stated reasons for geographic mobility to compare earnings outcomes among job migrants, family migrants, and quality-of-life migrants by gender and family status. We further assess the impact of migration on couples' internal household economy. The effects of job-related moves that we find are reduced substantially in the fixed-effects models, indicating strong selection effects. Married women who moved for family reasons experience significant and substantial earnings declines. Consistent with conventional models of migration, we find that household earnings and income and gender specialization increase following job migration. Married women who are secondary earners have increased odds of reducing their labor supply following migration for job or family reasons. However, we also find that migrating women who contributed as equals to the household economy before the move are no more likely than nonmigrant women to exit work or to work part-time. Equal breadwinner status may protect women from becoming tied movers.

  18. Obesity, diabetes, hypertension, and vegetarian status among Seventh-Day Adventists in Barbados: preliminary results.

    Science.gov (United States)

    Brathwaite, Noel; Fraser, Henry S; Modeste, Naomi; Broome, Hedy; King, Rosaline

    2003-01-01

    A population-based sample of Seventh-Day Adventists was studied to determine the relationship between vegetarian status, body mass index (BMI), obesity, diabetes mellitus (DM), and hypertension, in order to gain a better understanding of factors influencing chronic diseases in Barbados. A systematic sampling from a random start technique was used to select participants for the study. A standard questionnaire was used to collect data on demographic and lifestyle characteristics, to record anthropometrics and blood pressure measurements, and to ascertain the hypertension and diabetes status of participants. The sample population consisted of 407 Barbadian Seventh-Day Adventists (SDAs), who ranged in age from 25 to 74 years. One hundred fifty-three (37.6%) participants were male, and 254 (62.4%) were female, and 43.5% were vegetarians. The prevalence rates of diabetes and hypertension were lower among long-term vegetarians, compared to non-vegetarians, and long-term vegetarians were, on average, leaner than non-vegetarians within the same cohort. A significant association was observed between a vegetarian diet and obesity (vegetarian by definition P=.04, self-reported vegetarian P=.009) in this population. Other components of the study population lifestyle should be further analyzed to determine the roles they may plan in lessening the prevalence rates of obesity, diabetes, and hypertension.

  19. Associations of Bariatric Surgery With Changes in Interpersonal Relationship Status: Results From 2 Swedish Cohort Studies.

    Science.gov (United States)

    Bruze, Gustaf; Holmin, Tobias E; Peltonen, Markku; Ottosson, Johan; Sjöholm, Kajsa; Näslund, Ingmar; Neovius, Martin; Carlsson, Lena M S; Svensson, Per-Arne

    2018-03-28

    Bariatric surgery is a life-changing treatment for patients with severe obesity, but little is known about its association with interpersonal relationships. To investigate if relationship status is altered after bariatric surgery. Changes in relationship status after bariatric surgery were examined in 2 cohorts: (1) the prospective Swedish Obese Subjects (SOS) study, which recruited patients undergoing bariatric surgery from September 1, 1987, to January 31, 2001, and compared their care with usual nonsurgical care in matched obese control participants; and (2) participants from the Scandinavian Obesity Surgery Registry (SOReg), a prospective, electronically captured register that recruited patients from January 2007 through December 2012 and selected comparator participants from the general population matched on age, sex, and place of residence. Data was collected in surgical departments and primary health care centers in Sweden. The current analysis includes data collected up until July 2015 (SOS) and December 2012 (SOReg). Data analysis was completed from June 2016 to December 2017. In the SOS study, information on relationship status was obtained from questionnaires. In the SOReg and general population cohort, information on marriage and divorce was obtained from the Swedish Total Population Registry. The SOS study included 1958 patients who had bariatric surgery (of whom 1389 [70.9%] were female) and 1912 matched obese controls (of whom 1354 [70.8%] were female) and had a median (range) follow-up of 10 (0.5-20) years. The SOReg cohort included 29 234 patients who had gastric bypass surgery (of whom 22 131 [75.6%] were female) and 283 748 comparators from the general population (of whom 214 342 [75.5%] were female), and had a median (range) follow-up of 2.9 (0.003-7.0) years. In the SOS study, the surgical patients received gastric banding (n = 368; 18.8%), vertical banded gastroplasty (n = 1331; 68.0%), or gastric bypass (n = 259; 13

  20. Code Cactus; Code Cactus

    Energy Technology Data Exchange (ETDEWEB)

    Fajeau, M; Nguyen, L T; Saunier, J [Commissariat a l' Energie Atomique, Centre d' Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)

    1966-09-01

    This code handles the following problems: -1) Analysis of thermal experiments on a water loop at high or low pressure; steady state or transient behavior; -2) Analysis of thermal and hydrodynamic behavior of water-cooled and moderated reactors, at either high or low pressure, with boiling permitted; fuel elements are assumed to be flat plates: - Flowrate in parallel channels coupled or not by conduction across plates, with conditions of pressure drops or flowrate, variable or not with respect to time is given; the power can be coupled to reactor kinetics calculation or supplied by the code user. The code, containing a schematic representation of safety rod behavior, is a one dimensional, multi-channel code, and has as its complement (FLID), a one-channel, two-dimensional code. (authors) [French] Ce code permet de traiter les problemes ci-dessous: 1. Depouillement d'essais thermiques sur boucle a eau, haute ou basse pression, en regime permanent ou transitoire; 2. Etudes thermiques et hydrauliques de reacteurs a eau, a plaques, a haute ou basse pression, ebullition permise: - repartition entre canaux paralleles, couples on non par conduction a travers plaques, pour des conditions de debit ou de pertes de charge imposees, variables ou non dans le temps; - la puissance peut etre couplee a la neutronique et une representation schematique des actions de securite est prevue. Ce code (Cactus) a une dimension d'espace et plusieurs canaux, a pour complement Flid qui traite l'etude d'un seul canal a deux dimensions. (auteurs)

  1. Status and results of the theoretical and experimental investigations on the LWR fuel rod behavior under accident conditions

    International Nuclear Information System (INIS)

    Bocek, M.; Hofmann, P.; Leistikow, S.; Class, G.; Meyder, R.; Raff, S.; Erbacher, F.; Hofmann, G.; Ihle, P.; Karb, E.; Fiege, A.

    1978-09-01

    In this report the status of knowledge is described which has been gathered up to the end of 1977 of the LWR fuel rod behavior in loss-of-coolant accidents. The majority of results indicated have been derived from studies on the fuel rod behavior performed within the framework of the Nuclear Safety Project (PNS); partly, also the results of cooperating research establishments and fm international exchange of experience are referred to. The report has been subdivided into two complete parts: Part I provides a survey of the most significant results of the theoretical and experimental research projects on fuel rod behavior. Part II describes by detailed individual presentations the status as well as the results with respect to the major central subjects. (orig.) 891 RW 892 AP [de

  2. Status of the CUORE and results from the CUORE-0 neutrinoless double beta decay experiments

    Science.gov (United States)

    Sisti, M.; Artusa, D. R.; Avignone, F. T.; Azzolini, O.; Balata, M.; Banks, T. I.; Bari, G.; Beeman, J.; Bellini, F.; Bersani, A.; Biassoni, M.; Brofferio, C.; Bucci, C.; Cai, X. Z.; Camacho, A.; Caminata, A.; Canonica, L.; Cao, X. G.; Capelli, S.; Cappelli, L.; Carbone, L.; Cardani, L.; Casali, N.; Cassina, L.; Chiesa, D.; Chott, N.; Clemenza, M.; Copello, S.; Cosmelli, C.; Cremonesi, O.; Creswick, R. J.; Cushman, J. S.; Dafinei, I.; Dally, A.; Datskov, V.; Dell'Oro, S.; Deninno, M. M.; Di Domizio, S.; di Vacri, M. L.; Drobizhev, A.; Ejzak, L.; Fang, D. Q.; Farach, H. A.; Faverzani, M.; Fernandes, G.; Ferri, E.; Ferroni, F.; Fiorini, E.; Franceschi, M. A.; Freedman, S. J.; Fujikawa, B. K.; Giachero, A.; Gironi, L.; Giuliani, A.; Gorla, P.; Gotti, C.; Gutierrez, T. D.; Haller, E. E.; Han, K.; Heeger, K. M.; Hennings-Yeomans, R.; Hickerson, K. P.; Huang, H. Z.; Kadel, R.; Keppel, G.; Kolomensky, Yu. G.; Li, Y. L.; Ligi, C.; Lim, K. E.; Liu, X.; Ma, Y. G.; Maiano, C.; Maino, M.; Martinez, M.; Maruyama, R. H.; Mei, Y.; Moggi, N.; Morganti, S.; Napolitano, T.; Nastasi, M.; Nisi, S.; Nones, C.; Norman, E. B.; Nucciotti, A.; O'Donnell, T.; Orio, F.; Orlandi, D.; Ouellet, J. L.; Pagliarone, C. E.; Pallavicini, M.; Palmieri, V.; Pattavina, L.; Pavan, M.; Pedretti, M.; Pessina, G.; Pettinacci, V.; Piperno, G.; Pira, C.; Pirro, S.; Pozzi, S.; Previtali, E.; Rosenfeld, C.; Rusconi, C.; Sala, E.; Sangiorgio, S.; Scielzo, N. D.; Smith, A. R.; Taffarello, L.; Tenconi, M.; Terranova, F.; Tian, W. D.; Tomei, C.; Trentalange, S.; Ventura, G.; Vignati, M.; Wang, B. S.; Wang, H. W.; Wielgus, L.; Wilson, J.; Winslow, L. A.; Wise, T.; Woodcraft, A.; Zanotti, L.; Zarra, C.; Zhang, G. Q.; Zhu, B. X.; Zucchelli, S.

    2016-04-01

    CUORE is a 741 kg array of TeO2 bolometers for the search of neutrinoless double beta decay of 130Te. The detector is being constructed at the Laboratori Nazionali del Gran Sasso, Italy, where it will start taking data in 2015. If the target background of 0.01 counts / (keV ṡkg ṡy) will be reached, in five years of data taking CUORE will have a 1σ half life sensitivity of 1026 y. CUORE-0 is a smaller experiment constructed to test and demonstrate the performances expected for CUORE. The detector is a single tower of 52 CUORE-like bolometers that started taking data in spring 2013. The status and perspectives of CUORE will be discussed, and the first CUORE-0 data will be presented.

  3. WP 2 Report: Integrated Status Quo and Trends Assessment in Wuxi. Overview of WP 2 Results

    Energy Technology Data Exchange (ETDEWEB)

    Dienst, Carmen; Hoeller, Samuel; Saurat, Mathieu; Schneider, Clemens; Xia-Bauer, Chun (Wuppertal Institute (Germany)); Oberheitmann, Andreas (China Environmental Research (China)); Fischer, Tom; Gemmer, Marco; Jiang Tong (China Meteorological Administration, National Climate Centre (China)); Wang Can; Wang Haoping (Tsinghua University, Research Centre for International Environmental Policy (China)); Ren Hongyan; Sui Xinying (Wuxi Low Carbon Development Research Centre (China))

    2013-04-01

    The overall project will scientifically explore the Low Carbon Future City (LCFC) concept in two case studies: the German region of Dusseldorf and the Chinese city of Wuxi, Jiangsu Province. The Wuppertal Institute together with a consortium of Chinese scientific institutes is developing integrated low carbon city strategies for the two pilot regions. The project is funded by the German Stiftung Mercator. Provided in this report, as part of the scientific analysis of the Chinese pilot region, is a comprehensive status quo and trends assessment of greenhouse gas emissions, climate change and resource use in Wuxi. It includes a GHG inventory, a business-as-usual scenario for GHG emissions, scenarios for future climate change and its impacts as well as an analysis of future resource use in the energy and buildings sector of Wuxi. Based on this assessment, the authors have selected key sectors for which low carbon scenarios as well as policy strategies will be finalised.

  4. Validation of activity determination codes and nuclide vectors by using results from processing of retired components and operational waste

    International Nuclear Information System (INIS)

    Lundgren, Klas; Larsson, Arne

    2012-01-01

    Decommissioning studies for nuclear power reactors are performed in order to assess the decommissioning costs and the waste volumes as well as to provide data for the licensing and construction of the LILW repositories. An important part of this work is to estimate the amount of radioactivity in the different types of decommissioning waste. Studsvik ALARA Engineering has performed such assessments for LWRs and other nuclear facilities in Sweden. These assessments are to a large content depending on calculations, senior experience and sampling on the facilities. The precision in the calculations have been found to be relatively high close to the reactor core. Of natural reasons the precision will decline with the distance. Even if the activity values are lower the content of hard to measure nuclides can cause problems in the long term safety demonstration of LLW repositories. At the same time Studsvik is processing significant volumes of metallic and combustible waste from power stations in operation and in decommissioning phase as well as from other nuclear facilities such as research and waste treatment facilities. Combining the unique knowledge in assessment of radioactivity inventory and the large data bank the waste processing represents the activity determination codes can be validated and the waste processing analysis supported with additional data. The intention with this presentation is to highlight how the European nuclear industry jointly could use the waste processing data for validation of activity determination codes. (authors)

  5. Impact of depressive symptoms on prosthetic status--results of the study of health in Pomerania (SHIP).

    Science.gov (United States)

    Samietz, Stefanie A; Kindler, Stefan; Schwahn, Christian; Polzer, Ines; Hoffmann, Wolfgang; Kocher, Thomas; Grabe, Hans Jörgen; Mundt, Torsten; Biffar, Reiner

    2013-05-01

    Previous investigations have confirmed that every fifth dental patient suffers from clinically significant depressive symptoms. However, the putative impact of depressive symptoms on the prosthetic status has not been addressed in these studies. The objective of this study was to investigate the association between depressive symptoms and prosthetic status based on data from the Study of Health in Pomerania (SHIP-0). Data from 2,135 participants aged 30 to 59 years were analyzed. A classification (six classes regarding the number and position of missing teeth per jaw) was used to identify the degree of prosthetic status (no/suboptimal/optimal tooth replacement). The presence of depressive symptoms was assessed with a modified version of von Zerssen's complaints scale. Screening for lifetime diagnoses of mental disorders was performed with the Composite International Diagnostic-Screener (CID-S). Multivariable logistic regressions including several confounders were calculated. A significant protective dose-response effect of depressive symptoms on prosthetic status was found only in men for the lower jaw [0-1 depressive symptoms: odds ratio (OR) = 3.84, 95 % confidence interval (CI, 1.65-8.92), p < 0.01; 2-3: OR = 2.87 (CI, 1.22-6.74), p < 0.05; reference, ≥8; adjusted for age, school education, smoking status, household income, marital status, living without a partner, risky alcohol consumption, obesity, diabetes, and physical activity]. There was no such association in women or for the upper jaw. The analyses using the CID-S confirmed these results. In the lower jaw, men with depressive symptoms had a better prosthetic status than men without depressive symptoms suggesting a higher level of concern regarding their personal health. If dentists might have an opportunity to identify men with depressive symptoms they can provide a wide range of treatment options that may enhance patients' self-esteem and contribute to the patient' well-being. Furthermore, depressive

  6. Cancer and heart attack survivors’ expectations of employment status: results from the English Longitudinal Study of Ageing

    Directory of Open Access Journals (Sweden)

    Saskia F. A. Duijts

    2017-08-01

    Full Text Available Abstract Background Sociodemographic, health- and work-related factors have been found to influence return to work in cancer survivors. It is feasible though that behavioural factors, such as expectation of being at work, could also affect work-related outcomes. Therefore, the effect of earlier identified factors and expectation of being at work on future employment status in cancer survivors was explored. To assess the degree to which these factors specifically concern cancer survivors, a comparison with heart attack survivors was made. Methods Data from the English Longitudinal Study of Ageing were used. Cancer and heart attack survivors of working age in the UK were included and followed up for 2 years. Baseline characteristics of both cancer and heart attack survivors were compared regarding employment status. Univariate and multivariate regression analyses were performed in survivors at work, and the interaction between independent variables and diagnose group was assessed. Results In cancer survivors at work (N = 159, alcohol consumption, participating in moderate or vigorous sport activities, general health and participation were univariate associated with employment status at two-year follow-up. Only fair general health (compared to very good general health remained statistically significant in the multivariate model (OR 0.31; 95% CI 0.13–0.76; p = 0.010. In heart attack survivors at work (N = 78, gender, general health and expectation of being at work were univariate associated with employment status at follow-up. Female gender (OR 0.03; 95% CI 0.00–0.57; p = 0.018 and high expectation of being at work (OR 10.68; 95% CI 1.23–93.92; p = 0.033 remained significant in the multivariate model. The influence of gender (p = 0.066 and general health (p = 0.020 regarding employment status was found to differ significantly between cancer and heart attack survivors. Conclusions When predicting future employment status in cancer

  7. Aztheca Code

    International Nuclear Information System (INIS)

    Quezada G, S.; Espinosa P, G.; Centeno P, J.; Sanchez M, H.

    2017-09-01

    This paper presents the Aztheca code, which is formed by the mathematical models of neutron kinetics, power generation, heat transfer, core thermo-hydraulics, recirculation systems, dynamic pressure and level models and control system. The Aztheca code is validated with plant data, as well as with predictions from the manufacturer when the reactor operates in a stationary state. On the other hand, to demonstrate that the model is applicable during a transient, an event occurred in a nuclear power plant with a BWR reactor is selected. The plant data are compared with the results obtained with RELAP-5 and the Aztheca model. The results show that both RELAP-5 and the Aztheca code have the ability to adequately predict the behavior of the reactor. (Author)

  8. Health status of the population in the Ukraine exposed to radiation as a result of the Chernobyl accident

    International Nuclear Information System (INIS)

    Romanenko, A.E.

    1992-01-01

    Evaluation of the health status of population exposed top radiation as a result of the Chernobyl accident is a problem of paramount importance. The results of demographic and epidemiologic surveys and clinical observations have shown that changes in the morbidity rates among children and adults at the strictly controlled districts in the Ukraine result not only from improved diagnostic service, but also from the after effects of the Chernobyl accident. A tendency to a growth of primary disease incidence among childrn and adults was established. Analysis of the results of follow-up of children has revealed an increased incidence of thyroid cancer. The accident caused an unfavourable demographic situation in the Republic

  9. Factors associated with different smoking status in European adolescents: results of the SEYLE study.

    Science.gov (United States)

    Banzer, Raphaela; Haring, C; Buchheim, A; Oehler, S; Carli, V; Wasserman, C; Kaess, M; Apter, A; Balazs, J; Bobes, J; Brunner, R; Corcoran, P; Cosman, D; Hoven, C W; Kahn, J P; Keeley, H S; Postuvan, V; Podlogar, T; Sisask, M; Värnik, A; Sarchiapone, M; Wasserman, D

    2017-11-01

    Early onset and long-term smoking are associated with physical and psychological health problems. The aim of the presented analysis was to investigate risk and influencing factors for different smoking status in a big sample of European adolescents. In the context of the "saving and empowering young lives in Europe" (SEYLE) study we surveyed 12,328 adolescents at the age of 13-17 from 11 countries. The survey took place in a school-based context using a questionnaire. Overall 58% reported the onset of ever-smoking under the age of 14 and 30.9% smoke on a daily basis. Multinomial logistic regression model showed significant positive associations between adolescent smoking and internalizing problems (suicidal behavior, direct self-injurious behavior, anxiety), externalizing problems (conduct problems, hyperactivity, substance consumption) and family problems (parental substance consumption, broken home). Our data show that smoking among adolescents is still a major public health problem and adolescents who smoke are at higher risk for mental problems. Further, adolescent smoking is associated with broken home families and parental behaviors. Therefore, early preventive measures are necessary not only for adolescents, but also for their parents.

  10. Socioeconomic status and tobacco expenditures among Moroccans: results of the "Maroc Tabagisme" survey.

    Science.gov (United States)

    Tachfouti, Nabil; Berraho, Mohammed; Elfakir, Samira; Serhier, Zineb; Elrhazi, Karima; Slama, Karen; Najjari, Chakib

    2010-01-01

    To investigate the relationship of sociodemographic and economic characteristics to tobacco expenses among Moroccan daily smokers. Cross-sectional ("Maroc Tabagisme" Survey) study. Random sample of 9195 subjects representative of the Moroccan population. Household subjects 15 years and older. Data were collected from selected households using a questionnaire about smoking, educational level, occupation, and household monthly income. Associations between sociodemographic and economic characteristics, smoking status, and tobacco expenses were assessed by multivariate analysis in a sample of 5959 respondents who provided details about their family income. Of 5959 participants, 28.5% of men and 2.8% of women were daily smokers. Compared with students, the odds of daily smoking were higher among blue-collar workers (odds ratio, 2.66). Tobacco expenses increased with higher family monthly income (p < .001). Moreover, smokers whose family monthly income was less than 1000 Moroccan dirham (MAD) spent 50.9% on tobacco, while those with family monthly income of 6000 MAD or higher spent 13.0 %on tobacco. There was a strong association between tobacco expenses and sociodemographic and economic characteristics. Among households with low monthly income, up to half of the monthly income is spent on tobacco.

  11. Current educational status of paediatric rheumatology in Europe: the results of PReS survey.

    Science.gov (United States)

    Demirkaya, E; Ozen, S; Türker, T; Kuis, W; Saurenmann, R K

    2009-01-01

    To understand the status of education and problems in paediatric rheumatology practice in Europe, through a survey. A 26-item questionnaire was conducted during the 14th Congress of the Paediatric Rheumatology European Society in Istanbul, 2007. Physicians who were practicing or studying within the field of paediatric rheumatology for at least one year were included in the survey. One hundred and twenty eight physicians, 79 paediatric rheumatologists (including 5 paediatric immunologists and 10 paediatric nephrologists), 34 paediatric rheumatology fellows and 15 adult rheumatologists completed the survey. The physicians were from: Europe 95 (81.9%), South America 12 (10.4%), Middle East 5 (4.3%), Asia 2 (1.7%), Africa 2 (1.7%). The duration of training for paediatric rheumatology ranged between 1-5 years (mean: 3.12+/-1.11). Sixty physicians scored their education as unsatisfactory and among those, 48 physicians were from Europe. Physicians reported good skills in the following items; intraarticular injections (83.3%); soft tissue injections (47.6%); evaluation of radiographs (67.5%); whereas competence in the evaluation of computed tomography/magnetic resonance imaging (30.5%); and musculoskeletal sonography (16.7%) was much lower. A need for improved basic science and rotations among relevant fields were specifically expressed. Being a relatively new speciality in the realm of paediatrics, paediatric rheumatology education at the European level needs to be further discussed, revised and uniformed.

  12. Effects of Secondary Circuit Modeling on Results of Pressurized Water Reactor Main Steam Line Break Benchmark Calculations with New Coupled Code TRAB-3D/SMABRE

    International Nuclear Information System (INIS)

    Daavittila, Antti; Haemaelaeinen, Anitta; Kyrki-Rajamaeki, Riitta

    2003-01-01

    All of the three exercises of the Organization for Economic Cooperation and Development/Nuclear Regulatory Commission pressurized water reactor main steam line break (PWR MSLB) benchmark were calculated at VTT, the Technical Research Centre of Finland. For the first exercise, the plant simulation with point-kinetic neutronics, the thermal-hydraulics code SMABRE was used. The second exercise was calculated with the three-dimensional reactor dynamics code TRAB-3D, and the third exercise with the combination TRAB-3D/SMABRE. VTT has over ten years' experience of coupling neutronic and thermal-hydraulic codes, but this benchmark was the first time these two codes, both developed at VTT, were coupled together. The coupled code system is fast and efficient; the total computation time of the 100-s transient in the third exercise was 16 min on a modern UNIX workstation. The results of all the exercises are similar to those of the other participants. In order to demonstrate the effect of secondary circuit modeling on the results, three different cases were calculated. In case 1 there is no phase separation in the steam lines and no flow reversal in the aspirator. In case 2 the flow reversal in the aspirator is allowed, but there is no phase separation in the steam lines. Finally, in case 3 the drift-flux model is used for the phase separation in the steam lines, but the aspirator flow reversal is not allowed. With these two modeling variations, it is possible to cover a remarkably broad range of results. The maximum power level reached after the reactor trip varies from 534 to 904 MW, the range of the time of the power maximum being close to 30 s. Compared to the total calculated transient time of 100 s, the effect of the secondary side modeling is extremely important

  13. NSURE code

    International Nuclear Information System (INIS)

    Rattan, D.S.

    1993-11-01

    NSURE stands for Near-Surface Repository code. NSURE is a performance assessment code. developed for the safety assessment of near-surface disposal facilities for low-level radioactive waste (LLRW). Part one of this report documents the NSURE model, governing equations and formulation of the mathematical models, and their implementation under the SYVAC3 executive. The NSURE model simulates the release of nuclides from an engineered vault, their subsequent transport via the groundwater and surface water pathways tot he biosphere, and predicts the resulting dose rate to a critical individual. Part two of this report consists of a User's manual, describing simulation procedures, input data preparation, output and example test cases

  14. Present Status And First Results of the Final Focus Beam Line at the KEK Accelerator Test Facility

    International Nuclear Information System (INIS)

    2010-01-01

    ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  15. Present status and first results of the final focus beam line at the KEK Accelerator Test Facility

    CERN Document Server

    Bambade, P; Amann, J; Angal-Kalinin, D; Apsimon, R; Araki, S; Aryshev, A; Bai, S; Bellomo, P; Bett, D; Blair, G; Bolzon, B; Boogert, S; Boorman, G; Burrows, P N; Christian, G; Coe, P; Constance, B; Delahaye, J P; Deacon, L; Elsen, E; Faus-Golfe, A; Fukuda, M; Gao, J; Geffroy, N; Gianfelice-Wendt, E; Guler, H; Hayano, H; Heo, A Y; Honda, Y; Huang, J Y; Hwang, W H; Iwashita, Y; Jeremie, A; Jones, J; Kamiya, Y; Karataev, P; Kim, E S; Kim, H S; Kim, S H; Komamiya, S; Kubo, K; Kume, T; Kuroda, S; Lam, B; Lyapin, A; Masuzawa, M; McCormick, D; Molloy, S; Naito, T; Nakamura, T; Nelson, J; Okamoto, D; Okugi, T; Oroku, M; Park, Y J; Parker, B; Paterson, E; Perry, C; Pivi, M; Raubenheimer, T; Renier, Y; Resta-Lopez, J; Rimbault, C; Ross, M; Sanuki, T; Scarfe, A; Schulte, D; Seryi, A; Spencer, C; Suehara, T; Sugahara, R; Swinson, C; Takahashi, T; Tauchi, T; Terunuma, N; Tomas, R; Urakawa, J; Urner, D; Verderi, M; Wang, M H; Warden, M; Wendt, M; White, G; Wittmer, W; Wolski, A; Woodley, M; Yamaguchi, Y; Yamanaka, T; Yan, Y; Yoda, H; Yokoya, K; Zhou, F; Zimmermann, F; 10.1103/PhysRevSTAB.13.042801

    2010-01-01

    ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  16. Uplink Coding

    Science.gov (United States)

    Andrews, Ken; Divsalar, Dariush; Dolinar, Sam; Moision, Bruce; Hamkins, Jon; Pollara, Fabrizio

    2007-01-01

    This slide presentation reviews the objectives, meeting goals and overall NASA goals for the NASA Data Standards Working Group. The presentation includes information on the technical progress surrounding the objective, short LDPC codes, and the general results on the Pu-Pw tradeoff.

  17. The Status of Honey Bee Health in Italy: Results from the Nationwide Bee Monitoring Network.

    Directory of Open Access Journals (Sweden)

    Claudio Porrini

    Full Text Available In Italy a nation-wide monitoring network was established in 2009 in response to significant honey bee colony mortality reported during 2008. The network comprised of approximately 100 apiaries located across Italy. Colonies were sampled four times per year, in order to assess the health status and to collect samples for pathogen, chemical and pollen analyses. The prevalence of Nosema ceranae ranged, on average, from 47-69% in 2009 and from 30-60% in 2010, with strong seasonal variation. Virus prevalence was higher in 2010 than in 2009. The most widespread viruses were BQCV, DWV and SBV. The most frequent pesticides in all hive contents were organophosphates and pyrethroids such as coumaphos and tau-fluvalinate. Beeswax was the most frequently contaminated hive product, with 40% of samples positive and 13% having multiple residues, while 27% of bee-bread and 12% of honey bee samples were contaminated. Colony losses in 2009/10 were on average 19%, with no major differences between regions of Italy. In 2009, the presence of DWV in autumn was positively correlated with colony losses. Similarly, hive mortality was higher in BQCV infected colonies in the first and second visits of the year. In 2010, colony losses were significantly related to the presence of pesticides in honey bees during the second sampling period. Honey bee exposure to poisons in spring could have a negative impact at the colony level, contributing to increase colony mortality during the beekeeping season. In both 2009 and 2010, colony mortality rates were positively related to the percentage of agricultural land surrounding apiaries, supporting the importance of land use for honey bee health.

  18. Automatic examination of nuclear reactor vessels with focused search units. Status and typical application to inspections performed in accordance with ASME code

    International Nuclear Information System (INIS)

    Verger, B.; Saglio, R.

    1981-05-01

    The use of focused search units in nuclear reactor vessel examinations has significantly increased the capability of flaw indication detection and characterization. These search units especially allow a more accurate sizing of indications and a more efficient follow up of their history. In this aspect, they are a unique tool in the area of safety and reliability of installations. It was this type of search unit which was adopted to perform the examinations required within the scope of inservice inspections of all P.W.R. reactors of the French nuclear program. This paper summarizes the results gathered through the 4l examinations performed over the last five years. A typical application of focused search units in automated inspections performed in accordance with ASME code requirements on P.W.R. nuclear reactor vessels is then described

  19. Implementation of the International Code of Practice on Dosimetry in Diagnostic Radiology (TRS 457): Review of Test Results

    International Nuclear Information System (INIS)

    2011-01-01

    In 2007, the IAEA published Dosimetry in Diagnostic Radiology: An International Code of Practice (IAEA Technical Reports Series No. 457). This publication recommends procedures for calibration and dosimetric measurement for the attainment of standardized dosimetry. It also addresses requirements both in standards dosimetry laboratories, especially Secondary Standards Dosimetry Laboratories (SSDLs), and in clinical centres for radiology, as found in most hospitals. The implementation of TRS No. 457 decreases the uncertainty in the dosimetry of diagnostic radiology beams and provides Member States with a unified and consistent framework for dosimetry in diagnostic radiology, which previously did not exist. A coordinated research project (CRP E2.10.06) was established in order to provide practical guidance to professionals at SSDLs and to clinical medical physicists on the implementation of TRS No. 457. This includes the calibration of radiological dosimetry instrumentation, the dissemination of calibration coefficients to clinical centres and the establishment of dosimetric measurement processes in clinical settings. The main goals of the CRP were to: Test the procedures recommended in TRS No. 457 for calibration of radiation detectors in different types of diagnostic beams and measuring instruments for varying diagnostic X ray modalities; Test the clinical dosimetry procedures, including the use of phantoms and patient dose surveys; Report on the practical implementation of TRS No. 457 at both SSDLs and hospital sites. Testing of TRS No. 457 was performed by a group of medical physicists from hospitals and SSDLs from various institutions worldwide

  20. Current status of iodine intake in Croatia--the results of 2009 survey.

    Science.gov (United States)

    Kusić, Zvonko; Jukić, Tomislav; Rogan, Suncica Andreja; Juresa, Vesna; Dabelić, Nina; Stanicić, Josip; Borić, Marta; Lukinac, Ljerka; Mihaljević, Ivan; Punda, Ante; Smokvina, Aleksandar; Topalović, Zlatko; Katalenić, Marijan

    2012-03-01

    In 1996, due to persistence of mild to moderate iodine deficiency, new law on obligatory salt iodination with 25 mg of potassium iodide (KI) per kg of salt was implemented in Croatia. Along with a new law, a new program for monitoring of iodine prophylaxis was implemented. Investigations of goiter and iodine intake performed in 2002, demonstrated sufficient iodine intake in Croatia with overall median of urinary iodine concentration (UIC) for schoolchildren in Croatia of 140 microg/L. In 2002, thyroid volumes (TV) measured by ultrasound in schoolchildren from all four geographic regions of Croatia were for the first time within the normal range according to ICCIDD reference values. Nowadays, Croatia is internationally recognized as iodine sufficient country. The aim of the present study was to assess current status of iodine intake in Croatia. The investigation was carried out in 2009. A total of 386 schoolchildren aged 7-10 years from all four major geographic regions of Croatia, 103 euthyroid pregnant women and 36 women of child-bearing age from Zagreb, the capital, were included in the survey. Urinary iodine concentration (UIC) was measured in all participants. Thyroid volumes were measured by ultrasound in schoolchildren from the capital of Zagreb (N = 101) and the village of Rude (N = 56). In the time period 2002-2009, the content of KI was analyzed in 384 salt samples from Croatian salt plants and samples of imported salt. An overall median UIC for schoolchildren in Croatia was 248 microg/L. Median UIC in pregnant women was 159 microg/L, with 50% of samples below and under 150 microg/L. Median UIC in women of child-bearing age was 136 microg/L. Thyroid volumes in schoolchildren were within the normal range according to the new reference values. Mean value of KI/kg of salt in samples from Croatian salt plants was 25.5 mg/kg and 24.9 mg/kg in samples of imported salt. A total of 72/384 (18.8%) of salt samples didn't corresponded to the Croatian law on

  1. The Aster code; Code Aster

    Energy Technology Data Exchange (ETDEWEB)

    Delbecq, J.M

    1999-07-01

    The Aster code is a 2D or 3D finite-element calculation code for structures developed by the R and D direction of Electricite de France (EdF). This dossier presents a complete overview of the characteristics and uses of the Aster code: introduction of version 4; the context of Aster (organisation of the code development, versions, systems and interfaces, development tools, quality assurance, independent validation); static mechanics (linear thermo-elasticity, Euler buckling, cables, Zarka-Casier method); non-linear mechanics (materials behaviour, big deformations, specific loads, unloading and loss of load proportionality indicators, global algorithm, contact and friction); rupture mechanics (G energy restitution level, restitution level in thermo-elasto-plasticity, 3D local energy restitution level, KI and KII stress intensity factors, calculation of limit loads for structures), specific treatments (fatigue, rupture, wear, error estimation); meshes and models (mesh generation, modeling, loads and boundary conditions, links between different modeling processes, resolution of linear systems, display of results etc..); vibration mechanics (modal and harmonic analysis, dynamics with shocks, direct transient dynamics, seismic analysis and aleatory dynamics, non-linear dynamics, dynamical sub-structuring); fluid-structure interactions (internal acoustics, mass, rigidity and damping); linear and non-linear thermal analysis; steels and metal industry (structure transformations); coupled problems (internal chaining, internal thermo-hydro-mechanical coupling, chaining with other codes); products and services. (J.S.)

  2. Results of Surveys for Special Status Reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory

    Energy Technology Data Exchange (ETDEWEB)

    Woollett, J J

    2008-09-18

    The purpose of this report is to present the results of a live-trapping and visual surveys for special status reptiles at the Site 300 Facilities of Lawrence Livermore National Laboratory (LLNL). The survey was conducted under the authority of the Federal recovery permit of Swaim Biological Consulting (PRT-815537) and a Memorandum of Understanding issued from the California Department of Fish and Game. Site 300 is located between Livermore and Tracy just north of Tesla road (Alameda County) and Corral Hollow Road (San Joaquin County) and straddles the Alameda and San Joaquin County line (Figures 1 and 2). It encompasses portions of the USGS 7.5 minute Midway and Tracy quadrangles (Figure 2). Focused surveys were conducted for four special status reptiles including the Alameda whipsnake (Masticophis lateralis euryxanthus), the San Joaquin Whipsnake (Masticophis Hagellum ruddock), the silvery legless lizard (Anniella pulchra pulchra), and the California horned lizard (Phrynosoma coronanum frontale).

  3. Edaphic macrofauna as biological indicator of the conservation/disturbance status of soil. Results obtained in Cuba

    International Nuclear Information System (INIS)

    Cabrera, Grisel

    2012-01-01

    In order to predict the degradation status of a soil, a group of variables comprising its physical, chemical and/or biological properties is used. Macrofauna, which includes soil invertebrates higher than 2 mm of diameter, is a biological component that can be used for such purpose. Its taxonomic richness as well as its density, biomass and functional composition change depending on the effect of diverse land uses and managements. This review reaffirms that the macrofauna characteristics and the results obtained, mainly in Cuba, about its variation in ecosystems with different anthropization levels, support the potential use of this fauna as biological indicator of the soil's conservation status. Future studies should consider a lower taxonomic level in the identification of macrofauna, and relate its taxonomic and functional composition to the climate and pedological factors. (author)

  4. The Modern U.S. High School Astronomy Course, Its Status and Makeup II: Additional Results

    Science.gov (United States)

    Krumenaker, Larry

    2009-01-01

    A postal survey of high school astronomy teachers strongly confirms many results of an earlier electronic survey. Additional and new results include a measure of the level of inquiry (more structured inquiry and teacher-led) in the classroom as well as data showing that more emphasis is given to traditional topics than to contemporary astronomy…

  5. Review on the present status of the German Risk Study: overall results

    International Nuclear Information System (INIS)

    Heuser, F.W.

    1982-01-01

    An overview on the most important results of the German Risk Study (Phase A) is given. Besides plant design analysis, the description mainly refers to core melt accidents, radioactive release and accidental consequences depending on various types of containment failure. Thereby some differences or results compared to WASH 1400 are discussed

  6. Preliminary results of the seventh three-dimensional AER dynamic benchmark problem calculation. Solution with DYN3D and RELAP5-3D codes

    International Nuclear Information System (INIS)

    Bencik, M.; Hadek, J.

    2011-01-01

    The paper gives a brief survey of the seventh three-dimensional AER dynamic benchmark calculation results received with the codes DYN3D and RELAP5-3D at Nuclear Research Institute Rez. This benchmark was defined at the twentieth AER Symposium in Hanassari (Finland). It is focused on investigation of transient behaviour in a WWER-440 nuclear power plant. Its initiating event is opening of the main isolation valve and re-connection of the loop with its main circulation pump in operation. The WWER-440 plant is at the end of the first fuel cycle and in hot full power conditions. Stationary and burnup calculations were performed with the code DYN3D. Transient calculation was made with the system code RELAP5-3D. The two-group homogenized cross sections library HELGD05 created by HELIOS code was used for the generation of reactor core neutronic parameters. The detailed six loops model of NPP Dukovany was adopted for the seventh AER dynamic benchmark purposes. The RELAP5-3D full core neutronic model was coupled with 49 core thermal-hydraulic channels and 8 reflector channels connected with the three-dimensional model of the reactor vessel. The detailed nodalization of reactor downcomer, lower and upper plenum was used. Mixing in lower and upper plenum was simulated. The first part of paper contains a brief characteristic of RELAP5-3D system code and a short description of NPP input deck and reactor core model. The second part shows the time dependencies of important global and local parameters. (Authors)

  7. Developing a methodology for the evaluation of results uncertainties in CFD codes; Desarrollo de una Metodologia para la Evaluacion de Incertidumbres en los Resultados de Codigos de CFD

    Energy Technology Data Exchange (ETDEWEB)

    Munoz-cobo, J. L.; Chiva, S.; Pena, C.; Vela, E.

    2014-07-01

    In this work the development of a methodology is studied to evaluate the uncertainty in the results of CFD codes and is compatible with the VV-20 standard Standard for Verification and Validation in CFD and Heat Transfer {sup ,} developed by the Association of Mechanical Engineers ASME . Similarly, the alternatives are studied for obtaining existing uncertainty in the results to see which is the best choice from the point of view of implementation and time. We have developed two methods for calculating uncertainty of the results of a CFD code, the first method based on the use of techniques of Monte-Carlo for the propagation of uncertainty in this first method we think it is preferable to use the statistics of the order to determine the number of cases to execute the code, because this way we can always determine the confidence interval desired level of output quantities. The second type of method we have developed is based on non-intrusive polynomial chaos. (Author)

  8. Marital status and survival in patients with rectal cancer: An analysis of the Surveillance, Epidemiology and End Results (SEER) database.

    Science.gov (United States)

    Wang, Xiangyang; Cao, Weilan; Zheng, Chenguo; Hu, Wanle; Liu, Changbao

    2018-06-01

    Marital status has been validated as an independent prognostic factor for survival in several cancer types, but is controversial in rectal cancer (RC). The objective of this study was to investigate the impact of marital status on the survival outcomes of patients with RC. We extracted data of 27,498 eligible patients diagnosed with RC between 2004 and 2009 from the Surveillance, Epidemiology and End Results (SEER) database. Patients were categorized into married, never married, divorced/separated and widowed groups.We used Chi-square tests to compare characteristics of patients with different marital status.Rectal cancer specific survival was compared using the Kaplan-Meier method,and multivariate Cox regression analyses was used to analyze the survival outcome risk factors in different marital status. The widowed group had the highest percentage of elderly patients and women,higher proportion of adenocarcinomas, and more stage I/II in tumor stage (P married group (76.7% VS 85.4%). Compared with the married patients, the never married (HR 1.40), widowed (HR 1.61,) and divorced/separated patients (HR 1.16) had an increased overall 5-year mortality. A further analysis showed that widowed patients had an increased overall 5-year cause-specific survival(CSS) compared with married patients at stage I(HR 1.92),stage II (HR 1.65),stage III (HR 1.73),and stage IV (HR 1.38). Our study showed marriage was associated with better outcomes of RC patients, but unmarried RC patients, especially widowed patients,are at greater risk of cancer specific mortality. Copyright © 2018 Elsevier Ltd. All rights reserved.

  9. Application of MELCOR Code to a French PWR 900 MWe Severe Accident Sequence and Evaluation of Models Performance Focusing on In-Vessel Thermal Hydraulic Results

    International Nuclear Information System (INIS)

    De Rosa, Felice

    2006-01-01

    In the ambit of the Severe Accident Network of Excellence Project (SARNET), funded by the European Union, 6. FISA (Fission Safety) Programme, one of the main tasks is the development and validation of the European Accident Source Term Evaluation Code (ASTEC Code). One of the reference codes used to compare ASTEC results, coming from experimental and Reactor Plant applications, is MELCOR. ENEA is a SARNET member and also an ASTEC and MELCOR user. During the first 18 months of this project, we performed a series of MELCOR and ASTEC calculations referring to a French PWR 900 MWe and to the accident sequence of 'Loss of Steam Generator (SG) Feedwater' (known as H2 sequence in the French classification). H2 is an accident sequence substantially equivalent to a Station Blackout scenario, like a TMLB accident, with the only difference that in H2 sequence the scram is forced to occur with a delay of 28 seconds. The main events during the accident sequence are a loss of normal and auxiliary SG feedwater (0 s), followed by a scram when the water level in SG is equal or less than 0.7 m (after 28 seconds). There is also a main coolant pumps trip when ΔTsat < 10 deg. C, a total opening of the three relief valves when Tric (core maximal outlet temperature) is above 603 K (330 deg. C) and accumulators isolation when primary pressure goes below 1.5 MPa (15 bar). Among many other points, it is worth noting that this was the first time that a MELCOR 1.8.5 input deck was available for a French PWR 900. The main ENEA effort in this period was devoted to prepare the MELCOR input deck using the code version v.1.8.5 (build QZ Oct 2000 with the latest patch 185003 Oct 2001). The input deck, completely new, was prepared taking into account structure, data and same conditions as those found inside ASTEC input decks. The main goal of the work presented in this paper is to put in evidence where and when MELCOR provides good enough results and why, in some cases mainly referring to its

  10. Associations between subjective social status and DSM-IV mental disorders: results from the World Mental Health surveys.

    Science.gov (United States)

    Scott, Kate M; Al-Hamzawi, Ali Obaid; Andrade, Laura H; Borges, Guilherme; Caldas-de-Almeida, Jose Miguel; Fiestas, Fabian; Gureje, Oye; Hu, Chiyi; Karam, Elie G; Kawakami, Norito; Lee, Sing; Levinson, Daphna; Lim, Carmen C W; Navarro-Mateu, Fernando; Okoliyski, Michail; Posada-Villa, Jose; Torres, Yolanda; Williams, David R; Zakhozha, Victoria; Kessler, Ronald C

    2014-12-01

    The inverse social gradient in mental disorders is a well-established research finding with important implications for causal models and policy. This research has used traditional objective social status (OSS) measures, such as educational level, income, and occupation. Recently, subjective social status (SSS) measurement has been advocated to capture the perception of relative social status, but to our knowledge, there have been no studies of associations between SSS and mental disorders. To estimate associations of SSS with DSM-IV mental disorders in multiple countries and to investigate whether the associations persist after comprehensive adjustment of OSS. Face-to-face cross-sectional household surveys of community-dwelling adults in 18 countries in Asia, South Pacific, the Americas, Europe, and the Middle East (N=56,085). Subjective social status was assessed with a self-anchoring scale reflecting respondent evaluations of their place in the social hierarchies of their countries in terms of income, educational level, and occupation. Scores on the 1 to 10 SSS scale were categorized into 4 categories: low (scores 1-3), low-mid (scores 4-5), high-mid (scores 6-7), and high (scores 8-10). Objective social status was assessed with a wide range of fine-grained objective indicators of income, educational level, and occupation. The Composite International Diagnostic Interview assessed the 12-month prevalence of 16 DSM-IV mood, anxiety, and impulse control disorders. The weighted mean survey response rate was 75.2% (range, 55.1%-97.2%). Graded inverse associations were found between SSS and all 16 mental disorders. Gross odds ratios (lowest vs highest SSS categories) in the range of 1.8 to 9.0 were attenuated but remained significant for all 16 disorders (odds ratio, 1.4-4.9) after adjusting for OSS indicators. This pattern of inverse association between SSS and mental disorders was significant in 14 of 18 individual countries, and in low-, middle-, and high

  11. Computer codes for safety analysis

    International Nuclear Information System (INIS)

    Holland, D.F.

    1986-11-01

    Computer codes for fusion safety analysis have been under development in the United States for about a decade. This paper will discuss five codes that are currently under development by the Fusion Safety Program. The purpose and capability of each code will be presented, a sample given, followed by a discussion of the present status and future development plans

  12. Acoustic detection of particles, the RAP experiment: present status and results

    International Nuclear Information System (INIS)

    Bassan, M; Buonomo, B; Coccia, E; Blair, D; D'Antonio, S; Monache, G Delle; Gioacchino, D Di; Fafone, V; Ligi, C; Marini, A; Mazzitelli, G; Modestino, G; Pizzella, G; Quintieri, L; Roccella, S; Rocchi, A; Ronga, F; Tripodi, P; Valente, P

    2006-01-01

    Cosmic ray events with rate and energy much higher than expected were detected by the ultracryogenic gravitational antenna Nautilus located at the Laboratori Nazionali di Frascati, when it was operating in superconducting state. Mechanisms related to the superconductivity state of the material could be involved in such a way to enhance the conversion efficiency of the particle energy into vibrational energy of the detector. The RAP experiment has the aim to study the mechanical response of a small metallic resonant bar to short pulses of high energy electron beam, investigating the response of the bar both in normal and in superconducting state. The results obtained for an Al5056 bar down to a temperature of 4 K are reported and the preliminary results for a niobium bar at temperature below and above the superconducting-normal transition are also discussed

  13. The North American Regional Climate Change Assessment Program (NARCCAP): Status and results

    Science.gov (United States)

    Arritt, R.

    2009-04-01

    NARCCAP is an international program that is generating projections of climate change for the U.S., Canada, and northern Mexico at decision-relevant regional scales. NARCCAP uses multiple limited-area regional climate models (RCMs) nested within multiple atmosphere-ocean general circulation models (AOGCMs). The use of multiple regional and global models allows us to investigate the uncertainty in model responses to future emissions (here, the A2 SRES scenario). The project also includes global time-slice experiments at the same discretization (50 km) using the GFDL atmospheric model (AM2.1) and the NCAR atmospheric model (CAM3). Phase I of the experiment uses the regional models nested within reanalysis in order to establish uncertainty attributable to the RCMs themselves. Phase II of the project then nests the RCMs within results from the current and future runs of the AOGCMs to explore the cascade of uncertainty from the global to the regional models. Phase I has been completed and the results to be shown include findings that spectral nudging is beneficial in some regions but not in others. Phase II is nearing completion and some preliminary results will be shown.

  14. Status report on the Zagreb Radiocarbon Laboratory - AMS and LSC results of VIRI intercomparison samples

    Science.gov (United States)

    Sironić, Andreja; Krajcar Bronić, Ines; Horvatinčić, Nada; Barešić, Jadranka; Obelić, Bogomil; Felja, Igor

    2013-01-01

    A new line for preparation of the graphite samples for 14C dating by Accelerator Mass Spectrometry (AMS) in the Zagreb Radiocarbon Laboratory has been validated by preparing graphite from various materials distributed within the Fifth International Radiocarbon Intercomparison (VIRI) study. 14C activity of prepared graphite was measured at the SUERC AMS facility. The results are statistically evaluated by means of the z-score and u-score values. The mean z-score value of 28 prepared VIRI samples is (0.06 ± 0.23) showing excellent agreement with the consensus VIRI values. Only one sample resulted in the u-score value above the limit of acceptability (defined for the confidence interval of 99%) and this was probably caused by a random contamination of the graphitization rig. After the rig had been moved to the new adapted and isolated room, all u-score values laid within the acceptable limits. Our LSC results of VIRI intercomparison samples are also presented and they are all accepted according to the u-score values.

  15. Status report on the Zagreb Radiocarbon Laboratory – AMS and LSC results of VIRI intercomparison samples

    International Nuclear Information System (INIS)

    Sironić, Andreja; Krajcar Bronić, Ines; Horvatinčić, Nada; Barešić, Jadranka; Obelić, Bogomil; Felja, Igor

    2013-01-01

    A new line for preparation of the graphite samples for 14 C dating by Accelerator Mass Spectrometry (AMS) in the Zagreb Radiocarbon Laboratory has been validated by preparing graphite from various materials distributed within the Fifth International Radiocarbon Intercomparison (VIRI) study. 14 C activity of prepared graphite was measured at the SUERC AMS facility. The results are statistically evaluated by means of the z-score and u-score values. The mean z-score value of 28 prepared VIRI samples is (0.06 ± 0.23) showing excellent agreement with the consensus VIRI values. Only one sample resulted in the u-score value above the limit of acceptability (defined for the confidence interval of 99%) and this was probably caused by a random contamination of the graphitization rig. After the rig had been moved to the new adapted and isolated room, all u-score values laid within the acceptable limits. Our LSC results of VIRI intercomparison samples are also presented and they are all accepted according to the u-score values.

  16. Status report on the Zagreb Radiocarbon Laboratory - AMS and LSC results of VIRI intercomparison samples

    Energy Technology Data Exchange (ETDEWEB)

    Sironic, Andreja [Department of Experimental Physics, Ruder Boskovic Institute, Bijenicka 54, 10000 Zagreb (Croatia); Krajcar Bronic, Ines, E-mail: krajcar@irb.hr [Department of Experimental Physics, Ruder Boskovic Institute, Bijenicka 54, 10000 Zagreb (Croatia); Horvatincic, Nada; Baresic, Jadranka; Obelic, Bogomil; Felja, Igor [Department of Experimental Physics, Ruder Boskovic Institute, Bijenicka 54, 10000 Zagreb (Croatia)

    2013-01-15

    A new line for preparation of the graphite samples for {sup 14}C dating by Accelerator Mass Spectrometry (AMS) in the Zagreb Radiocarbon Laboratory has been validated by preparing graphite from various materials distributed within the Fifth International Radiocarbon Intercomparison (VIRI) study. {sup 14}C activity of prepared graphite was measured at the SUERC AMS facility. The results are statistically evaluated by means of the z-score and u-score values. The mean z-score value of 28 prepared VIRI samples is (0.06 {+-} 0.23) showing excellent agreement with the consensus VIRI values. Only one sample resulted in the u-score value above the limit of acceptability (defined for the confidence interval of 99%) and this was probably caused by a random contamination of the graphitization rig. After the rig had been moved to the new adapted and isolated room, all u-score values laid within the acceptable limits. Our LSC results of VIRI intercomparison samples are also presented and they are all accepted according to the u-score values.

  17. MCNP code

    International Nuclear Information System (INIS)

    Cramer, S.N.

    1984-01-01

    The MCNP code is the major Monte Carlo coupled neutron-photon transport research tool at the Los Alamos National Laboratory, and it represents the most extensive Monte Carlo development program in the United States which is available in the public domain. The present code is the direct descendent of the original Monte Carlo work of Fermi, von Neumaum, and Ulam at Los Alamos in the 1940s. Development has continued uninterrupted since that time, and the current version of MCNP (or its predecessors) has always included state-of-the-art methods in the Monte Carlo simulation of radiation transport, basic cross section data, geometry capability, variance reduction, and estimation procedures. The authors of the present code have oriented its development toward general user application. The documentation, though extensive, is presented in a clear and simple manner with many examples, illustrations, and sample problems. In addition to providing the desired results, the output listings give a a wealth of detailed information (some optional) concerning each state of the calculation. The code system is continually updated to take advantage of advances in computer hardware and software, including interactive modes of operation, diagnostic interrupts and restarts, and a variety of graphical and video aids

  18. XS data recalculation with HELIOS-1.8 and statistical investigation of C-PORCA and GEPETTO codes results based on in-core measurements

    International Nuclear Information System (INIS)

    Szabo, Sandor Patai; Parko, Tamas; Pos, Istvan

    2005-01-01

    As a part of the power up rate process at the NPP PAKS some reactor physical model development and testing were fulfilled. The model development mainly focussed on the more flexible handling of assemblies with different initial material compositions in axial direction and the renewing of few group XS data storage. Parallel with this modification all of the few group XS data were recalculated by the newest HELIOS version.To satisfy the correct and accurate off-line and on-line reactor physical analysis of reactor cores a comprehensive investigation of the relevant codes has been done. During this process the accuracy of applied models was determined and their appropriateness was also demonstrated. The paper shows the main features of modifications and code developments and basic results of tests (Authors)

  19. Model description of CHERPAC (Chalk River Environmental Research Pathways Analysis Code); results of testing with post-Chernobyl data from Finland

    International Nuclear Information System (INIS)

    Peterson, S-R.

    1994-07-01

    CHERPAC (Chalk River Environmental Research Pathways Analysis Code), a time-dependent code for assessing doses from accidental and routine releases of radionuclides, has been under development since 1987. A complete model description is provide here with equations, parameter values, assumptions and information on parameter distributions for uncertainty analysis. Concurrently, CHERPAC has been used to participate in the two internal model validation exercises BIOMOVS (BIOspheric MOdel Validation Study) and VAMP (VAlidation of Assessment Model Predictions, a co-ordinated research program of the International Atomic Energy Agency). CHERPAC has been tested for predictions of concentrations of 137 Cs in foodstuffs, body burden and dose over time using data collected after the Chernobyl accident of 1986 April. CHERPAC's results for the recent VAMP scenario for southern Finland are particularly accurate and should represent what the code can do under Canadian conditions. CHERPAC's predictions are compared with the observations from Finland for four and one-half years after the accident as well as with the results of the other participating models from nine countries. (author). 18 refs., 23 figs., 2 appendices

  20. Model description of CHERPAC (Chalk River Environmental Research Pathways Analysis Code); results of testing with post-Chernobyl data from Finland

    Energy Technology Data Exchange (ETDEWEB)

    Peterson, S-R

    1994-07-01

    CHERPAC (Chalk River Environmental Research Pathways Analysis Code), a time-dependent code for assessing doses from accidental and routine releases of radionuclides, has been under development since 1987. A complete model description is provide here with equations, parameter values, assumptions and information on parameter distributions for uncertainty analysis. Concurrently, CHERPAC has been used to participate in the two internal model validation exercises BIOMOVS (BIOspheric MOdel Validation Study) and VAMP (VAlidation of Assessment Model Predictions, a co-ordinated research program of the International Atomic Energy Agency). CHERPAC has been tested for predictions of concentrations of {sup 137}Cs in foodstuffs, body burden and dose over time using data collected after the Chernobyl accident of 1986 April. CHERPAC`s results for the recent VAMP scenario for southern Finland are particularly accurate and should represent what the code can do under Canadian conditions. CHERPAC`s predictions are compared with the observations from Finland for four and one-half years after the accident as well as with the results of the other participating models from nine countries. (author). 18 refs., 23 figs., 2 appendices.

  1. TSOAK-M1: a computer code to determine tritium reaction/adsorption/release parameters from experimental results of air-detritiation tests

    International Nuclear Information System (INIS)

    Land, R.H.; Maroni, V.A.; Minkoff, M.

    1979-01-01

    A computer code has been developed which permits the determination of tritium reaction (T 2 to HTO)/adsorption/release and instrument correction parameters from enclosure (building) - detritiation test data. The code is based on a simplified model which treats each parameter as a normalized time-independent constant throughout the data-unfolding steps. Because of the complicated four-dimensional mathematical surface generated by the resulting differential equation system, occasional local-minima effects are observed, but these effects can be overcome in most instances by selecting a series of trial guesses for the initial parameter values and observing the reproducibility of final parameter values for cases where the best overall fit to experimental data is achieved. The code was then used to analyze existing small-cubicle test data with good success, and the resulting normalized parameters were employed to evaluate hypothetical reactor-building detritiation scenarios. It was concluded from the latter evaluation that the complications associated with moisture formation, adsorption, and release, particularly in terms of extended cleanup times, may not be as great as was previously thought. It is recommended that the validity of the TSOAK-M1 model be tested using data from detritiation tests conducted on large experimental enclosures (5 to 10 cm 3 ) and, if possible, actual facility buildings

  2. Status of FRJ-2 refurbishment of tank pipes and essential results of aging analysis

    International Nuclear Information System (INIS)

    Hansen, G.; Thamm, G.; Thome, M.

    1993-01-01

    An aging evaluation program for FRJ-2 (DIDO) of the Forschungszentrum Juelich GmbH has been developed and is currently executed in cooperation with the licensing and regulatory and TUV experts in order to determine the overall life expectancy of the facility and to identify critical systems and components that need to be upgraded or refurbished for future safe reactor operation. In Phase A (completed) a so called master list of the FRJ-2 mechanical, electrical and structural components was compiled on a system-by system basis and the operational documentation with respect to regular inspections, maintenance, repair and unusual occurences was carefully examined. Critical components were selected and their ageing respectively life limiting mechanisms identified. In Phase (currently under way) special inspections, examinations and tests for critical systems/components are being elaborated, executed and evaluated. Current work is being concentrated on non replaceable components (e.g. reactor aluminium tank (RAT) and the connecting pipes to the primary cooling circuit, the reactor steel tank and pipe work inside the concrete reactor block). As a consequence of first results of the aging evaluation program and due to leaks in the weir and drain pipes of the RAT a repair/refurbishment program was set up for the Al-RAT pipes (risers, downcomers weir and drain pipes) and the steel guide tubes. Details of the r/r program which is in far progress and first essential results of the aging evaluation will be presented. The results achieved until today are encouraging with respect to safe reactor operation on short and medium term. (author)

  3. Status of FRJ-2 Refurbishment of tank pipes and essential results of aging analysis

    International Nuclear Information System (INIS)

    Hansen, G.; Thamm, G.; Thome, M.

    1994-01-01

    An aging evaluation program for FRJ-2 (DIDO) of the Forschungszentrum Juelich GmbH has been developed and is currently executed in cooperation with the licensing and regulatory and TUEV experts in order to determine the overall life expectancy of the facility and to identify critical systems and components that need to be upgraded or refurbished for future safe reactor operation. In Phase A (completed) a so called master list of the FRJ-2 mechanical, electrical and structural components was compiled on a system-by system basis and the operational documentation with respect to regular inspections, maintenance, repair and unusual occurrences was carefully examined. Critical components were selected and their ageing respectively life limiting mechanisms identified. In Phase B (currently under way) special inspections, examinations and tests for critical systems/components are being elaborated, executed and evaluated. Current work is being concentrated on non replaceable components (e.g. reactor aluminium tank (RAT) and the connecting pipes to the primary cooling circuit, the reactor steel tank and pipe work inside the concrete reactor block). As a consequence of first results of the aging evaluation program and due to leaks in the weir and drain pipes of the RAT a repair/refurbishment program was set up for the Al-RAT pipes (risers, downcomers, weir and drain pipes) and the steel guide tubes. Details of the r/r program which is in far progress and first essential results of the aging evaluation will be presented. The results achieved until today are encouraging with respect to safe reactor operation on short and medium term. (J.P.N.)

  4. Results and present status of the Japan-US collaboration on detector research and development

    International Nuclear Information System (INIS)

    Arai, Yasuo; Takahashi, Kasuke

    1985-02-01

    This is a summary report on the results of the Detector R and D work, which we have been carrying out these three years, under the Japan-U.S. collaboration on High Energy Physics. It is clear that there have been already many considerable progress and outputs in the activities, some of which are already applied to the actual detectors in various ways. It is foreseeable that more extensive development will be realized. It should also be better to emphasize that these detector R and D efforts will be very important for the further development of high energy physics in the near future. (author)

  5. Status, performance, and first results of the IceTop array

    Energy Technology Data Exchange (ETDEWEB)

    Stanev, Todor [Bartol Research Institute, Department of Physics and Astronomy, University of Delaware, Newark, DE 19716 (United States)

    2009-12-15

    We describe the design and performance of IceTop, the air shower array on top of the IceCube neutrino detector. After the 2008/09 antarctic summer season both detectors are deployed at almost 3/4 of their design size. With the current IceTop 59 stations we can start the study of showers of energy well above 10{sup 17}eV. The paper also describes the first results from IceTop and our plans to study the cosmic ray composition using several different types of analysis.

  6. Stratospheric controlled perturbation experiment (SCoPEx): overview, status, and results from related laboratory experiments

    Science.gov (United States)

    Keith, D.; Dykema, J. A.; Keutsch, F. N.

    2017-12-01

    Stratospheric Controlled Perturbation Experiment (SCoPEx), is a scientific experiment to advance understanding of stratospheric aerosols. It aims to make quantitative measurements of aerosol microphysics and atmospheric chemistry to improve large-scale models used to assess the risks and benefits of solar geoengineering. A perturbative experiment requires: (a) means to create a well-mixed, small perturbed volume, and (b) observation of time evolution of chemistry and aerosols in the volume. SCoPEx will used a propelled balloon gondola containing all instruments and drive system. The propeller wake forms a well-mixed volume (roughly 1 km long and 100 meters in diameter) that serves as an experimental `beaker' into which aerosols (e.g., budget, etc; (d) results from CFD simulation of propeller wake and simulation of chemistry and aerosol microphysics; and finally (e) proposed concept of operations and schedule. We will also provide an overview of the plans for governance including management of health safety and environmental risks, transparency, public engagement, and larger questions about governance of solar geoengineering experiments. Finally, we will briefly present results of laboratory experiments of the interaction of chemical such as ClONO2 and HCl on particle surfaces relevant for stratospheric solar geoengineering.

  7. Human population doses: Comparative analysis of CREAM code results with currently computer codes of Nuclear Regulatory Authority; Dosis en la poblacion: comparacion de los resultados del codigo CREAM con resultados de modelos vigentes en la ARN

    Energy Technology Data Exchange (ETDEWEB)

    Alonso Jimenez, Maria Teresa; Curti, Adriana [Autoridad Regulatoria Nuclear, Buenos Aires (Argentina)]. E-mail: mtalonso@sede.arn.gov.ar; acurti@sede.arn.gov.ar

    2001-07-01

    The Nuclear Regulatory Authority is performing an analysis with PC CREAM, developed at the NRPB, for updating computer programs and models used for calculating the transfer of radionuclides through the environment. For CREAM dose assessment verification for local scenarios, this paper presents a comparison of population doses assessed with the computer codes used nowadays and with CREAM, for unitary releases of main radionuclides in nuclear power plant discharges. The results of atmospheric dispersion processes and the transfer of radionuclides through the environment for local scenarios are analysed. The programs used are PLUME for atmospheric dispersion, FARMLAND for the transfer of radionuclides into foodstuffs following atmospheric deposition in the terrestrial environment and ASSESSOR for individual and collective dose assessments.This paper presents the general assumptions made for dose assessments. The results show some differences between doses due to differences in models, in the complexity level of the same models, or in parameters. (author)

  8. Phebus program main results and status for severe fuel damage studies

    International Nuclear Information System (INIS)

    Duco, J.; Reocreux, M.; Tattegrain, A.

    1986-06-01

    A large experimental in-pile program has been set up at the PHEBUS facility to investigate the actual behavior of .8 m active height, 25-rod PWR-type pressurized fresh fuel bundles under typical accident conditions. The program consists of four stages. Stage 1 was devoted to the adjustment of the operational procedure for stage 2. Stage 2 refers to the simulation of conservatively calculated L.B. LOCA 2 - peak transients. Stages 3/4 refer to four PWR severe accident scenarios retained for in-pile simulation at PHEBUS: a) a large break LOCA with injection failure; b) a small break LOCA associated with an injection failure; c) a prolonged total loss of the steam generator feedwater; and, d) a prolonged core uncovery a few days after reactor shutdown. The main PHEBUS stage 2 results are presented and finally interpreted

  9. Status and first measurement results for a high gradient CH-cavity

    Energy Technology Data Exchange (ETDEWEB)

    Almomani, Ali; Ratzinger, Ulrich [Institut fuer Angewandte Physik, Frankfurt Universitaet, Frankfurt am Main (Germany)

    2016-07-01

    This pulsed linac activity aims on compact designs and on a considerable increase of the voltage gain per meter. A high gradient CH {sup *} cavity operated at 325 MHz was developed at IAP {sup *} Frankfurt. The mean effective accelerating field for this cavity is expected well above 10 MV/m at β=0.164. This cavity is developed within a funded project. The results might influence the rebuilt of the UNILAC {sup *} Alvarez section, aiming to achieve the beam intensities specified for the GSI {sup *} FAIR project (15 mA U28+). Another motivation is the development of an efficient pulsed ion accelerator for significantly higher energies like 60 AMeV. The new GSI 3 MW Thales klystron test stand will be used for the cavity RF power tests. Detailed studies on two different types of copper plating will be performed with this cavity.

  10. Status of data, major results, and plans for geophysical activities, Yucca Mountain Project

    Energy Technology Data Exchange (ETDEWEB)

    Oliver, H.W. [Geological Survey, Menlo Park, CA (USA); Hardin, E.L. [Science Applications International Corp., Las Vegas, NV (USA); Nelson, P.H. [Geological Survey, Denver, CO (USA)] [eds.

    1990-07-01

    This report describes past and planned geophysical activities associated with the Yucca Mountain Project and is intended to serve as a starting point for integration of geophysical activities. This report relates past results to site characterization plans, as presented in the Yucca Mountain Site Characterization Plan (SCP). This report discusses seismic exploration, potential field methods, geoelectrical methods, teleseismic data collection and velocity structural modeling, and remote sensing. This report discusses surface-based, airborne, borehole, surface-to-borehole, crosshole, and Exploratory Shaft Facility-related activities. The data described in this paper, and the publications discussed, have been selected based on several considerations; location with respect to Yucca Mountain, whether the success or failure of geophysical data is important to future activities, elucidation of features of interest, and judgment as to the likelihood that the method will produce information that is important for site characterization. 65 refs., 19 figs., 12 tabs.

  11. Status and results from the decay spectroscopy project EURICA (Euroball-RIKEN cluster array)

    Energy Technology Data Exchange (ETDEWEB)

    Söderström, P.-A., E-mail: pasoder@ribf.riken.jp; Doornenbal, P.; Nishimura, S.; Baba, H.; Isobe, T.; Kiss, G. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); Lorusso, G. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); National Physical Laboratory, Teddington, Middlesex, TW11 0LW (United Kingdom); Wu, J. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); School of Physics, Peking University, Beijing 100871 (China); Xu, Z. Y. [Department of Physics, University of Tokyo, Hongo, Bunkyo-ku, Tokyo 113-0033 (Japan); KU Leuven, Instituut voor Kern-en Stralingsfysica, 3001 Leuven (Belgium); Benzoni, G. [Istituto Nazionale di Fisica Nucleare, Sezione di Milano, Via Celoria 16, 20133 Milano (Italy); Browne, F. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); School of Computing, Engineering and Mathematics, University of Brighton, Brighton BN2 4JG (United Kingdom); Gey, G. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); LPSC, Université Grenoble-Alpes, CNRS/IN2P3, F-38026 Grenoble Cedex (France); ILL, 38042 Grenoble Cedex (France); Research Center for Nuclear Physics (RCNP), Osaka University, Ibaraki, Osaka 567-0047 (Japan); Jungclaus, A. [Instituto de Estructura de la Materia, CSIC, E-28006 Madrid (Spain); Kojouharov, I.; Kurz, N.; Schaffner, H. [GSI Helmholtzzentrum für Schwerionenforschung GmbH, 64291 Darmstadt (Germany); Lubos, D. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); Physik Department E12, Technische Universität München, D-85748 Garching (Germany); Moschner, K. [RIKEN Nishina Center, 2-1 Hirosawa, Wako-shi, Saitama 351-0198 (Japan); IKP, University of Cologne, D-50937 Cologne (Germany); and others

    2016-07-07

    β- and isomer-decay spectroscopy are sensitive probes of nuclear structure, and are often the only techniques capable of providing data for exotic nuclei that are produced with very low rates. Decay properties of exotic nuclei are also essential to model astrophysical events responsible for the evolution of the universe such as the rp- and r-processes. The EURICA project (EUROBALL RIKEN Cluster Array) has been launched in 2012 with the goal of performing spectroscopy of very exotic nuclei. Since 2012, five experimental campaigns have been successfully completed using fragmentation of {sup 124}Xe beam and in-flight-fission of {sup 238}U beam. In these proceedings we will introduce the experimental setup and highlight some key recent results around {sup 78}Ni, {sup 132}Sn, and {sup 110}Zn published during 2014 and 2015.

  12. Status of data, major results, and plans for geophysical activities, Yucca Mountain Project

    International Nuclear Information System (INIS)

    Oliver, H.W.; Hardin, E.L.; Nelson, P.H.

    1990-07-01

    This report describes past and planned geophysical activities associated with the Yucca Mountain Project and is intended to serve as a starting point for integration of geophysical activities. This report relates past results to site characterization plans, as presented in the Yucca Mountain Site Characterization Plan (SCP). This report discusses seismic exploration, potential field methods, geoelectrical methods, teleseismic data collection and velocity structural modeling, and remote sensing. This report discusses surface-based, airborne, borehole, surface-to-borehole, crosshole, and Exploratory Shaft Facility-related activities. The data described in this paper, and the publications discussed, have been selected based on several considerations; location with respect to Yucca Mountain, whether the success or failure of geophysical data is important to future activities, elucidation of features of interest, and judgment as to the likelihood that the method will produce information that is important for site characterization. 65 refs., 19 figs., 12 tabs

  13. Main results and status of the development of LEU fuel for Russian research reactors

    International Nuclear Information System (INIS)

    Vatulin, A.; Morozov, A.; Suprun, V.; Dobrikova, I.

    2005-01-01

    VNIINM develops low enrichment uranium (LEU) fuel on base U-Mo alloys and a novel design of pin-type fuel elements. The development is carried out both for existing reactors, and for new advanced designs of reactors. The work is carried on the following main directions: - irradiate LEU U-Mo dispersion fuel (the uranium density up to 6,0 g/cm 3 ) in two Russian research reactors: MIR (RIAR, Dimitrovgrad) as pin type fuel mini-elements and in WWR-M (PINP, Gatchina) within full-scaled fuel assembly (FA) with pin type fuel elements; - finalize development of design and fabrication process of IRT type FA with pin type fuel elements; - develop methods of reducing of U-Mo fuel --Al matrix interaction under irradiation; - develop fabricating methods of fuel elements on base of monolithic U-Mo fuel. The paper generally reviews the results of calculation, design and technology investigations accomplished by now. (author)

  14. ELIMED: MEDICAL APPLICATION AT ELI-BEAMLINES. STATUS OF THE COLLABORATION AND FIRST RESULTS

    Directory of Open Access Journals (Sweden)

    Francesco Schillaci

    2014-08-01

    Full Text Available ELI-Beamlines is one of the four pillars of the ELI (Extreme Light Infrastructure pan-European project. It will be an ultrahigh-intensity, high repetition-rate, femtosecond laser facility whose main goal is to generate and apply high-brightness X-ray sources and accelerated charged particles. In particular, medical applications are treated by the ELIMED task force, which has been launched by collaboration between ELI and INFN researchers. ELIMED aims to demonstrate the clinical applicability of laser accelerated ions. In this article, the state of the ELIMED project and the first scientific results are reported. The design and realisation of a preliminary beam handling system and of an advanced spectrometer for diagnostics of high energy (multi-MeV laser-accelerated ion beams will also be briefly presented.

  15. Present status and first results of the final focus beam line at the KEK Accelerator Test Facility

    Directory of Open Access Journals (Sweden)

    2010-04-01

    Full Text Available ATF2 is a final-focus test beam line which aims to focus the low emittance beam from the ATF damping ring to a vertical size of about 37 nm and to demonstrate nanometer level beam stability. Several advanced beam diagnostics and feedback tools are used. In December 2008, construction and installation were completed and beam commissioning started, supported by an international team of Asian, European, and U.S. scientists. The present status and first results are described.

  16. Assessment of the French environment radiological status in 2009. Synthesis of the results obtained by the IRSN survey networks

    International Nuclear Information System (INIS)

    2009-01-01

    After a brief recall of the IRSN's missions, this report describes why and how radioactivity is controlled in France. It presents the national network for environment radioactivity measurements, and indicates the objectives of this radiological survey. It comments the status and levels of the natural and artificial radioactivity in France, discusses the results of the territory general survey (atmosphere, inland, coast, regions), the results of fuel cycle related sites (nuclear sites, old mining sites, front end industries, electricity production plants, back end industries, waste storage sites), the results concerning the nuclear medicine radioactive releases, the results obtained during selective expertises, and discusses the assessment of the exposure of the French population to ionizing radiations. It finally indicates how those data are published

  17. Myocardial perfusion scintigraphy 2006 in Germany. Results of the query and current status

    International Nuclear Information System (INIS)

    Lindner, O.; Burchert, W.; Bengel, F.M.; Zimmermann, R.; Dahl, J. vom; Schaefer, W.; Schober, O.; Kluge, R.; Schaefers, M.

    2008-01-01

    Aim: this second survey was to deliver further information on myocardial perfusion scintigraphy (MPS) in Germany in 2006. Method: 351 questionnaires were evaluated: 207 private practices (PP), 117 hospitals (HO), 27 from university hospitals (UH). Results: MPS of 106 331 patients were reported, 85% were investigated with 99m Tc-perfusion tracers. 74% [2005 = 72%] were performed in PP, 17% [2005 = 15%] in HO and 9% [2005 = 13%] in UH. PP, which participated in 2005 and 2006, demonstrated an increase by 3,9% (HO 0%, UH -13,0%). The type of stress was pharmacological in 27% [2005 = 22%]; 54% adenosine (of these 29% with exercise), 37% dipyridamole (of these 56% with exercise), and 9% dobutamine. Gated SPECT was performed in 42% [2005 = 36%] of all rest- and in 39% [2005 32%] of all stress MPS. An attenuation correction was used by 69 [2005 = 78] institutions. 40% of all MPS were performed in patients suspected to have CAD. 24% of all institutions reported changes in the use of MPS by competing methods. Conclusion: there is a small increase of MPS between 2005 and 2006 despite competing methods. Gated SPECT has experienced more acceptance. Suspicion of CAD is an important indication of MPS. In order to tap the full potential of MPS a gated SPECT should be performed routinely. (orig.)

  18. Status and results from the TR30 cyclotron centre region model

    International Nuclear Information System (INIS)

    Kleeven, W.; Lanz, P.; McDonald, M.; Milton, B.F.; Schmor, P.W.; Schneider, H.R.; Jayamanna, K.; Sura, J.; Uzat, W.; Gyles, W.

    1990-06-01

    A full scale model for the centre region of the compact 30 MeV, 350 μA H - cyclotron (TR30) has been constructed, to test the design of critical components and to study beam properties and space charge effects out to the 5. turn (1 MeV). The ion source and injection line system duplicates that used in the TR30. The centre region can be accessed with diagnostic probes at four different angles. The normalized circulating emittances as estimated from beam profile measurements are 1.7π mm-mrad (radially) and 1.8π mm-mrad (vertically). The radial centering error of the beam is less than 1.5 mm. After initial tests the maximum intensity achieved at the 5. turn is 650 μA. This corresponds with a transmission efficiency of 12.5% for a continuous (non-bunched) input beam. No significant space charge effects are observed up to 650 μA. For the TR30 bunching is not a must because of the high current available from the source. Nevertheless, it was considered useful to study beam bunching for the Centre Region Cyclotron (CRC). Some of these results are described. (Author) 11 refs., 6 figs

  19. Design, Results, Evolution and Status of the ATLAS Simulation at Point1 Project

    CERN Document Server

    AUTHOR|(SzGeCERN)377840; Fressard-Batraneanu, Silvia Maria; Ballestrero, Sergio; Contescu, Alexandru Cristian; Fazio, Daniel; Di Girolamo, Alessandro; Lee, Christopher Jon; Pozo Astigarraga, Mikel Eukeni; Scannicchio, Diana; Sedov, Alexey; Twomey, Matthew Shaun; Wang, Fuquan; Zaytsev, Alexander

    2015-01-01

    Abstract. During the LHC Long Shutdown 1 period (LS1), that started in 2013, the Simulation at Point1 (Sim@P1) Project takes advantage, in an opportunistic way, of the TDAQ (Trigger and Data Acquisition) HLT (High Level Trigger) farm of the ATLAS experiment. This farm provides more than 1300 compute nodes, which are particularly suited for running event generation and Monte Carlo production jobs that are mostly CPU and not I/O bound. It is capable of running up to 2700 virtual machines (VMs) provided with 8 CPU cores each, for a total of up to 22000 parallel running jobs. This contribution gives a review of the design, the results, and the evolution of the Sim@P1 Project; operating a large scale OpenStack based virtualized platform deployed on top of the ATLAS TDAQ HLT farm computing resources. During LS1, Sim@P1 was one of the most productive ATLAS sites: it delivered more than 50 million CPU-hours and it generated more than 1.7 billion Monte Carlo events to various analysis communities. The design aspects a...

  20. Design, Results, Evolution and Status of the ATLAS simulation in Point1 project.

    CERN Document Server

    Ballestrero, Sergio; The ATLAS collaboration; Brasolin, Franco; Contescu, Alexandru Cristian; Fazio, Daniel; Di Girolamo, Alessandro; Lee, Christopher Jon; Pozo Astigarraga, Mikel Eukeni; Scannicchio, Diana; Sedov, Alexey; Twomey, Matthew Shaun; Wang, Fuquan; Zaytsev, Alexander

    2015-01-01

    During the LHC long shutdown period (LS1), that started in 2013, the simulation in Point1 (Sim@P1) project takes advantage in an opportunistic way of the trigger and data acquisition (TDAQ) farm of the ATLAS experiment. The farm provides more than 1500 computer nodes, and they are particularly suitable for running event generation and Monte Carlo production jobs that are mostly CPU and not I/O bound. It is capable of running up to 2500 virtual machines (VM) provided with 8 CPU cores each, for a total of up to 20000 parallel running jobs. This contribution gives a thorough review of the design, the results and the evolution of the Sim@P1 project operating a large scale Openstack based virtualized platform deployed on top of the ATLAS TDAQ farm computing resources. During LS1, Sim@P1 was one of the most productive GRID sites: it delivered more than 50 million CPU-hours and it generated more than 1.7 billion Monte Carlo events to various analysis communities within the ATLAS collaboration. The particular design ...

  1. Status of disposal techniques for spent fuel in Germany: Results of demonstration tests for direct disposal

    International Nuclear Information System (INIS)

    Engelmann, H.J.; Filbert, W.

    1993-01-01

    According to the Atomic Energy Act (1985) the Federal Government is responsible for establishing facilities to indemnify and dispose radioactive waste. According to Art. 9b of the Atomic Energy Act (1986) the construction and operation of such a repository requires approval of a plan. According to safety criteria applicable for disposing radioactive waste in mines, construction and operation of repository mines require application of acknowledged rules of technology, laws, ordinances and other regulations to protect operating staff and population from radiation damages. Shaft hoisting equipment for the transportation of radioactive waste in a repository mine must satisfy normal operational tasks and meet special safety-requirements. Its failure may result in danger for persons, release of radioactive substances into the plant and environment. That means, shaft hoisting equipment must be designed to satisfy the necessary safety requirements and be state of the art of science and technology. The aim of these demonstration tests is verification of technical feasibility of a shaft hoisting equipment with a payload of 85 t, underground for drift disposal of POLLUX-casks, and essential machine and mine-technical systems and components. The demonstration also includes safe radiation protection during transport and disposal operations. Investigations assume that radioactive waste is transported in containers that satisfy transport requirements for dangerous goods and have a type-B-certificate

  2. [Combustion zone investigation and modelling in fuel flexible suspension fired boilers]. Result summary and status

    Energy Technology Data Exchange (ETDEWEB)

    Lovmand Hvid, S.

    2011-12-15

    The project has been designed to obtain data from a power plant boiler with co-combustion, partly to gain greater knowledge of particle turnover in the fuel zone, partly to support the development of modeling tools. Data collection occurred at Studstrup Power Station Unit 4, where the fuel is a combination of coal and biomass. The boiler is equipped with 24 dust burners, four of which have been converted to firing with biomass. Measurements have been carried out in the flame zone with different fuels: coal alone, coal + straw and coal + wood. During the experiments velocity fields, temperature fields and gas concentration fields were measured in the firing zone. Also, particle samples from the flame zone ware collected. Several measurements are performed with well-known techniques, but in addition, the project developed new optical measurement methods based on UV spectroscopy. They allow measuring other gases than the hitherto known methods and allow you to gain insight into the dynamic variations beyond just mean fields. The collection of particle samples from the boiler was, as expected, a very challenging task under the given conditions, but was carried out with a largely satisfactory result. Analysis of the samples has initially failed to lead to an increased recognition of the speed of the conversion process, but the samples will be analyzed in more detail in other projects. (LN)

  3. Myocardial perfusion scintigraphy in Germany. Results of the 2005 query and current status

    International Nuclear Information System (INIS)

    Lindner, O.; Burchert, W.; Bengel, F.M.; Zimmermann, R.; Dahl, J. vom; Schaefer, W.; Buell, U.; Schober, O.; Schwaiger, M.; Kluge, R.; Schaefers, M.

    2007-01-01

    The working group Cardiovascular Nuclear Medicine of the German Society of Nuclear Medicine (DGN), in cooperation with the working group Nuclear Cardiology of the German Cardiac Society (DGK), decided to conduct a national survey on myocardial perfusion scintigraphy (MPS). Method: a questionnaire to evaluate MPS for the year 2005 was sent. Results: 346 completed questionnaires had been returned (213 private practices, 99 hospitals and 33 university hospitals). MPS of 112 707 patients were reported with 110 747 stress and 95 878 rest studies. The majority (> 75%) was performed with 99m Tc-MIBI or tetrofosmin. 201 Tl stress-redistribution was used in 22 637 patients (20%). The types of stress were exercise in 78%, vasodilation with adenosine or dipyridamol in 21% and dobutamine in 1%. 99.97% of all MPS were SPECT studies. Gated SPECT was performed in 36% of the stress and in 32% of the rest studies. An attenuation correction was used in 21%. 29 institutions (8%) performed gated SPECT (stress and rest) and attenuation correction. 47% of all MPS were requested by ambulatory care cardiologists, 17% by internists, 12% by primary care physicians, 21% by hospital departments and 2% by others. Conclusion: in Germany, MPS is predominantly performed with 99m Tc-perfusion agents. The common type of stress is ergometry. Gated SPECT and attenuation correction do not yet represent standards of MPS practice in Germany, which indicates some potential of optimization. (orig.)

  4. Status of test results of electrochemical organic oxidation of a tank 241-SY-101 simulated waste

    International Nuclear Information System (INIS)

    Colby, S.A.

    1994-06-01

    This report presents scoping test results of an electrochemical waste pretreatment process to oxidize organic compounds contained in the Hanford Site's radioactive waste storage tanks. Electrochemical oxidation was tested on laboratory scale to destroy organics that are thought to pose safety concerns, using a nonradioactive, simulated tank waste. Minimal development work has been applied to alkaline electrochemical organic destruction. Most electrochemical work has been directed towards acidic electrolysis, as in the metal purification industry, and silver catalyzed oxidation. Alkaline electrochemistry has traditionally been associated with the following: (1) inefficient power use, (2) electrode fouling, and (3) solids handling problems. Tests using a laboratory scale electrochemical cell oxidized surrogate organics by applying a DC electrical current to the simulated tank waste via anode and cathode electrodes. The analytical data suggest that alkaline electrolysis oxidizes the organics into inorganic carbonate and smaller carbon chain refractory organics. Electrolysis treats the waste without adding chemical reagents and at ambient conditions of temperature and pressure. Cell performance was not affected by varying operating conditions and supplemental electrolyte additions

  5. Present status of Kyoto University reactor research result data base KURRIP

    International Nuclear Information System (INIS)

    Takeuchi, Takayuki

    1986-01-01

    The construction of KURRIP data base was begun in 1982, and in 1983, the data base concerning the literatures published in five years from 1978 to 1982 was set up in the Kyoto University Large Computer Center, and it has become available generally. In fiscal year 1984, the data concerning the literatures published from 1974 to 1977 and in 1983 were added. Moreover in this fiscal year, the work is carried out to input the data concerning the literatures published from 1970 to 1973 and in 1984. The data retrievable at present are those for ten years from 1974 to 1983. The results of having retrieved these data about a number of items are reported in this paper. The classification according to the places of employment of authors, the classification according to the kinds of literatures, the classification according to the languages used, the classification according to the installations used, the classification according to the fields of research, and the classification according to the magazines which printed the data are reported. (Kako, I.)

  6. Radioactivity monitoring status in French Polynesia in 2008. Results from IRSN's monitoring network

    International Nuclear Information System (INIS)

    2009-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. The task addresses two objectives: - To monitor the levels of artificial radioactivity in all sectors of the environment and in major foodstuffs; - To estimate the exposure of the Polynesian population to this artificial radioactivity. The IRSN has monitored radioactivity levels in French Polynesia, excluding the Mururoa and Fangataufa nuclear experimentation centres, since 1962. This task is realized by the IRSN's Environmental Study and Monitoring Laboratory located in Tahiti (Vairao) This monitoring was instigated at the time when atmospheric nuclear weapons testing was being performed by the major powers (the United States, the Soviet Union, the United Kingdom, France and China), causing fallout of artificial radionuclides, over several years, on a planetary scale. In French Polynesia, the IRSN is most particularly interested in fallout resulting from the 41 tests carried out by France in this region of the globe between 1966 and 1974, and in its consequent effects on the population. Today, just as in metropolitan France, the IRSN carries out monitoring as part of its mission to constantly monitor radiological protection factors. The monitoring takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes and consists of taking monthly samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. For more than 40 years, the IRSN takes part in the evaluation of the dosimetric consequences of these atmospheric depositions in French Polynesia. This laboratory is established in Tahiti. The ingestion component of this dosimetric evaluation requires to collect the most representative samples of

  7. Myocardial perfusion scintigraphy 2007 in Germany. Results of the query and current status

    Energy Technology Data Exchange (ETDEWEB)

    Lindner, O. [Inst. fuer Radiologie, Nuklearmedizin und Molekulare Bildgebung, Herz- und Diabeteszentrum NRW, Bad Oeynhausen (Germany); Burchert, W. [Inst. fuer Radiologie, Nuklearmedizin und Molekulare Bildgebung, Herz- und Diabeteszentrum NRW, Bad Oeynhausen (Germany); Arbeitsgemeinschaft Kardiovaskulaere Nuklearmedizin der Deutschen Gesellschaft fuer Nuklearmedizin (Germany); Bengel, F.M. [Cardiovascular Nuclear Medicine, Johns Hopkins Medical Institutions, Baltimore (United States); Arbeitsgruppe Nuklearkardiologische Diagnostik der Deutschen Gesellschaft fuer Kardiologie (Germany); Zimmermann, R. [Arbeitsgruppe Nuklearkardiologische Diagnostik der Deutschen Gesellschaft fuer Kardiologie (Germany); Medizinische Klinik, Klinikum Pforzheim GmbH, Pforzheim (Germany); Dahl, J. vom [Klinik fuer Kardiologie, Kliniken Maria Hilf GmbH, Moenchengladbach (Germany); Schaefer, W. [Klinik fuer Nuklearmedizin, Universitaetsklinikum Aachen (Germany); Schober, O. [Klinik und Poliklinik fuer Nuklearmedizin, Universitaetsklinikum Muenster UKM (Germany); Schaefers, M. [Arbeitsgemeinschaft Kardiovaskulaere Nuklearmedizin der Deutschen Gesellschaft fuer Nuklearmedizin (Germany); Klinik und Poliklinik fuer Nuklearmedizin, Universitaetsklinikum Muenster UKM (Germany)

    2009-07-01

    Aim: This third survey of the working group Cardiovascular Nuclear Medicine of the German Society of Nuclear Medicine in cooperation with the working group Nuclear Cardiology of the German Cardiac Society was to deliver information on the procedures and in particular on the development of myocardial perfusion scintigraphy (MPS) from 2005 to 2007. Method: 370 questionnaires (222 private practices (PP), 117 hospitals (HO), 31 university hospitals (UH)) were evaluated. Results: MPS of 114,374 patients were reported, 83% were investigated with {sup 99m}Tc-perfusion tracers. 76% [2006=74%] were performed in PP, 15% [2006=17%] in HO and 9% [2006=9%] in UH. Diabetics represented 21% of all MPS patients in 2007. Data of 215 institutions which participated all from 2005 to 2007 showed an increase in MPS of 2.3% (PP +6.8%, HO -4.5%, UH -18.2%). The type of stress was pharmacological in 27% [2006 = 27%]; 67% adenosine (of these 25% with exercise), 31% dipyridamole (of these 55% with exercise), and 2% dobutamine. Gated SPECT was performed in 47% [2006 = 42%] of all rest and in 44% [2006 = 39%] of all stress MPS. 61% [2006 = 83%] of all institutions did not apply perfusion scores. 20% [2006 = 24%] of the institutions reported changes in the use of MPS by competing methods. Conclusion: There is a small increase of MPS between 2005 and 2007 despite competing methods. Gated SPECT has experienced more acceptance, but is still underrepresented. As compared to the European average and general standards of MPS a considerable backlog accounts to pharmacological stress tests, gated SPECT and perfusion scores. (orig.)

  8. Status of neurology medical school education: results of 2005 and 2012 clerkship director survey.

    Science.gov (United States)

    Carter, Jonathan L; Ali, Imran I; Isaacson, Richard S; Safdieh, Joseph E; Finney, Glen R; Sowell, Michael K; Sam, Maria C; Anderson, Heather S; Shin, Robert K; Kraakevik, Jeff A; Coleman, Mary; Drogan, Oksana

    2014-11-04

    To survey all US medical school clerkship directors (CDs) in neurology and to compare results from a similar survey in 2005. A survey was developed by a work group of the American Academy of Neurology Undergraduate Education Subcommittee, and sent to all neurology CDs listed in the American Academy of Neurology database. Comparisons were made to a similar 2005 survey. Survey response rate was 73%. Neurology was required in 93% of responding schools. Duration of clerkships was 4 weeks in 74% and 3 weeks in 11%. Clerkships were taken in the third year in 56%, third or fourth year in 19%, and fourth year in 12%. Clerkship duration in 2012 was slightly shorter than in 2005 (fewer clerkships of ≥4 weeks, p = 0.125), but more clerkships have moved into the third year (fewer neurology clerkships during the fourth year, p = 0.051). Simulation training in lumbar punctures was available at 44% of schools, but only 2% of students attempted lumbar punctures on patients. CDs averaged 20% protected time, but reported that they needed at least 32%. Secretarial full-time equivalent was 0.50 or less in 71% of clerkships. Eighty-five percent of CDs were "very satisfied" or "somewhat satisfied," but more than half experienced "burnout" and 35% had considered relinquishing their role. Trends in neurology undergraduate education since 2005 include shorter clerkships, migration into the third year, and increasing use of technology. CDs are generally satisfied, but report stressors, including inadequate protected time and departmental support. © 2014 American Academy of Neurology.

  9. Myocardial perfusion scintigraphy 2007 in Germany. Results of the query and current status

    International Nuclear Information System (INIS)

    Lindner, O.; Burchert, W.; Bengel, F.M.; Zimmermann, R.; Dahl, J. vom; Schaefer, W.; Schober, O.; Schaefers, M.

    2009-01-01

    Aim: This third survey of the working group Cardiovascular Nuclear Medicine of the German Society of Nuclear Medicine in cooperation with the working group Nuclear Cardiology of the German Cardiac Society was to deliver information on the procedures and in particular on the development of myocardial perfusion scintigraphy (MPS) from 2005 to 2007. Method: 370 questionnaires (222 private practices (PP), 117 hospitals (HO), 31 university hospitals (UH)) were evaluated. Results: MPS of 114,374 patients were reported, 83% were investigated with 99m Tc-perfusion tracers. 76% [2006=74%] were performed in PP, 15% [2006=17%] in HO and 9% [2006=9%] in UH. Diabetics represented 21% of all MPS patients in 2007. Data of 215 institutions which participated all from 2005 to 2007 showed an increase in MPS of 2.3% (PP +6.8%, HO -4.5%, UH -18.2%). The type of stress was pharmacological in 27% [2006 = 27%]; 67% adenosine (of these 25% with exercise), 31% dipyridamole (of these 55% with exercise), and 2% dobutamine. Gated SPECT was performed in 47% [2006 = 42%] of all rest and in 44% [2006 = 39%] of all stress MPS. 61% [2006 = 83%] of all institutions did not apply perfusion scores. 20% [2006 = 24%] of the institutions reported changes in the use of MPS by competing methods. Conclusion: There is a small increase of MPS between 2005 and 2007 despite competing methods. Gated SPECT has experienced more acceptance, but is still underrepresented. As compared to the European average and general standards of MPS a considerable backlog accounts to pharmacological stress tests, gated SPECT and perfusion scores. (orig.)

  10. Design, Results, Evolution and Status of the ATLAS Simulation at Point1 Project

    Science.gov (United States)

    Ballestrero, S.; Batraneanu, S. M.; Brasolin, F.; Contescu, C.; Fazio, D.; Di Girolamo, A.; Lee, C. J.; Pozo Astigarraga, M. E.; Scannicchio, D. A.; Sedov, A.; Twomey, M. S.; Wang, F.; Zaytsev, A.

    2015-12-01

    During the LHC Long Shutdown 1 (LSI) period, that started in 2013, the Simulation at Point1 (Sim@P1) project takes advantage, in an opportunistic way, of the TDAQ (Trigger and Data Acquisition) HLT (High-Level Trigger) farm of the ATLAS experiment. This farm provides more than 1300 compute nodes, which are particularly suited for running event generation and Monte Carlo production jobs that are mostly CPU and not I/O bound. It is capable of running up to 2700 Virtual Machines (VMs) each with 8 CPU cores, for a total of up to 22000 parallel jobs. This contribution gives a review of the design, the results, and the evolution of the Sim@P1 project, operating a large scale OpenStack based virtualized platform deployed on top of the ATLAS TDAQ HLT farm computing resources. During LS1, Sim@P1 was one of the most productive ATLAS sites: it delivered more than 33 million CPU-hours and it generated more than 1.1 billion Monte Carlo events. The design aspects are presented: the virtualization platform exploited by Sim@P1 avoids interferences with TDAQ operations and it guarantees the security and the usability of the ATLAS private network. The cloud mechanism allows the separation of the needed support on both infrastructural (hardware, virtualization layer) and logical (Grid site support) levels. This paper focuses on the operational aspects of such a large system during the upcoming LHC Run 2 period: simple, reliable, and efficient tools are needed to quickly switch from Sim@P1 to TDAQ mode and back, to exploit the resources when they are not used for the data acquisition, even for short periods. The evolution of the central OpenStack infrastructure is described, as it was upgraded from Folsom to the Icehouse release, including the scalability issues addressed.

  11. Status of 2009 radioactivity monitoring in French Polynesia. Results of IRSN's monitoring network

    International Nuclear Information System (INIS)

    2010-01-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, Hiva Oa, Mangareva and Tubuai) representing the five archipelagoes, consists in regularly collecting samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagoes of that territory. They come from the marine environment of the open sea, from the marine lagoon environment and from the terrestrial environment. Almost all samples are measured at the IRSN Laboratory for the Environment Study and Monitoring, based in Vairao, Tahiti Island. The 239 samples collected in 2009 were measured by Hp-Ge low background gamma spectrometry in order to be able to characterize lowest possible radioactivity levels. The levels of activity of Pu isotopes have also been determined for 17 selected samples and tritium activities for 15 water samples. The results for the year 2009 are in the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro Sieverts per year). This value corresponds to less than 0, 5 % of exposure due to natural radioactivity in Polynesia (approximately 1000 μSv.y -1 ). (authors)

  12. FireBird - a small satellite fire monitoring mission: Status and first results

    Science.gov (United States)

    Lorenz, Eckehard; Rücker, Gernot; Terzibaschian, Thomas; Klein, Doris; Tiemann, Joachim

    2014-05-01

    The scientific mission FireBird is operated by the German Aerospace Center (DLR) and consists of two small satellites. The first satellite - TET-1 - was successfully launched from Baikonur, Russia in July 2012. Its first year in orbit was dedicated to a number of experiments within the framework of the DLR On Orbit Verification (OOV) program which is dedicated to technology testing in space. After successful completion of its OOV phase, TET-1 was handed over to the DLR FireBird mission and is now a dedicated Earth Observation mission. Its primary goal is sensing of hot phenomena such as wildfires, volcanoes, gas flares and industrial hotspots. The second satellite, BiROS is scheduled for launch in the second or third quarter of 2015. The satellite builds on the heritage of the DLR BIRD (BIspectral Infrared Detection) mission and delivers quantitative information (such as Fire Radiative Power, FRP) at a spatial resolution of 350 m, superior to any current fire enabled satellite system such as NPP VIIRS, MODIS or Meteosat SEVIRI. The satellite is undergoing a four month validation phase during which satellite operations are adapted to the new mission goals of FireBIRD and processing capacities are established to guarantee swift processing and delivery of high quality data. The validation phase started with an informal Operational Readiness Review and will be completed with a formal review, covering all aspects of the space and ground segments. The satellite is equipped with a camera with a 42 m ground pixel size in the red, green and near infrared spectral range, and a 370 m ground pixel size camera in the mid and thermal infrared with a swath of 185 km. The satellite can be pointed towards a target in order to enhance observation frequency. First results of the FireBird mission include a ground validation experiment and acquisitions over fires across the world. Once the validation phase is finished the data will be made available to a wide scientific community.

  13. Convolutional coding techniques for data protection

    Science.gov (United States)

    Massey, J. L.

    1975-01-01

    Results of research on the use of convolutional codes in data communications are presented. Convolutional coding fundamentals are discussed along with modulation and coding interaction. Concatenated coding systems and data compression with convolutional codes are described.

  14. Investigation of reactivity changes due to flooding the irradiation sites of the MNSR reactor using the MCNP code and comparison with experimental results

    Directory of Open Access Journals (Sweden)

    A Shirani

    2010-06-01

    Full Text Available In this work, the Isfahan Miniature Neutron Source Reactor (MNSR has been simulated using the MCNP code, and reactivity worth of flooding the inner irradiation sites of this reactor in an accident has been calculated. Also, by inserting polyethylene capsules containing water inside the inner irradiation sites, reactivity changes of this reactor in same such accident have been measured, the results of which are in good agreements with the calculated results. In this work, the reactivity worth due to flooding one inner irradiation site is 0.53mk , and reactivity worth due to flooding of the whole 5 inner irradiation sites is 2.61 mk.

  15. Interim results of the sixth three-dimensional AER dynamic benchmark problem calculation. Solution of problem with DYN3D and RELAP5-3D codes

    International Nuclear Information System (INIS)

    Hadek, J.; Kral, P.; Macek, J.

    2001-01-01

    The paper gives a brief survey of the 6 th three-dimensional AER dynamic benchmark calculation results received with the codes DYN3D and RELAPS-3D at NRI Rez. This benchmark was defined at the 10 th AER Symposium. Its initiating event is a double ended break in the steam line of steam generator No. I in a WWER-440/213 plant at the end of the first fuel cycle and in hot full power conditions. Stationary and burnup calculations as well as tuning of initial state before the transient were performed with the code DYN3D. Transient calculations were made with the system code RELAPS-3D.The KASSETA library was used for the generation of reactor core neutronic parameters. The detailed six loops model of NPP Dukovany was adopted for the 6 th AER dynamic benchmark purposes. The RELAPS-3D full core neutronic model was connected with seven coolant channels thermal-hydraulic model of the core (Authors)

  16. Genetic Recombination Between Stromal and Cancer Cells Results in Highly Malignant Cells Identified by Color-Coded Imaging in a Mouse Lymphoma Model.

    Science.gov (United States)

    Nakamura, Miki; Suetsugu, Atsushi; Hasegawa, Kousuke; Matsumoto, Takuro; Aoki, Hitomi; Kunisada, Takahiro; Shimizu, Masahito; Saji, Shigetoyo; Moriwaki, Hisataka; Hoffman, Robert M

    2017-12-01

    The tumor microenvironment (TME) promotes tumor growth and metastasis. We previously established the color-coded EL4 lymphoma TME model with red fluorescent protein (RFP) expressing EL4 implanted in transgenic C57BL/6 green fluorescent protein (GFP) mice. Color-coded imaging of the lymphoma TME suggested an important role of stromal cells in lymphoma progression and metastasis. In the present study, we used color-coded imaging of RFP-lymphoma cells and GFP stromal cells to identify yellow-fluorescent genetically recombinant cells appearing only during metastasis. The EL4-RFP lymphoma cells were injected subcutaneously in C57BL/6-GFP transgenic mice and formed subcutaneous tumors 14 days after cell transplantation. The subcutaneous tumors were harvested and transplanted to the abdominal cavity of nude mice. Metastases to the liver, perigastric lymph node, ascites, bone marrow, and primary tumor were imaged. In addition to EL4-RFP cells and GFP-host cells, genetically recombinant yellow-fluorescent cells, were observed only in the ascites and bone marrow. These results indicate genetic exchange between the stromal and cancer cells. Possible mechanisms of genetic exchange are discussed as well as its ramifications for metastasis. J. Cell. Biochem. 118: 4216-4221, 2017. © 2017 Wiley Periodicals, Inc. © 2017 Wiley Periodicals, Inc.

  17. Modification and application of TOUGH2 as a variable-density, saturated-flow code and comparison to SWIFT II results

    International Nuclear Information System (INIS)

    Christian-Frear, T.L.; Webb, S.W.

    1995-01-01

    Human intrusion scenarios at the Waste Isolation Pilot Plant (WIPP) involve penetration of the repository and an underlying brine reservoir by a future borehole. Brine and gas from the brine reservoir and the repository may flow up the borehole and into the overlying Culebra formation, which is saturated with water containing different amounts of dissolved 'solids resulting in a spatially varying density. Current modeling approaches involve perturbing a steady-state Culebra flow field by inflow of gas and/or brine from a breach borehole that has passed through the repository. Previous studies simulating steady-state flow in the Culebra have been done. One specific study by LaVenue et al. (1990) used the SWIFT 2 code, a single-phase flow and transport code, to develop the steady-state flow field. Because gas may also be present in the fluids from the intrusion borehole, a two-phase code such as TOUGH2 can be used to determine the effect that emitted fluids may have on the steady-state Culebra flow field. Thus a comparison between TOUGH2 and SWIFT2 was prompted. In order to compare the two codes and to evaluate the influence of gas on flow in the Culebra, modifications were made to TOUGH2. Modifications were performed by the authors to allow for element-specific values of permeability, porosity, and elevation. The analysis also used a new equation of state module for a water-brine-air mixture, EOS7 (Pruess, 1991), which was developed to simulate variable water densities by assuming a miscible mixture of water and brine phases and allows for element-specific brine concentration in the INCON file

  18. Dynamic models for radionuclide transport in agricultural ecosystems: summary of results from a UK code comparison exercise

    International Nuclear Information System (INIS)

    Meekings, G.F.; Walters, B.

    1986-01-01

    In recent years, models have been developed by three organisations in the UK to represent the time-dependent behaviour of radionuclides in agricultural ecosystems. These models were developed largely independently of each other and, in view of their potential applications in relation to radioactive waste management and discharge, the Food Science Division of the Ministry of Agriculture, Fisheries and Food initiated a calculational intercomparison exercise with the agreement and cooperation of all three organisations involved. A subset of the results obtained is reported here. In general a high degree of consistency between the results of the various models was obtained particularly regarding the responses with time. The exercise supported the case for using dynamic models in radiological assessment studies. It also demonstrated areas where differences in results from the models are a consequence of a lack of appropriate data on the environmental behaviour of the radionuclides considered. (author)

  19. Research Project Control System (RPCS); research results utilization data as of 06/30/81. Status summary report

    International Nuclear Information System (INIS)

    1981-09-01

    The report on 'Research Results Utilization' provides status and control information concerning the utilization of research results in the regulatory policies and practices of the NRC. Research Information Letters (RILs) are prepared by RES to transmit research results to NRC user offices upon completion of a substantial, coherent and reasonably complete body of experimental and/or analytical research work. Section 3.0 of this report lists the RILs issued to date, together with an identification of the research program manager and the research program element which generated the RIL. The potential applicability of each RIL to the regulatory process is also identified, and comments from the cognizant RES and user office staff are summarized which relate to the expected impact of the reported RILs on the regulatory process

  20. Micronutrient intake and status in Central and Eastern Europe compared with other European countries, results from the EURRECA network

    NARCIS (Netherlands)

    Novakovic, R.N.; Cavelaars, A.J.E.M.; Bekkering, G.E.; Roman-Vinas, B.; Ngo, J.; Gurinovic, M.; Glibetic, M.; Golesorkhi, M.; Warthon-Medina, M.; Satalic, Z.; Geelen, A.; Serra Majem, L.; Veer, van 't P.; Groot, de C.P.G.M.

    2013-01-01

    Objective: To compare micronutrient intakes and status in Central and Eastern Europe (CEE) with those in other European countries and with reference values. Design: Review of the micronutrient intake/status data from open access and grey literature source

  1. Visual Input Enhancement via Essay Coding Results in Deaf Learners' Long-Term Retention of Improved English Grammatical Knowledge

    Science.gov (United States)

    Berent, Gerald P.; Kelly, Ronald R.; Schmitz, Kathryn L.; Kenney, Patricia

    2009-01-01

    This study explored the efficacy of visual input enhancement, specifically "essay enhancement", for facilitating deaf college students' improvement in English grammatical knowledge. Results documented students' significant improvement immediately after a 10-week instructional intervention, a replication of recent research. Additionally, the…

  2. Modification of the code BEAMCORR, and some simulation results of the magnet and achromat misalignments for the SLC South Arc

    International Nuclear Information System (INIS)

    Shoaee, H.; Kheifets, S.

    1984-01-01

    An important decision has been made regarding the correction scheme for the arcs leading to the adoption of the so called scheme I. In this scheme the beam position data are collected from single-plane x and y Beam Position Monitors (BPMs), which are placed in the drift spaces adjacent to the downstream D- and F-magnets correspondingly. Similarly, single-plane x and y correctors are used for moving the upstream end of the corresponding magnets. In the present simulation this scheme is used exclusively. The first order calculations performed by means of TRANSPORT appear to be unsatisfactory from the point of view of the beam spotsize at the interaction point (IP). In this note we describe the modification to our program BEAMCORR which employs second order calculations by means of the program TURTLE. We also present the results of the following simulations: (a) study of the effects of two different levels of magnet misalignment on the beam spotsize at IP, and comparison of the results with those obtained by means of the program DINGBAT; (b) study of disjoints between achromats (both the displacement of the adjacent ends and angular discontinuity between achromats)

  3. Results from a community-based program evaluating the effect of changing smoking status on asthma symptom control

    Directory of Open Access Journals (Sweden)

    To Teresa

    2012-04-01

    Full Text Available Abstract Background Cigarette smoking has been associated with accelerated decline in lung function, increased health services use and asthma severity in patients with asthma. Previous studies have provided insight into how smoking cessation improves lung function among asthma patients, however, fail to provide measurable asthma symptom-specific outcomes after smoking cessation. The objective of this study was to measure the effect of changing smoking status on asthma symptom control and health services use in adults with asthma. Methods The study was conducted in eight primary care practices across Ontario, Canada participating in a community-based, participatory, and evidence-based Asthma Care Program. Patients aged 18 to 55 identified with physician-diagnosed mild to moderate asthma were recruited. In addition to receiving clinical asthma care, participants were administered a questionnaire at baseline and 12-month follow-up visits to collect information on demographics, smoking status, asthma symptoms and routine health services use. The effect of changing smoking status on asthma symptom control was compared between smoking groups using Chi-square and Fisher’s exact tests where appropriate. Mixed effect models were used to measure the impact of the change in smoking status on asthma symptom and health services use while adjusting for covariates. Results This study included 519 patients with asthma; 11% of baseline smokers quit smoking while 4% of baseline non-smokers started smoking by follow-up. Individuals who quit smoking had 80% lower odds of having tightness in the chest (Odds ratio (OR = 0.21, 95% CI: 0.06, 0.82 and 76% lower odds of night-time symptoms (OR = 0.24, 95% CI: 0.07, 0.85 compared to smokers who continued to smoke. Compared to those who remained non-smokers, those who had not been smoking at baseline but self-reported as current smoker at follow-up had significantly higher odds of chest tightness (OR = 1

  4. Results of small break LOCA analysis for Kuosheng nuclear power plant using the RELAP5YA computer code

    International Nuclear Information System (INIS)

    Wang, L.C.; Jeng, S.C.; Chung, N.M.

    2004-01-01

    One lesson learned from the Three Mile Island (TMI) accident was the analysis methods used by Nuclear Steam Supply System (NSSS) vendors and/or nuclear fuel suppliers for small break Loss Of Coolant Accident (LOCA) analysis for compliance with appendix K to 10CFR50 should be revised, documented and submitted for USNRC approval and the plant-specific calculations using NRC-approved models for small-break LOCA to show compliance with 10CFR50.46 should be submitted for NRC approval. A study by Taiwan Power Company (TPC) under the guidance of Yankee Atomic Electric Company (YAEC) has been undertaken to perform this analysis for Kuosheng nuclear power plant. This paper presents the results of the analysis that are useful in satisfying the same requirements of the Republic Of China Atomic Energy Commission (ROCAEC). (author)

  5. Ownership status and patterns of care in hospice: results from the National Home and Hospice Care Survey.

    Science.gov (United States)

    Carlson, Melissa D A; Gallo, William T; Bradley, Elizabeth H

    2004-05-01

    The number of for-profit hospices increased nearly 4-fold over the past decade, more than 6 times the growth of nonprofit hospices. Despite this growth, the impact of ownership on hospice care is largely unknown. We sought to assess differences in the provision of services to patients of for-profit and nonprofit hospices. Using the 1998 National Home and Hospice Care Survey, we examined services used by patients (N = 2080) cared for by 422 hospices nationwide. We used multivariable ordered logistic and logistic regression to assess the effect of profit status on service use, adjusting for potentially confounding patient and organizational characteristics. We calculated point estimates adjusted for sampling weights and standard errors adjusted for the clustering of patients within hospices. In ordered logistic models controlling for organizational and patient factors, patients of for-profit hospices received a significantly narrower range of services (adjusted odds ratio [OR], 0.45; 95% confidence interval [CI], 0.22-0.92) than patients of nonprofit hospices. This result is driven by patients of for-profit hospices receiving significantly fewer types of hospice services that federal regulations term "noncore" or more discretionary services (adjusted OR, 0.34; 95% CI, 0.15-0.75). The pattern of care differs in for-profit and nonprofit hospices. As the industry develops a substantial for-profit presence, it is critical for clinicians and other healthcare professionals to be alert to the potential impact of profit status on the care their patients receive.

  6. Smoking Status and the Five-Factor Model of Personality: Results of a Cross-Sectional Study Conducted in Poland.

    Science.gov (United States)

    Buczkowski, Krzysztof; Basinska, Małgorzata A; Ratajska, Anna; Lewandowska, Katarzyna; Luszkiewicz, Dorota; Sieminska, Alicja

    2017-01-27

    Tobacco smoking is the single most important modifiable factor in increased morbidity and premature mortality. Numerous factors-including genetics, personality, and environment-affect the development and persistence of tobacco addiction, and knowledge regarding these factors could improve smoking cessation rates. This study compared personality traits between never, former, and current smokers, using the Five-Factor Model of Personality in a country with a turbulent smoking reduction process. : In this cross-sectional study, 909 Polish adults completed the Revised Neuroticism-Extraversion-Openness Personality Inventory. Our results showed that current smokers' scores for extraversion, one of the five global dimensions of personality, were higher relative to never smokers. Neuroticism, openness to experience, agreeableness, and conscientiousness did not differ significantly according to smoking status. Facet analysis, which described each dimension in detail, showed that current smokers' activity and excitement seeking (facets of extraversion) scores were higher relative to those of never and former smokers. In turn, current smokers' dutifulness and deliberation (facets of conscientiousness) scores were lower than those found in former and never smokers. Never smokers scored the highest in self-consciousness (a facet of neuroticism) and compliance (a component of agreeableness). The study conducted among Polish individuals showed variation in personality traits according to their smoking status; however, this variation differed from that reported in countries in which efforts to reduce smoking had begun earlier relative to Poland. Knowledge regarding personality traits could be useful in designing smoking prevention and cessation programs tailored to individuals' needs.

  7. Verification of the both hydrogeological and hydrogeochemical code results by an on-site test in granitic rocks

    Directory of Open Access Journals (Sweden)

    Michal Polák

    2007-01-01

    Full Text Available The project entitled “Methods and tools for the evaluation of the effect of engeneered barriers on distant interactions in the environment of a deep repository facility” deals with the ability to validate the behavior of applied engeneered barriers on hydrodynamic and migration parameters in the water-bearing granite environment of a radioactive waste deep repository facility. A part of the project represents a detailed mapping of the fracture network by means of geophysical and drilling surveys on the test-site (active granite quarry, construction of model objects (about 100 samples with the shape of cylinders, ridges and blocks, and the mineralogical, petrological and geochemical description of granite. All the model objects were subjected to migration and hydrodynamic tests with the use of fluorescein and NaCl as tracers. The tests were performed on samples with simple fractures, injected fractures and with an undisturbed integrity (verified by ultrasonic. The gained hydrodynamic and migration parameters of the model objects were processed with the modeling software NAPSAC and FEFLOW. During the following two years, these results and parameters will be verified (on the test-site by means of a long-term field test including the tuning of the software functionality.

  8. Health sciences librarians' awareness and assessment of the Medical Library Association Code of Ethics for Health Sciences Librarianship: the results of a membership survey.

    Science.gov (United States)

    Byrd, Gary D; Devine, Patricia J; Corcoran, Kate E

    2014-10-01

    The Medical Library Association (MLA) Board of Directors and president charged an Ethical Awareness Task Force and recommended a survey to determine MLA members' awareness of and opinions about the current Code of Ethics for Health Sciences Librarianship. THE TASK FORCE AND MLA STAFF CRAFTED A SURVEY TO DETERMINE: (1) awareness of the MLA code and its provisions, (2) use of the MLA code to resolve professional ethical issues, (3) consultation of other ethical codes or guides, (4) views regarding the relative importance of the eleven MLA code statements, (5) challenges experienced in following any MLA code provisions, and (6) ethical problems not clearly addressed by the code. Over 500 members responded (similar to previous MLA surveys), and while most were aware of the code, over 30% could not remember when they had last read or thought about it, and nearly half had also referred to other codes or guidelines. The large majority thought that: (1) all code statements were equally important, (2) none were particularly difficult or challenging to follow, and (3) the code covered every ethical challenge encountered in their professional work. Comments provided by respondents who disagreed with the majority views suggest that the MLA code could usefully include a supplementary guide with practical advice on how to reason through a number of ethically challenging situations that are typically encountered by health sciences librarians.

  9. The nutritional status of children in Bhutan: results from the 2008 National nutrition survey and trends over time

    Directory of Open Access Journals (Sweden)

    Zangmo Ugyen

    2012-09-01

    Full Text Available Abstract Background There are few reports on the nutritional status of Bhutanese children. The objective of this paper is to summarize results from the 2008 National Nutrition Survey and to describe progress achieved during the last two decades. Methods A cross-sectional survey of 2376 children aged 6 to 59 months was conducted during November-December 2008 to provide national and regional estimates. A multi-stage cluster sampling method was applied and 40 gewogs/thromdes were selected from each region (Western, Central, Eastern. Guidelines on how to measure length/height and weight followed WHO standardized procedures. Data were analysed for consistency and validation using the software WHO Anthro and the WHO SPSS macro. Underweight, stunting, overweight, wasting and thinness were defined based on the WHO Child Growth Standards. Data from 1986-88 and 1999 national surveys were reanalysed using the WHO standards to describe trends in nutritional status. Results Nationally, 34.9% Bhutanese preschool children are stunted and 10.4% are underweight. Wasting is 4.7%, with severe wasting close to 2% in rural areas, while overweight affects 4.4% of preschool children. While underweight rates are similar across regions, wasting is substantially more prevalent in the Western region and stunting in the Eastern region. Stunting shows a steep rise during the first two years of life, as high as 40%, and levels off thereafter, while wasting is greatest among children aged 6-24 months and subsequently decreases. The prevalence of stunting fell from 60.9% in 1986-88 to 34.9% in 2008, and underweight declined from 34.0% to 10.4% during same period. The percentage of wasted children dropped from 5.2% in 1986-88 to 2.5% in 1999 but then increased to 4.7% in 2008. Conclusions There have been major improvements in the nutritional status of Bhutanese children over the past two decades, however, linear growth retardation remains a significant concern. Early

  10. Opening up codings?

    DEFF Research Database (Denmark)

    Steensig, Jakob; Heinemann, Trine

    2015-01-01

    doing formal coding and when doing more “traditional” conversation analysis research based on collections. We are more wary, however, of the implication that coding-based research is the end result of a process that starts with qualitative investigations and ends with categories that can be coded...

  11. Study of neoclassical transport and bootstrap current for W7-X in the 1/upsilon regime, using results from the PIES code

    International Nuclear Information System (INIS)

    Nemov, V V; Kalyuzhnyj, V N; Kasilov, S V; Drevlak, M; Nuehrenberg, J; Kernbichler, W; Reiman, A; Monticello, D

    2004-01-01

    For the magnetic field of the Wendelstein 7-X (W7-X) standard high-mirror configuration, computed by the PIES code, taking into account real coil geometry, neoclassical transport and bootstrap current are analysed in the 1/upsilon regime using methods based on the integration along magnetic field lines in a given magnetic field. The zero beta and (beta) = 1% cases are studied. The results are compared to the corresponding results for the vacuum magnetic field directly produced by modular coils. A significant advantage of W7-X over a conventional stellarator resulting from reduced neoclassical transport and from reduced bootstrap current follows from the computations although the neoclassical transport is somewhat larger than that previously obtained for the ideal W7-X model configuration

  12. Three-dimensional all-speed CFD code for safety analysis of nuclear reactor containment: Status of GASFLOW parallelization, model development, validation and application

    Energy Technology Data Exchange (ETDEWEB)

    Xiao, Jianjun, E-mail: jianjun.xiao@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Travis, John R., E-mail: jack_travis@comcast.com [Engineering and Scientific Software Inc., 3010 Old Pecos Trail, Santa Fe, NM 87505 (United States); Royl, Peter, E-mail: peter.royl@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Necker, Gottfried, E-mail: gottfried.necker@partner.kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Svishchev, Anatoly, E-mail: anatoly.svishchev@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany); Jordan, Thomas, E-mail: thomas.jordan@kit.edu [Institute of Nuclear and Energy Technologies, Karlsruhe Institute of Technology, P.O. Box 3640, 76021 Karlsruhe (Germany)

    2016-05-15

    Highlights: • 3-D scalable semi-implicit pressure-based CFD code for containment safety analysis. • Robust solution algorithm valid for all-speed flows. • Well validated and widely used CFD code for hydrogen safety analysis. • Code applied in various types of nuclear reactor containments. • Parallelization enables high-fidelity models in large scale containment simulations. - Abstract: GASFLOW is a three dimensional semi-implicit all-speed CFD code which can be used to predict fluid dynamics, chemical kinetics, heat and mass transfer, aerosol transportation and other related phenomena involved in postulated accidents in nuclear reactor containments. The main purpose of the paper is to give a brief review on recent GASFLOW code development, validations and applications in the field of nuclear safety. GASFLOW code has been well validated by international experimental benchmarks, and has been widely applied to hydrogen safety analysis in various types of nuclear power plants in European and Asian countries, which have been summarized in this paper. Furthermore, four benchmark tests of a lid-driven cavity flow, low Mach number jet flow, 1-D shock tube and supersonic flow over a forward-facing step are presented in order to demonstrate the accuracy and wide-ranging capability of ICE’d ALE solution algorithm for all-speed flows. GASFLOW has been successfully parallelized using the paradigms of Message Passing Interface (MPI) and domain decomposition. The parallel version, GASFLOW-MPI, adds great value to large scale containment simulations by enabling high-fidelity models, including more geometric details and more complex physics. It will be helpful for the nuclear safety engineers to better understand the hydrogen safety related physical phenomena during the severe accident, to optimize the design of the hydrogen risk mitigation systems and to fulfill the licensing requirements by the nuclear regulatory authorities. GASFLOW-MPI is targeting a high

  13. Development of in-vessel source term analysis code, tracer

    International Nuclear Information System (INIS)

    Miyagi, K.; Miyahara, S.

    1996-01-01

    Analyses of radionuclide transport in fuel failure accidents (generally referred to source terms) are considered to be important especially in the severe accident evaluation. The TRACER code has been developed to realistically predict the time dependent behavior of FPs and aerosols within the primary cooling system for wide range of fuel failure events. This paper presents the model description, results of validation study, the recent model advancement status of the code, and results of check out calculations under reactor conditions. (author)

  14. Coding Partitions

    Directory of Open Access Journals (Sweden)

    Fabio Burderi

    2007-05-01

    Full Text Available Motivated by the study of decipherability conditions for codes weaker than Unique Decipherability (UD, we introduce the notion of coding partition. Such a notion generalizes that of UD code and, for codes that are not UD, allows to recover the ``unique decipherability" at the level of the classes of the partition. By tacking into account the natural order between the partitions, we define the characteristic partition of a code X as the finest coding partition of X. This leads to introduce the canonical decomposition of a code in at most one unambiguouscomponent and other (if any totally ambiguouscomponents. In the case the code is finite, we give an algorithm for computing its canonical partition. This, in particular, allows to decide whether a given partition of a finite code X is a coding partition. This last problem is then approached in the case the code is a rational set. We prove its decidability under the hypothesis that the partition contains a finite number of classes and each class is a rational set. Moreover we conjecture that the canonical partition satisfies such a hypothesis. Finally we consider also some relationships between coding partitions and varieties of codes.

  15. Antismoking messages and current cigarette smoking status in Somaliland: results from the Global Youth Tobacco Survey 2004

    Directory of Open Access Journals (Sweden)

    Muula Adamson S

    2008-05-01

    Full Text Available Abstract Background Tobacco is a leading cause of death globally. There are limited reports on current cigarette smoking prevalence and its associated-antismoking messages among adolescents in conflict zones of the world. We, therefore, conducted secondary analysis of data to estimate the prevalence of current cigarette smoking, and to determine associations of antismoking messages with smoking status. Methods We used data from the Somaliland Global Youth Tobacco Survey (GYTS of 2004 to estimate the prevalence of smoking. We also assessed whether being exposed to anti-smoking media, education and having discussed with family members on the harmful effects of smoking were associated with smoking. Logistic regression analysis was used to assess these associations. Current smoking was defined as having reported smoking cigarettes, even a single puff, in the last 30 days preceding the survey (main outcome. Results Altogether 1563 adolescents participated in the survey. However, 1122 had data on the main outcome. Altogether, 15.8% of the respondents reported having smoked cigarettes (10.3% among males, and 11.1% among females. Factors that were associated with reported non-smoking were: discussing harmful effects of smoking cigarettes with their family members (OR = 0.61, 95% CI 0.52, 0.71; being taught that smoking makes teeth yellow, causes wrinkles and smokers smell badly (OR = 0.62, 95% CI 0.52, 0.74; being taught that people of the respondent's age do not smoke (OR = 0.81, 95% CI 0.69, 0.95; and having reported that religious organizations discouraged young people smoking (OR = 0.70, 95% CI 0.60, 0.82. However, exposure to a lot many antismoking messages at social gatherings was associated with smoking. Exposure to antismoking print media was not associated with smoking status. Conclusion A combination of school and home based antismoking interventions may be effective in controlling adolescent smoking in Somaliland.

  16. Maintenance and improvement of thermal hydraulic system codes using results of OCDE experiments (PKL, Rosa, Atlas) and application to Spanish Nuclear power plants. Camp-Spain project

    International Nuclear Information System (INIS)

    Sanchez, M.; Perez, J.; Martorell, S.; Carlos, S.; Villanueva, J. F.; Sanchez, F.; Queral, C.; Rebollo, M. J.; Rivas-Lewicky, J.; Verdu, G.; Gallardo, S.; Miro, R.; Querol, A.; Munoz-Cobo, J. L.; Escriva, A.; Berna, C.; Reventos, F.; Freixa, J.; Martinez, V.

    2016-01-01

    CSN involvement in different international NEA experimental TH programmes has outlined the scope for a new period of CAMP-Espana activities, currently focused on the: -Analysis, simulation and investigation of specific safety aspects of PKL3/OECD and ATLAS/OECD experiments. -Analysis of applicability and/or extension of the results in these projects to the safety, operation or availability of the Spanish nuclear power plants. Both objective are carried out by simulating experiments and plant application with the last available versions of NRC TH codes (RELAP5 or TRACE). A CAMP in kind contribution (NUREG/IA) is aimed as final result of both types of analyses. Five different national research groups (from Technical Universities of Madrid, Valencia and Cataluna) ate carrying out the development of these activities. (Author)

  17. Monte Carlo code development in Los Alamos

    International Nuclear Information System (INIS)

    Carter, L.L.; Cashwell, E.D.; Everett, C.J.; Forest, C.A.; Schrandt, R.G.; Taylor, W.M.; Thompson, W.L.; Turner, G.D.

    1974-01-01

    The present status of Monte Carlo code development at Los Alamos Scientific Laboratory is discussed. A brief summary is given of several of the most important neutron, photon, and electron transport codes. 17 references. (U.S.)

  18. Opportunistic Adaptive Transmission for Network Coding Using Nonbinary LDPC Codes

    Directory of Open Access Journals (Sweden)

    Cocco Giuseppe

    2010-01-01

    Full Text Available Network coding allows to exploit spatial diversity naturally present in mobile wireless networks and can be seen as an example of cooperative communication at the link layer and above. Such promising technique needs to rely on a suitable physical layer in order to achieve its best performance. In this paper, we present an opportunistic packet scheduling method based on physical layer considerations. We extend channel adaptation proposed for the broadcast phase of asymmetric two-way bidirectional relaying to a generic number of sinks and apply it to a network context. The method consists of adapting the information rate for each receiving node according to its channel status and independently of the other nodes. In this way, a higher network throughput can be achieved at the expense of a slightly higher complexity at the transmitter. This configuration allows to perform rate adaptation while fully preserving the benefits of channel and network coding. We carry out an information theoretical analysis of such approach and of that typically used in network coding. Numerical results based on nonbinary LDPC codes confirm the effectiveness of our approach with respect to previously proposed opportunistic scheduling techniques.

  19. Clinical And Morphological Androgenic Status Characteristics At Children Suffering From Hypospadias And Its Influence On Results Of Surgical Correction

    Directory of Open Access Journals (Sweden)

    F.K. Napolnikov

    2009-09-01

    Full Text Available The goal of this article is to estimate the androgenic status and analyze its influence on the surgical treatment of hypospadias. From 2000 till 2008 there were 209 children under treatment, whose age varied from 8 months till 15 years old (average age — 4,5+ 1,5. 49 patients were subjected to clinical, humoral and morphological study. Preoperational preparation was carried out by testosterone medications. The comparison group consisted of 10 boys with cicatricial phimosis. The patients with the medium and back forms of hypospadias suffered from the androgenic deficit characterized by proximal level of meatus ectopia, diminution of penis length and prostate volume, decrease of blood vessels in deep layers of penis skin. The testosterone pre-operational medication of patients makes possible to improve the results of surgical correction due to blood supply of plastic material. On the basis of recieved data logistically regressive model has been worked out and the prognosis of results has been estimated

  20. Quantitative Evaluation of Medial Temporal Lobe Morphology in Children with Febrile Status Epilepticus: Results of the FEBSTAT Study.

    Science.gov (United States)

    McClelland, A C; Gomes, W A; Shinnar, S; Hesdorffer, D C; Bagiella, E; Lewis, D V; Bello, J A; Chan, S; MacFall, J; Chen, M; Pellock, J M; Nordli, D R; Frank, L M; Moshé, S L; Shinnar, R C; Sun, S

    2016-12-01

    The pathogenesis of febrile status epilepticus is poorly understood, but prior studies have suggested an association with temporal lobe abnormalities, including hippocampal malrotation. We used a quantitative morphometric method to assess the association between temporal lobe morphology and febrile status epilepticus. Brain MR imaging was performed in children presenting with febrile status epilepticus and control subjects as part of the Consequences of Prolonged Febrile Seizures in Childhood study. Medial temporal lobe morphologic parameters were measured manually, including the distance of the hippocampus from the midline, hippocampal height:width ratio, hippocampal angle, collateral sulcus angle, and width of the temporal horn. Temporal lobe morphologic parameters were correlated with the presence of visual hippocampal malrotation; the strongest association was with left temporal horn width (P status epilepticus, encompassing both the right and left sides. This association was statistically strongest in the right temporal lobe, whereas hippocampal malrotation was almost exclusively left-sided in this cohort. The association between temporal lobe measurements and febrile status epilepticus persisted when the analysis was restricted to cases with visually normal imaging findings without hippocampal malrotation or other visually apparent abnormalities. Several component morphologic features of hippocampal malrotation are independently associated with febrile status epilepticus, even when complete hippocampal malrotation is absent. Unexpectedly, this association predominantly involves the right temporal lobe. These findings suggest that a spectrum of bilateral temporal lobe anomalies are associated with febrile status epilepticus in children. Hippocampal malrotation may represent a visually apparent subset of this spectrum. © 2016 by American Journal of Neuroradiology.

  1. Effect of a vitamin and mineral supplementation on glycemic status: Results from a community-based program

    Directory of Open Access Journals (Sweden)

    Samantha M. Kimball

    2017-12-01

    Full Text Available Aims: Diet is a major risk factor for type 2 diabetes mellitus. As cofactors necessary for enzyme function of all metabolic pathways, vitamins and minerals have the potential to improve glucose metabolism. We investigated the effects of a nutrient intervention program on glycemic status. Methods: We used a form of natural experiment to compare Pure North program participants (n = 1018 that received vitamin D alone (Vital 1 or vitamin D in combination with other nutrients (Vital 2 during two different time periods. Changes in 25-hydroxyvitamin D [25(OHD], high-sensitivity C reactive protein (hs-CRP, glycated hemoglobin (HbA1c and glycemic status were characterized over one and two years. Results: Serum 25(OHD concentrations increased significantly in both Vital 1 (to 111  ±  49 nmol/L and Vital 2 (to 119  ±  52 nmol/L over one year. HbA1c and hs-CRP were significantly reduced over time in Vital 2. Higher 25(OHD levels after one year were associated with larger decreases in HbA1c and hs-CRP in Vital 2. At one year, 8% of Vital 2 and 16% of Vital 1 participants progressed from normoglycemia to prediabetes/diabetes, whereas 44% of Vital 2 and 8% of Vital prediabetes/diabetes subjects regressed to normoglycemia. Conclusions: Vitamin D combined with other nutrients was associated with a reduced risk of progression to diabetes and with an increased rate of reversion to normoglycemia in high risk participants. The results suggest that nutrient supplementation regimes may provide a safe, economical and effective means for lowering diabetes risk. Further examination of this potential via randomized controlled trials is warranted. Keywords: Prediabetes, Type 2 diabetes mellitus, Vitamin D, Nutritional supplements, Multivitamin, Normoglycemia

  2. Coding for Electronic Mail

    Science.gov (United States)

    Rice, R. F.; Lee, J. J.

    1986-01-01

    Scheme for coding facsimile messages promises to reduce data transmission requirements to one-tenth current level. Coding scheme paves way for true electronic mail in which handwritten, typed, or printed messages or diagrams sent virtually instantaneously - between buildings or between continents. Scheme, called Universal System for Efficient Electronic Mail (USEEM), uses unsupervised character recognition and adaptive noiseless coding of text. Image quality of resulting delivered messages improved over messages transmitted by conventional coding. Coding scheme compatible with direct-entry electronic mail as well as facsimile reproduction. Text transmitted in this scheme automatically translated to word-processor form.

  3. Accuracy of Korean-Mini-Mental Status Examination Based on Seoul Neuro-Psychological Screening Battery II Results.

    Science.gov (United States)

    Kang, In-Woong; Beom, In-Gyu; Cho, Ji-Yeon; Son, Hyo-Rim

    2016-05-01

    The Korean-Mini-Mental Status Examination (K-MMSE) is a dementia-screening test that can be easily applied in both community and clinical settings. However, in 20% to 30% of cases, the K-MMSE produces a false negative response. This suggests that it is necessary to evaluate the accuracy of K-MMSE as a screening test for dementia, which can be achieved through comparison of K-MMSE and Seoul Neuropsychological Screening Battery (SNSB)-II results. The study included 713 subjects (male 534, female 179; mean age, 69.3±6.9 years). All subjects were assessed using K-MMSE and SNSB-II tests, the results of which were divided into normal and abnormal in 15 percentile standards. The sensitivity of the K-MMSE was 48.7%, with a specificity of 89.9%. The incidence of false positive and negative results totaled 10.1% and 51.2%, respectively. In addition, the positive predictive value of the K-MMSE was 87.1%, while the negative predictive value was 55.6%. The false-negative group showed cognitive impairments in regions of memory and executive function. Subsequently, in the false-positive group, subjects demonstrated reduced performance in memory recall, time orientation, attention, and calculation of K-MMSE items. The results obtained in the study suggest that cognitive function might still be impaired even if an individual obtained a normal score on the K-MMSE. If the K-MMSE is combined with tests of memory or executive function, the accuracy of dementia diagnosis could be greatly improved.

  4. Vegetarianism and colorectal cancer risk in a low-selenium environment: effect modification by selenium status? A possible factor contributing to the null results in British vegetarians.

    Science.gov (United States)

    Sobiecki, Jakub G

    2017-08-01

    Despite the consistent findings of lower total cancer incidence in vegetarians than in meat-eaters in the UK, the results of studies of colorectal cancer (CRC) risk in British vegetarians have largely been null. This was in contrast to the hypothesis of a decreased risk of CRC in this population due to null intake of red and processed meats and increased intake of fibre. Although the data are inconsistent, it has been suggested that selenium (Se) status may influence CRC risk. A literature review was performed of studies on CRC risk in vegetarians, Se intakes and status in vegetarians, and changes of Se intakes and status in the UK throughout the follow-up periods of studies on CRC risk in British vegetarians. Vegetarians in the UK and other low-Se areas were found to have low Se intakes and status compared to non-vegetarians. There was some evidence of a reverse J-shaped curve of Se intakes and status in the UK throughout the last three decades. These presumed patterns were followed by the changes in CRC mortality or incidence in British vegetarians during this period. Available data on Se intake and status in British vegetarians, as well as the relationship between their secular changes in the UK and changes in CRC risk in this dietary group, are compatible with the hypothesis that low Se status may contribute to the largely null results of studies of CRC risk in vegetarians in the UK.

  5. Comprehensive Status and Trends of Nitrogen Loads to Estuaries in the Conterminous United States: Pacific Coast Results

    Science.gov (United States)

    We applied regional SPARROW (SPAtially Referenced Regressions On Watershed attributes) models to estimate status and trends of potential nitrogen loads to estuaries of the conterminous United States. The original Regional SPARROW models predict average detrended loads by source ...

  6. Results of preoperative electrical stimulation of pelvic floor muscles in the continence status following radical retropubic prostatectomy

    Directory of Open Access Journals (Sweden)

    Carla Elaine Laurienzo

    2013-04-01

    Full Text Available Purpose To evaluate preoperative rectal electrical stimulation in the recovery of urinary continence in patients who undergo radical retropubic prostatectomy. Materials and Methods Patients were divided into 3 randomized groups: control, pelvic exercises, and electrical stimulation. A 1 hour pad-test, the ICIQ-SF, and the SF-36 were performed 1, 3, and 6 months after the surgical procedure. Results Of the 58 patients who were initially included in the study, 9 were excluded due to radiotherapy after surgical intervention, an indwelling urethral catheter for more than 30 days, high surgical risk, loss of follow-up, or incomplete participation in the study routines and spontaneous interruption. Forty-nine patients concluded the study (15 in the control group, 17 in the exercise group, and 17 in the electrical stimulation group. We did not observe any significant difference in the pad test (p > 0.05, the 8 domains of the SF-36, or ICIQ-SF score compared with control groups (control, exercise, and electrical stimulation. Conclusion Preoperative rectal electrical stimulation has no impact on continence status in patients who undergo radical retropubic prostatectomy. There is no difference in the three above mentioned groups with regard to urinary leakage and quality of life.

  7. Prevalence of sarcopenia in a population of nursing home residents according to their frailty status: results of the SENIOR cohort

    Science.gov (United States)

    Buckinx, F.; Reginster, J-Y.; Brunois, T.; Lenaerts, C.; Beaudart, C.; Croisier, J-L.; Petermans, J.; Bruyère, O.

    2017-01-01

    Objective: To investigate the relationship between frailty and sarcopenia, by evaluating the prevalence of sarcopenia among frail, pre-frail and robust elderly nursing home residents in Belgium. Methods: This is an analysis of baseline data collected from the SENIOR (Sample of Elderly Nursing home Individuals: an Observational Research) cohort. All subjects received a sarcopenia evaluation, based on the definition proposed by the European Working Group on Sarcopenia in Older People (EWGSOP). The frailty evaluation was primarily based on FRIED’s definition but also on 9 other operational definitions. Results: A total of 662 subjects (73.1% of women) were included in this analysis (mean age: 83.2±8.99 years). The prevalence of sarcopenia was 38.1% whereas the prevalence of frail and pre-frail persons was respectively 24.7% and 61.4%. Among frail, pre-frail and robust subjects, respectively 47%, 38.9% and 16.3% were diagnosed sarcopenic. The prevalence of sarcopenia according to ten different operational definitions of frailty ranged between 32.8 % (i.e. Frail scale Status and Frailty Index) and 47% (i.e. Fried definition). Conclusion: This research highlights that over a third of nursing home residents are sarcopenic and the percentage is almost 50% among frail subjects; those latter constitute about 1 in 4 of the population of nursing home residents studied here. PMID:28860423

  8. Socioeconomic Status and Age Variations in Health-Related Quality of Life: Results From the National Health Measurement Study

    Science.gov (United States)

    Cherepanov, Dasha; Palta, Mari; Dunham, Nancy Cross; Feeny, David; Fryback, Dennis G.

    2009-01-01

    Objectives We examine whether multiple health-related quality of life (HRQoL) measures are stratified by socioeconomic status (SES) and age in the United States. Methods Data are from the 2005/2006 National Health Measurement Study, a telephone survey of a nationally representative sample of U.S. adults. We plot mean HRQoL scores by SES within age groups. Regression analyses test whether education, income, and assets each have independent associations with three “preference-based” HRQoL measures and self-rated health (SRH). We test whether these associations vary by age. Results There are SES disparities in HRQoL and SRH among adults in the United States at all age groups. Income differentials in HRQoL are strong across current adult age cohorts, except the 75–89 age cohort. Education and assets have statistically significant but weaker associations with HRQoL. All three SES measures are associated with SRH (net of each other) at every age group. Those in the lowest income and education groups in the 35–44 age cohort have worse HRQoL and SRH than those in higher SES groups in the 65+ age cohort. Discussion Significant improvements in HRQoL at the population level will only be possible if we improve the HRQoL of people at the lowest end of the socioeconomic distribution. PMID:19307286

  9. The ATLAS level-1 trigger: Status of the system and first results from cosmic-ray data

    Energy Technology Data Exchange (ETDEWEB)

    Aielli, G [Universita degli Studi di Roma ' Tor Vergata' and INFN Roma II, Rome (Italy); Andrei, V; Achenbach, R [Kirchhoff-Institut fuer Physik, University of Heidelberg, D-69120 Heidelberg (Germany); Adragna, P [Physics Department, Queen Mary, University of London, London E1 4NS (United Kingdom); Aloisio, A; Alviggi, M G [Universita degli Studi di Napoli ' Federico II' and INFN Napoli (Italy); Antonelli, S [INFN Bologna and Universita degli Studi di Bologna (Italy); Ask, S [CERN, PH Department (Switzerland); Barnett, B M [CCLRC Rutherford Appleton Laboratory, Chilton, Didcot, Oxon OX11 0QX (United Kingdom); Bauss, B [Institut fuer Physik, University of Mainz, D-55099 Mainz (Germany); Bellagamba, L [INFN Bologna and Universita degli Studi di Bologna (Italy); Ben Ami, S [Technion Israel Institute of Technology (Israel); Bendel, M [Institut fuer Physik, University of Mainz, D-55099 Mainz (Germany); Benhammou, Y [Tel Aviv University (Israel); Berge, D. [CERN, PH Department (Switzerland)], E-mail: David.Berge@cern.ch; Bianco, M [Universita degli Studi di Lecce and INFN Lecce (Italy); Biglietti, M G [Universita degli Studi di Napoli ' Federico II' and INFN Napoli (Italy); Bohm, C [Fysikum, University of Stockholm, SE-10691 Stockholm (Sweden); Booth, J R.A. [School of Physics and Astronomy, University of Birmingham, Birmingham B15 2TT (United Kingdom); CCLRC Rutherford Appleton Laboratory, Chilton, Didcot, Oxon OX11 0QX (United Kingdom); Boscherini, D [INFN Bologna and Universita degli Studi di Bologna (Italy)

    2007-10-21

    The ATLAS detector at CERN's Large Hadron Collider (LHC) will be exposed to proton-proton collisions from beams crossing at 40 MHz. At the design luminosity of 10{sup 34}cm{sup -2}s{sup -1} there are on average 23 collisions per bunch crossing. A three-level trigger system will select potentially interesting events in order to reduce the readout rate to about 200 Hz. The first trigger level is implemented in custom-built electronics and makes an initial fast selection based on detector data of coarse granularity. It has to reduce the rate by a factor of 10{sup 4} to less than 100 kHz. The other two consecutive trigger levels are in software and run on PC farms. We present an overview of the first-level trigger system and report on the current installation status. Moreover, we show analysis results of cosmic-ray data recorded in situ at the ATLAS experimental site with final or close-to-final hardware.

  10. The ATLAS level-1 trigger: Status of the system and first results from cosmic-ray data

    International Nuclear Information System (INIS)

    Aielli, G.; Andrei, V.; Achenbach, R.; Adragna, P.; Aloisio, A.; Alviggi, M.G.; Antonelli, S.; Ask, S.; Barnett, B.M.; Bauss, B.; Bellagamba, L.; Ben Ami, S.; Bendel, M.; Benhammou, Y.; Berge, D.; Bianco, M.; Biglietti, M.G.; Bohm, C.; Booth, J.R.A.; Boscherini, D.

    2007-01-01

    The ATLAS detector at CERN's Large Hadron Collider (LHC) will be exposed to proton-proton collisions from beams crossing at 40 MHz. At the design luminosity of 10 34 cm -2 s -1 there are on average 23 collisions per bunch crossing. A three-level trigger system will select potentially interesting events in order to reduce the readout rate to about 200 Hz. The first trigger level is implemented in custom-built electronics and makes an initial fast selection based on detector data of coarse granularity. It has to reduce the rate by a factor of 10 4 to less than 100 kHz. The other two consecutive trigger levels are in software and run on PC farms. We present an overview of the first-level trigger system and report on the current installation status. Moreover, we show analysis results of cosmic-ray data recorded in situ at the ATLAS experimental site with final or close-to-final hardware

  11. Human epidermal growth factor receptor 2 status of gastric cancer patients in Asia: results from a large, multicountry study.

    Science.gov (United States)

    Pathmanathan, Nirmala; Geng, Jing-Shu; Li, Wencai; Nie, Xiu; Veloso, Januario; Wang, John; Hill, Julie; Mccloud, Philip; Bilous, Michael

    2017-06-01

    Current estimates of the human epidermal growth factor receptor 2 (HER2)-positivity rate in gastric cancer vary widely in the literature, and there are limited data from countries in Asia. The primary aim of this study was to conduct a clinical audit of laboratories across seven countries in Asia to determine the incidence of HER2-positive gastric cancer in this region. Pathologists were asked to collect data on patient gender, age, cancer site, specimen type, tumor spread, type and grade, HER2 test results, including protein and/or gene copy enumeration, and final HER2 status on consecutive gastric cancer cases tested for HER2 in their laboratory over a 2-year period. HER2 results from 5,301 gastric cancers were submitted by 50 laboratories. The overall HER2-positivity rate was 9.7% which, after the exclusion of China, increased to 18.1%. The rate between countries ranged from 0% to 23.1%, and from 0% to 50.0% between laboratories. An equivocal HER2 result was recorded in 19.5% of cases. Despite the lack of centralized testing to confirm the accuracy of HER2 diagnoses, the incidence of HER2-positive gastric cancer observed here was comparable to that reported in the literature. Nevertheless, rates were highly variable between countries and laboratories, which suggests a lack of HER2 testing expertise in gastric cancer. Given that the mortality rates for gastric cancer in Eastern Asia are the highest in the world, efforts should focus on improving HER2 testing expertise in the region so that patients receive the appropriate treatment early in their disease. © 2016 The Authors. Asia-Pacific Journal of Clinical Oncology Published by John Wiley & Sons Australia, Ltd.

  12. The sphere-PAC fuel code 'SPHERE-3'

    International Nuclear Information System (INIS)

    Wallin, H.

    2000-01-01

    Sphere-PAC fuel is an advanced nuclear fuel, in which the cladding tube is filled with small fuel spheres instead of the more usual fuel pellets. At PSI, the irradiation behaviour of sphere-PAC fuel is calculated using the computer code SPHERE-3. The paper describes the present status of the SPHERE-3 code, and some results of the qualification process against experimental data. (author)

  13. The sphere-pac fuel code 'SPHERE-3'

    International Nuclear Information System (INIS)

    Wallin, H.; Nordstroem, L.A.; Hellwig, C.

    2001-01-01

    Sphere-pac fuel is an advanced nuclear fuel, in which the cladding tube is filled with small fuel spheres instead of the more usual fuel pellets. At PSI, the irradiation behaviour of sphere-pac fuel is calculated using the computer code SPHERE-3. The paper describes the present status of the SPHERE-3 code, and some results of the qualification process against experimental data. (author)

  14. Computer codes developed in FRG to analyse hypothetical meltdown accidents

    International Nuclear Information System (INIS)

    Hassmann, K.; Hosemann, J.P.; Koerber, H.; Reineke, H.

    1978-01-01

    It is the purpose of this paper to give the status of all significant computer codes developed in the core melt-down project which is incorporated in the light water reactor safety research program of the Federal Ministry of Research and Technology. For standard pressurized water reactors, results of some computer codes will be presented, describing the course and the duration of the hypothetical core meltdown accident. (author)

  15. Status of the MCNPtrademark/LCStrademark merger project

    International Nuclear Information System (INIS)

    Hughes, H.G.; Adams, K.J.; Chadwick, M.B.; Comly, J.C.; Frankle, S.C.; Hendricks, J.S.; Little, R.C.; Prael, R.E.; Waters, L.S.; Young, P.G.

    1998-01-01

    The MCNPX code is now in limited release in a beta-test version. We provide a brief status report on the physics modules now in the code and of the enhanced capabilities to use new evaluated neutron data. We also present new benchmark calculations in which LAHET and MCNPX are compared with experimental results from the Japan Atomic Energy Research Institute

  16. Uncertainty analysis for results of thermal hydraulic codes of best-estimate-type; Analisis de incertidumbre para resultados de codigos termohidraulicos de mejor estimacion

    Energy Technology Data Exchange (ETDEWEB)

    Alva N, J.

    2010-07-01

    In this thesis, some fundamental knowledge is presented about uncertainty analysis and about diverse methodologies applied in the study of nuclear power plant transient event analysis, particularly related to thermal hydraulics phenomena. These concepts and methodologies mentioned in this work come from a wide bibliographical research in the nuclear power subject. Methodologies for uncertainty analysis have been developed by quite diverse institutions, and they have been widely used worldwide for application to results from best-estimate-type computer codes in nuclear reactor thermal hydraulics and safety analysis. Also, the main uncertainty sources, types of uncertainties, and aspects related to best estimate modeling and methods are introduced. Once the main bases of uncertainty analysis have been set, and some of the known methodologies have been introduced, it is presented in detail the CSAU methodology, which will be applied in the analyses. The main objective of this thesis is to compare the results of an uncertainty and sensibility analysis by using the Response Surface Technique to the application of W ilks formula, apply through a loss coolant experiment and an event of rise in a BWR. Both techniques are options in the part of uncertainty and sensibility analysis of the CSAU methodology, which was developed for the analysis of transients and accidents at nuclear power plants, and it is the base of most of the methodologies used in licensing of nuclear power plants practically everywhere. Finally, the results of applying both techniques are compared and discussed. (Author)

  17. Production of neutronic discrete equations for a cylindrical geometry in one group energy and benchmark the results with MCNP-4B code with one group energy library

    International Nuclear Information System (INIS)

    Salehi, A. A.; Vosoughi, N.; Shahriari, M.

    2002-01-01

    In reactor core neutronic calculations, we usually choose a control volume and investigate about the input, output, production and absorption inside it. Finally, we derive neutron transport equation. This equation is not easy to solve for simple and symmetrical geometry. The objective of this paper is to introduce a new direct method for neutronic calculations. This method is based on physics of problem and with meshing of the desired geometry, writing the balance equation for each mesh intervals and with notice to the conjunction between these mesh intervals, produce the final discrete equation series without production of neutron transport differential equation and mandatory passing form differential equation bridge. This method, which is named Direct Discrete Method, was applied in static state, for a cylindrical geometry in one group energy. The validity of the results from this new method are tested with MCNP-4B code with a one group energy library. One energy group direct discrete equation produces excellent results, which can be compared with the results of MCNP-4B

  18. QR code for medical information uses.

    Science.gov (United States)

    Fontelo, Paul; Liu, Fang; Ducut, Erick G

    2008-11-06

    We developed QR code online tools, simulated and tested QR code applications for medical information uses including scanning QR code labels, URLs and authentication. Our results show possible applications for QR code in medicine.

  19. Monte Carlo simulation of nuclear energy study (II). Annual report on Nuclear Code Evaluation Committee

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2001-01-01

    In the report, research results discussed in 1999 fiscal year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. Present status of Monte Carlo simulation on nuclear energy study was described. Especially, besides of criticality, shielding and core analyses, present status of applications to risk and radiation damage analyses, high energy transport and nuclear theory calculations of Monte Carlo Method was described. The 18 papers are indexed individually. (J.P.N.)

  20. An algebraic approach to graph codes

    DEFF Research Database (Denmark)

    Pinero, Fernando

    This thesis consists of six chapters. The first chapter, contains a short introduction to coding theory in which we explain the coding theory concepts we use. In the second chapter, we present the required theory for evaluation codes and also give an example of some fundamental codes in coding...... theory as evaluation codes. Chapter three consists of the introduction to graph based codes, such as Tanner codes and graph codes. In Chapter four, we compute the dimension of some graph based codes with a result combining graph based codes and subfield subcodes. Moreover, some codes in chapter four...

  1. BOT3P5.2, 3D Mesh Generator and Graphical Display of Geometry for Radiation Transport Codes, Display of Results

    International Nuclear Information System (INIS)

    Orsi, Roberto; Bidaud, Adrien

    2007-01-01

    1 - Description of program or function: BOT3P was originally conceived as a set of standard FORTRAN 77 language programs in order to give the users of the DORT and TORT deterministic transport codes some useful diagnostic tools to prepare and check their input data files. Later versions extended the possibility to produce the geometrical, material distribution and fixed neutron source data to other deterministic transport codes such as TWODANT/THREEDANT of the DANTSYS system, PARTISN and, potentially, to any transport code through BOT3P binary output files that can be easily interfaced (see, for example, the Russian two-dimensional (2D) and three-dimensional (3D) discrete ordinates neutron, photon and charged particle transport codes KASKAD-S-2.5 and KATRIN-2.0). As from Version 5.1 BOT3P contained important additions specifically addressed to radiation transport analysis for medical applications. BOT3P-5.2 contains new graphics capabilities. Some of them enable users to select space sub-domains of the total mesh grid in order to improve the zoom simulation of the geometry, both in 2D cuts and in 3D. Moreover the new BOT3P module (PDTM) may improve the interface of BOT3P geometrical models to transport analysis codes. The following programs are included in the BOT3P software package: GGDM, DDM, GGTM, DTM2, DTM3, RVARSCL, COMPARE, MKSRC, CATSM, DTET, and PDTM. The main features of these different programs are described. 2 - Methods: GGDM and GGTM work similarly from the logical point of view. Since the 3D case is more general, the following description refers to GGTM. All the co-ordinate values that characterise the geometrical scheme at the basis of the 3D transport code geometrical and material model are read, sorted and all stored if different from the neighbouring ones more than an input tolerance established by the user. These co-ordinates are always present in the fine-mesh boundary arrays independently of the mesh grid refinement options, because they

  2. The role of socio-economic status in depression: results from the COURAGE (aging survey in Europe

    Directory of Open Access Journals (Sweden)

    Aislinne Freeman

    2016-10-01

    Full Text Available Abstract Background Low socio-economic status (SES has been found to be associated with a higher prevalence of depression. However, studies that have investigated this association have been limited in their national scope, have analyzed different components of SES separately, and have not used standardized definitions or measurements across populations. The aim of the current study was to evaluate the association between SES and depression across three European countries that represent different regions across Europe, using standardized procedures and measurements and a composite score for SES. Method Nationally-representative data on 10,800 individuals aged ≥18 from the Collaborative Research on Ageing in Europe (COURAGE survey conducted in Finland, Poland and Spain were analyzed in this cross-sectional study. An adapted version of the Composite International Diagnostic Interview was used to identify the presence of depression, and SES was computed by using the combined scores of the total number of years educated (0–22 and the quintiles of the country-specific income level of the household (1–5. Multivariable logistic regression was used to assess the association between SES and depression. Results Findings reveal a significant association between depression and SES across all countries (p ≤ 0.001. After adjusting for confounders, the odds of depression were significantly decreased for every unit increase in the SES index for Finland, Poland and Spain. Additionally, higher education significantly decreased the odds for depression in each country, but income did not. Conclusion The SES index seems to predict depression symptomatology across European countries. Taking SES into account may be an important factor in the development of depression prevention strategies across Europe.

  3. Cancer and heart attack survivors' expectations of employment status: results from the English Longitudinal Study of Ageing.

    Science.gov (United States)

    Duijts, Saskia F A; van der Beek, Allard J; Bleiker, Eveline M A; Smith, Lee; Wardle, Jane

    2017-08-07

    Sociodemographic, health- and work-related factors have been found to influence return to work in cancer survivors. It is feasible though that behavioural factors, such as expectation of being at work, could also affect work-related outcomes. Therefore, the effect of earlier identified factors and expectation of being at work on future employment status in cancer survivors was explored. To assess the degree to which these factors specifically concern cancer survivors, a comparison with heart attack survivors was made. Data from the English Longitudinal Study of Ageing were used. Cancer and heart attack survivors of working age in the UK were included and followed up for 2 years. Baseline characteristics of both cancer and heart attack survivors were compared regarding employment status. Univariate and multivariate regression analyses were performed in survivors at work, and the interaction between independent variables and diagnose group was assessed. In cancer survivors at work (N = 159), alcohol consumption, participating in moderate or vigorous sport activities, general health and participation were univariate associated with employment status at two-year follow-up. Only fair general health (compared to very good general health) remained statistically significant in the multivariate model (OR 0.31; 95% CI 0.13-0.76; p = 0.010). In heart attack survivors at work (N = 78), gender, general health and expectation of being at work were univariate associated with employment status at follow-up. Female gender (OR 0.03; 95% CI 0.00-0.57; p = 0.018) and high expectation of being at work (OR 10.68; 95% CI 1.23-93.92; p = 0.033) remained significant in the multivariate model. The influence of gender (p = 0.066) and general health (p = 0.020) regarding employment status was found to differ significantly between cancer and heart attack survivors. When predicting future employment status in cancer survivors in the UK, general health is the most relevant factor

  4. Comparative study of Thermal Hydraulic Analysis Codes for Pressurized Water Reactors

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Yang Hoon; Jang, Mi Suk; Han, Kee Soo [Nuclear Engineering Service and Solution Co. Ltd., Daejeon (Korea, Republic of)

    2015-05-15

    Various codes are used for the thermal hydraulic analysis of nuclear reactors. The use of some codes among these is limited by user and some codes are not even open to general person. Thus, the use of alternative code is considered for some analysis. In this study, simple thermal hydraulic behaviors are analyzed using three codes to show that alternative codes are possible for the analysis of nuclear reactors. We established three models of the simple u-tube manometer using three different codes. RELAP5 (Reactor Excursion and Leak Analysis Program), SPACE (Safety and Performance Analysis CodE for nuclear power Plants), GOTHIC (Generation of Thermal Hydraulic Information for Containments) are selected for this analysis. RELAP5 is widely used codes for the analysis of system behavior of PWRs. SPACE has been developed based on RELAP5 for the analysis of system behavior of PWRs and licensing of the code is in progress. And GOTHIC code also has been widely used for the analysis of thermal hydraulic behavior in the containment system. The internal behavior of u-tube manometer was analyzed by RELAP5, SPACE and GOTHIC codes. The general transient behavior was similar among 3 codes. However, the stabilized status of the transient period analyzed by REPAP5 was different from the other codes. It would be resulted from the different physical models used in the other codes, which is specialized for the multi-phase thermal hydraulic behavior analysis.

  5. Speaking Code

    DEFF Research Database (Denmark)

    Cox, Geoff

    Speaking Code begins by invoking the “Hello World” convention used by programmers when learning a new language, helping to establish the interplay of text and code that runs through the book. Interweaving the voice of critical writing from the humanities with the tradition of computing and software...

  6. Irradiation of Argentine (U,Pu)O2 MOX fuels. Post-irradiation results and experimental analysis with the BACO code

    International Nuclear Information System (INIS)

    Marino, A.C.; Perez, E.; Adelfang, P.

    1996-01-01

    The irradiation of the first Argentine prototypes of pressurized heavy water reactor (PHWR) (U,Pu)O 2 MOX fuels began in 1986. These experiments were carried out in the High Flux Reactor (HFR)-Petten, Holland. The rods were prepared and controlled in the C NEA's α Facility. The postirradiation examinations were performed in the Kernforschungszentrum, Karlsruhe, Germany and in the Joint Research Center (JRC), Petten. The first rod has been used for destructive pre-irradiation analysis. The second one as a pathfinder to adjust systems in the HFR. Two additional rods including iodine doped pellets were intended to simulate 15000 MWd/T(M) burnup. The remaining two rods were irradiated until 15000 MWd/T(M). One of them underwent a final ramp with the aim of verifying fabrication processes and studying the behaviour under power transients. BACO (BArra COmbustible) code was used to define the power histories and to analyse the experiments. This paper presents a description of the different experiments and a comparison between the results of the postirradiation examinations and the BACO outputs. (orig.)

  7. Irradiation of Argentine (U,Pu)O 2 MOX fuels. Post-irradiation results and experimental analysis with the BACO code

    Science.gov (United States)

    Marino, Armando Carlos; Pérez, Edmundo; Adelfang, Pablo

    1996-04-01

    The irradiation of the first Argentine prototypes of pressurized heavy water reactor (PHWR) (U,Pu)O 2 MOX fuels began in 1986. These experiments were carried out in the High Flux Reactor (HFR)-Petten, Holland. The rods were prepared and controlled in the CNEA's α Facility. The postirradiation examinations were performed in the Kernforschungszentrum, Karlsruhe, Germany and in the Joint Research Center (JRC), Petten. The first rod has been used for destructive pre-irradiation analysis. The second one as a pathfinder to adjust systems in the HFR. Two additional rods including iodine doped pellets were intended to simulate 15 000 MWd/T(M) burnup. The remaining two rods were irradiated until 15 000 MWd/T(M). One of them underwent a final ramp with the aim of verifying fabrication processes and studying the behaviour under power transients. BACO (BArra COmbustible) code was used to define the power histories and to analyse the experiments. This paper presents a description of the different experiments and a comparison between the results of the postirradiation examinations and the BACO outputs.

  8. QR codes for dummies

    CERN Document Server

    Waters, Joe

    2012-01-01

    Find out how to effectively create, use, and track QR codes QR (Quick Response) codes are popping up everywhere, and businesses are reaping the rewards. Get in on the action with the no-nonsense advice in this streamlined, portable guide. You'll find out how to get started, plan your strategy, and actually create the codes. Then you'll learn to link codes to mobile-friendly content, track your results, and develop ways to give your customers value that will keep them coming back. It's all presented in the straightforward style you've come to know and love, with a dash of humor thrown

  9. results

    Directory of Open Access Journals (Sweden)

    Salabura Piotr

    2017-01-01

    Full Text Available HADES experiment at GSI is the only high precision experiment probing nuclear matter in the beam energy range of a few AGeV. Pion, proton and ion beams are used to study rare dielectron and strangeness probes to diagnose properties of strongly interacting matter in this energy regime. Selected results from p + A and A + A collisions are presented and discussed.

  10. Sex differences in adult outcomes by changes in weight status from adolescence to adulthood: results from Add Health.

    Science.gov (United States)

    Chung, Arlene E; Skinner, Asheley Cockrell; Maslow, Gary R; Halpern, Carolyn T; Perrin, Eliana M

    2014-01-01

    Changes in weight status from adolescence to adulthood may be associated with varying social, vocational, economic, and educational outcomes, which may differ by sex. We studied whether there are differences in adult outcomes by sex for different weight status changes in the transition to adulthood. Using data from the National Longitudinal Study of Adolescent Health, participants were categorized by weight status from adolescence into adulthood. We examined self-reported outcomes in adulthood for living with parents, being married, being a parent, employment, receipt of public assistance, income, and college graduation by weight groupings (healthy-healthy, healthy-overweight/obese, overweight/obese-overweight/obese, overweight/obese-healthy). The effect of changes in weight status on the adult outcomes was modeled, controlling for sex, age, parental education, and race/ethnicity. There were differences by sex for many of the self-reported outcomes, especially educational and economic outcomes. Female subjects who became overweight/obese between adolescence and adulthood or remained so had worse economic and educational findings as adults compared to male subjects. Overall, for female subjects, becoming and remaining overweight/obese was associated with worse outcomes, while for male subjects, adolescent obesity was more important than isolated adult obesity. The relationship between obesity and life situations may be more negative for female subjects in the transition to adulthood. The findings emphasize that adolescent obesity, and not just obesity isolated in adulthood, is important for characteristics achieved in adulthood. Copyright © 2014 Academic Pediatric Association. Published by Elsevier Inc. All rights reserved.

  11. Sexual behaviors, relationships, and perceived health status among adult women in the United States: results from a national probability sample.

    Science.gov (United States)

    Herbenick, Debby; Reece, Michael; Schick, Vanessa; Sanders, Stephanie A; Dodge, Brian; Fortenberry, J Dennis

    2010-10-01

    Past surveys of sexual behavior have demonstrated that female sexual behavior is influenced by medical and sociocultural changes. To be most attentive to women and their sexual lives, it is important to have an understanding of the continually evolving sexual behaviors of contemporary women in the United States. The purpose of this study, the National Survey of Sexual Health and Behavior (NSSHB), was to, in a national probability survey of women ages 18-92, assess the proportion of women in various age cohorts who had engaged in solo and partnered sexual activities in the past 90 days and to explore associations with participants' sexual behavior and their relationship and perceived health status. Past year frequencies of masturbation, vaginal intercourse, and anal intercourse were also assessed. A national probability sample of 2,523 women ages 18 to 92 completed a cross-sectional internet based survey about their sexual behavior. Relationship status; perceived health status; experience of solo masturbation, partnered masturbation, giving oral sex, receiving oral sex, vaginal intercourse, anal intercourse, in the past 90 days; frequency of solo masturbation, vaginal intercourse, and anal intercourse in the past year. Recent solo masturbation, oral sex, and vaginal intercourse were prevalent among women, decreased with age, and varied in their associations with relationship and perceived health status. Recent anal sex and same-sex oral sex were uncommonly reported. Solo masturbation was most frequent among women ages 18 to 39, vaginal intercourse was most frequent among women ages 18 to 29 and anal sex was infrequently reported. Contemporary women in the United States engage in a diverse range of solo and partnered sexual activities, though sexual behavior is less common and more infrequent among older age cohorts. © 2010 International Society for Sexual Medicine.

  12. Cigarette smoking, pocket money and socioeconomic status: results from a national survey of 4th form students in 2000.

    Science.gov (United States)

    Scragg, Robert; Laugesen, Murray; Robinson, Elizabeth

    2002-07-26

    To investigate whether pocket money amount and socio-economic status are risk factors for smoking in 14 and 15 year old children. This was a national cross-sectional survey of 4th form students who answered an anonymous self-administered questionnaire in November 2000. Socio-economic status was determined from the Ministry of Education school socio-economic deciles. Questionnaires from 14793 girls and 14577 boys were analysed. Socioeconomic status (SES) was inversely associated with smoking prevalence in girls only (ppocket money than those in high SES decile schools (ppocket money >$30, $21-30, or $11-20, the adjusted relative risks for smoking > or = monthly were 1.73 (95% CI 1.61, 1.85), 1.48 (1.35, 1.62), and 1.15 (1.03, 1.28) in girls, and 1.57 (1.46, 1.70), 1.32 (1.19, 1.46), and 1.11 (1.00, 1.23) in boys, respectively. The proportion of smokers purchasing cigarettes increased with amount of pocket money received in the last 30 days (ppocket money amount in adolescents. This finding has important public health significance, but further research is required to determine if the association is causal.

  13. Coding Labour

    Directory of Open Access Journals (Sweden)

    Anthony McCosker

    2014-03-01

    Full Text Available As well as introducing the Coding Labour section, the authors explore the diffusion of code across the material contexts of everyday life, through the objects and tools of mediation, the systems and practices of cultural production and organisational management, and in the material conditions of labour. Taking code beyond computation and software, their specific focus is on the increasingly familiar connections between code and labour with a focus on the codification and modulation of affect through technologies and practices of management within the contemporary work organisation. In the grey literature of spreadsheets, minutes, workload models, email and the like they identify a violence of forms through which workplace affect, in its constant flux of crisis and ‘prodromal’ modes, is regulated and governed.

  14. Short-term memory coding in children with intellectual disabilities.

    Science.gov (United States)

    Henry, Lucy

    2008-05-01

    To examine visual and verbal coding strategies, I asked children with intellectual disabilities and peers matched for MA and CA to perform picture memory span tasks with phonologically similar, visually similar, long, or nonsimilar named items. The CA group showed effects consistent with advanced verbal memory coding (phonological similarity and word length effects). Neither the intellectual disabilities nor MA groups showed evidence for memory coding strategies. However, children in these groups with MAs above 6 years showed significant visual similarity and word length effects, broadly consistent with an intermediate stage of dual visual and verbal coding. These results suggest that developmental progressions in memory coding strategies are independent of intellectual disabilities status and consistent with MA.

  15. Reactor safety computer code development at INEL

    International Nuclear Information System (INIS)

    Johnsen, G.W.

    1985-01-01

    This report provides a brief overview of the computer code development programs being conducted at EG and G Idaho, Inc. on behalf of US Nuclear Regulatory Commission and the Department of Energy, Idaho Operations Office. Included are descriptions of the codes being developed, their development status as of the date of this report, and resident code development expertise

  16. Rate-adaptive BCH codes for distributed source coding

    DEFF Research Database (Denmark)

    Salmistraro, Matteo; Larsen, Knud J.; Forchhammer, Søren

    2013-01-01

    This paper considers Bose-Chaudhuri-Hocquenghem (BCH) codes for distributed source coding. A feedback channel is employed to adapt the rate of the code during the decoding process. The focus is on codes with short block lengths for independently coding a binary source X and decoding it given its...... strategies for improving the reliability of the decoded result are analyzed, and methods for estimating the performance are proposed. In the analysis, noiseless feedback and noiseless communication are assumed. Simulation results show that rate-adaptive BCH codes achieve better performance than low...... correlated side information Y. The proposed codes have been analyzed in a high-correlation scenario, where the marginal probability of each symbol, Xi in X, given Y is highly skewed (unbalanced). Rate-adaptive BCH codes are presented and applied to distributed source coding. Adaptive and fixed checking...

  17. Marital status is an independent prognostic factor for pancreatic neuroendocrine tumors patients: An analysis of the Surveillance, Epidemiology, and End Results (SEER) database.

    Science.gov (United States)

    Zhou, Huaqiang; Zhang, Yuanzhe; Song, Yiyan; Tan, Wulin; Qiu, Zeting; Li, Si; Chen, Qinchang; Gao, Shaowei

    2017-09-01

    Marital status's prognostic impact on pancreatic neuroendocrine tumors (PNET) has not been rigorously studied. We aimed to explore the relationship between marital status and outcomes of PNET. We retrospectively investigated 2060 PNET cases between 2004 and 2010 from Surveillance, Epidemiology, and End Results (SEER) database. Variables were compared by Chi 2 test, t-test as appropriate. Kaplan-Meier methods and COX proportional hazard models were used to ascertain independent prognostic factors. Married patients had better 5-year overall survival (OS) (53.37% vs. 42.27%, Pvs. 59.82%, P=0.001) comparing with unmarried patients. Multivariate analysis revealed marital status is an independent prognostic factor, with married patients showing better OS (HR=0.74; 95% CI: 0.65-0.84; Punmarried patients may be associated with a delayed diagnosis with advanced tumor stage, psychosocial and socioeconomic factors. Further studies are needed. Copyright © 2017. Published by Elsevier Masson SAS.

  18. Oral Health and nutritional status in nursing home residents-results of an explorative cross-sectional pilot study.

    Science.gov (United States)

    Ziebolz, Dirk; Werner, Christine; Schmalz, Gerhard; Nitschke, Ina; Haak, Rainer; Mausberg, Rainer F; Chenot, Jean-François

    2017-01-31

    This study was performed to assess oral and nutritional status of nursing home residents in a region of Lower Saxony, Germany. The aim was to show potential associations between oral status (dentate or edentulous), further anamnestic factors (dementia, age, smoking) and the risk for malnutrition in this population. In this observational cross-sectional pilot study of residents from four nursing homes Mini Nutritional Assessment (MNA), Body-Mass-Index (BMI), dental status (DMF-T) and periodontal situation (PSR ® /PSI) were recorded. Associations of recorded factors with oral health and nutritional status were examined in univariate and multivariate analysis. Eighty-seven residents participated in the study (mean age: 84.1 years; female: 72%, demented: 47%). Average BMI was 26.2 kg/m 2 ; according MNA 52% were at risk for malnutrition. 48% of the residents were edentulous, and the average DMF-T of dentulous was 25.0 (3.7) (D-T: 2.0 [3.1], M-T: 15.0 [8.3], F-T: 8.0 [7.4]); PSR ® /PSI 3 and 4 (need for periodontal treatment) showed 79% of residents. In univariate analysis dementia (OR 2.5 CI 95 1.1-5.6) but not being edentulous (OR 2.0 CI 95 0.8-5.8) were associated with being at risk for malnutrition. Dementia remained associated in multivariate analysis adjusting for age and sex, (OR 3.1 CI 95 1.2-8.2) and additionally being edentulous (OR 2.8 CI 95 1.1-7.3) became associated significantly. Furthermore, nursing home residents with dementia had more remaining teeth (OR 2.5 CI 95 1.1-5.9). Dementia was a stronger predictor for risk of malnutrition in nursing home residents than being edentulous. Further studies to elucidate the possible role of oral health as cofactor for malnutrition in dementia are needed.

  19. To report the obtained results in the simulation with the FCS-11 and Presto codes of the two first operation cycles of the Laguna Verde Unit 1 reactor

    International Nuclear Information System (INIS)

    Montes T, J.L.; Moran L, J.M.; Cortes C, C.C.

    1990-08-01

    The objective of this work is to establish a preliminary methodology to carry out analysis of recharges for the reactor of the Laguna Verde U-1, by means of the evaluation of the state of the reactor core in its first two operation cycles using the FCS2 and Presto-B codes. (Author)

  20. Factors associated with poor nutritional status among community dwelling Lebanese elderly subjects living in rural areas: results of the AMEL study.

    Science.gov (United States)

    Boulos, C; Salameh, P; Barberger-Gateau, P

    2014-05-01

    This study aimed to assess the nutritional status, measured by MNA, and its association with socio-demographic indicators and health related characteristics of a representative sample of community dwelling elderly subjects. Cross-sectional study. Community dwelling elderly individuals living in rural communities in Lebanon. 1200 elderly individuals aged 65 years or more. Socio-demographic indicators and health related characteristics were recorded during a standardized interview. Nutritional status was assessed through Mini Nutritional Assessment (MNA). The 5-item GDS score and the WHO-5-A score were used to assess mood, whereas Mini Mental Status (MMS) was applied to evaluate cognitive status. The prevalence of malnutrition and risk of malnutrition was 8.0% respective 29.1% of the study sample. Malnutrition was significantly more frequent in elderly subjects aged more than 85 years, in females, widowed and illiterate people. Moreover, participants who reported lower financial status were more often malnourished or at risk of malnutrition. Regarding health status, poor nutritional status was more common among those reporting more than three chronic diseases, taking more than three drugs daily, suffering from chronic pain and those who had worse oral health status. Also, depressive disorders and cognitive dysfunction were significantly related to malnutrition. After multivariate analysis following variables remained independently associated to malnutrition: living in the governorate of Nabatieh (ORa 2.30, 95% CI 1.35 -3.93), reporting higher income (ORa 0.77, 95% CI 0.61-0.97), higher number of comorbidities (ORa 1.22, 95% CI 1.12-1.32), chronic pain (ORa 1.72, 95% CI 1.24-2.39), and depressive disorders (ORa 1.66, 95% CI 1.47-1.88). On the other hand, better cognitive functioning was strongly associated with decreased nutritional risk (ORa 0.27, 95%CI 0.17-0.43). Our results highlighted the close relationship between health status and malnutrition. The

  1. Food branding influences ad libitum intake differently in children depending on weight status. Results of a pilot study.

    Science.gov (United States)

    Forman, Jamie; Halford, Jason C G; Summe, Heather; MacDougall, Megan; Keller, Kathleen L

    2009-08-01

    Environmental changes have facilitated the rapid increase in childhood obesity. One such change is increased presence of food marketing which promotes intake of high-fat, energy-dense foods. This study tested the hypotheses that overweight (OW) children are more sensitive to the intake-enhancing effects of food branding than non-OW children, and that the relationship between weight status and intake of branded foods is mediated by level of food brand awareness. Forty-three non-OW (n = 23) and OW (n = 20) children from diverse ethnic backgrounds participated in four dinnertime visits to test their intake of meals where food brands were present ("branded") or absent ("unbranded"). Food brand awareness was assessed by testing children's abilities to match food brand logos with correct foods and name specific brands from recall. Weight and height were measured on the first visit to determine BMI z-score and weight status. OW children consumed significantly more energy per meal than non-OW. Child age and brand awareness were positively associated. OW children consumed an additional 40 kcal in branded vs. unbranded meals whereas non-OW children consumed 45 kcal less in branded meals. Overweight children showed greater responsiveness to food branding, and they may be at risk in environments that are highly inundated with messages about food.

  2. Ten-year observations on health status of Children irradiated in utero as a result of the Chernobyl accident

    Energy Technology Data Exchange (ETDEWEB)

    Stepanova, E I; Kondrashova, V G; Galychanskaya, T Y; Vdovenko, V U [Radiation Medicine scientific Center of Ukrainian Medical Sciences Academy, (Ukraine)

    1997-12-31

    The health status dynamics of 1104 children exposed to radiation in utero was estimated after the Chernobyl nuclear power plant accident. The thyroid doses ranged from 0.00 to 3340.00 mg y, and total body doses from 1.00 to 376.00 mZv. The decrease in child adaptation capacity was observed with general somatic pathology and higher incidence of thyroid haemoglobin levels were rare in children irradiated in utero. The leucopenias with blood cells ultrastructure surficial architectonics alterations were more frequent. The metabolism of hemopoietic elements during early, post-accident years was peculiar with energy production activation through all paths of energy reception. During further years, all the intracellular enzymes activity decreased. energy depots exhaustion accompanied with ultrastructural changes, neutrophyles functional capacity and specific functions depression were revealed. The PC analysis of data obtained enabled to determine the presence of interconnection between some body systems disorders, radiation effects phenomenon and health status as a whole, and to reveal the further deterioration risk level. 5 figs., 3 tabs.

  3. Comparison of results of simulation of the CONTEMPT-LT/028 and lAP-3B codes for the analysis of the internal vacuum breaker valves of the CNLV

    International Nuclear Information System (INIS)

    Ovando C, R.; Cecenas F, M.; Moya C, M.M.

    2006-01-01

    In the primary container of a BWR type reactor, the humid and dry wells its are communicate by means of valves designed to equal the pressure in case of a significant pressure difference exists, produced by an operative event just as the performance of an emergency system. These valves are known as internal vacuum breakers and its analysis it is made by means of the use of a code with the capacity to analyze the primary contention of the reactor. Among the codes able to carry out this analysis type there is CONTEMPT-LT/028 and MAAP-3B; however, these codes possess characteristic different respect the modeling one of the different damage mitigation systems to the contention (dews, windy, emergency systems), of the transfer of heat among the different compartments of the primary container and in the details of the civil construction. In previous works carried out with the CONTEMPT-LT/028 code, they have been carried out different cases of simulation related with the operation of the internal breaker vacuum valves. These cases include small ruptures in the main steam lines and ruptures in the recirculation knots. It was selected the case more restrictive and it was generated an equivalent scenario file for the MAAP-3B code. In this work the performance of the internal breaker vacuum valves is analyzed by means of the CONTEMPT-LT/028 and MAAP-3B codes, when using the case more restrictive consistent in a small rupture in a main steam line. The analysis of the simulations indicates that both codes produce very similar results and the found differences are explained with base in the models used by each code to obtain the answer of the main thermohydraulic variables. In general terms, MAAP-3B possesses models that adapt in a form more convenient to the prospective phenomenology for this analysis, maintaining a conservative focus. (Author)

  4. Speech coding

    Energy Technology Data Exchange (ETDEWEB)

    Ravishankar, C., Hughes Network Systems, Germantown, MD

    1998-05-08

    Speech is the predominant means of communication between human beings and since the invention of the telephone by Alexander Graham Bell in 1876, speech services have remained to be the core service in almost all telecommunication systems. Original analog methods of telephony had the disadvantage of speech signal getting corrupted by noise, cross-talk and distortion Long haul transmissions which use repeaters to compensate for the loss in signal strength on transmission links also increase the associated noise and distortion. On the other hand digital transmission is relatively immune to noise, cross-talk and distortion primarily because of the capability to faithfully regenerate digital signal at each repeater purely based on a binary decision. Hence end-to-end performance of the digital link essentially becomes independent of the length and operating frequency bands of the link Hence from a transmission point of view digital transmission has been the preferred approach due to its higher immunity to noise. The need to carry digital speech became extremely important from a service provision point of view as well. Modem requirements have introduced the need for robust, flexible and secure services that can carry a multitude of signal types (such as voice, data and video) without a fundamental change in infrastructure. Such a requirement could not have been easily met without the advent of digital transmission systems, thereby requiring speech to be coded digitally. The term Speech Coding is often referred to techniques that represent or code speech signals either directly as a waveform or as a set of parameters by analyzing the speech signal. In either case, the codes are transmitted to the distant end where speech is reconstructed or synthesized using the received set of codes. A more generic term that is applicable to these techniques that is often interchangeably used with speech coding is the term voice coding. This term is more generic in the sense that the

  5. Codes maintained by the LAACG [Los Alamos Accelerator Code Group] at the NMFECC

    International Nuclear Information System (INIS)

    Wallace, R.; Barts, T.

    1990-01-01

    The Los Alamos Accelerator Code Group (LAACG) maintains two groups of design codes at the National Magnetic Fusion Energy Computing Center (NMFECC). These codes, principally electromagnetic field solvers, are used for the analysis and design of electromagnetic components for accelerators, e.g., magnets, rf structures, pickups, etc. In this paper, the status and future of the installed codes will be discussed with emphasis on an experimental version of one set of codes, POISSON/SUPERFISH

  6. Optimal codes as Tanner codes with cyclic component codes

    DEFF Research Database (Denmark)

    Høholdt, Tom; Pinero, Fernando; Zeng, Peng

    2014-01-01

    In this article we study a class of graph codes with cyclic code component codes as affine variety codes. Within this class of Tanner codes we find some optimal binary codes. We use a particular subgraph of the point-line incidence plane of A(2,q) as the Tanner graph, and we are able to describe ...

  7. Developments of HTGR thermofluid dynamic analysis codes and HTGR plant dynamic simulation code

    International Nuclear Information System (INIS)

    Tanaka, Mitsuhiro; Izaki, Makoto; Koike, Hiroyuki; Tokumitsu, Masashi

    1983-01-01

    In nuclear power plants as well as high temperature gas-cooled reactor plants, the design is mostly performed on the basis of the results after their characteristics have been grasped by carrying out the numerical simulation using the analysis code. Also in Kawasaki Heavy Industries Ltd., on the basis of the system engineering accumulated with gas-cooled reactors since several years ago, the preparation and systematization of analysis codes have been advanced, aiming at lining up the analysis codes for heat transferring flow and control characteristics, taking up HTGR plants as the main object. In this report, a part of the results is described. The example of the analysis applying the two-dimensional compressible flow analysis codes SOLA-VOF and SALE-2D, which were developed by Los Alamos National Laboratory in USA and modified for use in Kawasaki, to HTGR system is reported. Besides, Kawasaki has developed the control characteristics analyzing code DYSCO by which the change of system composition is easy and high versatility is available. The outline, fundamental equations, fundamental algorithms and examples of application of the SOLA-VOF and SALE-2D, the present status of system characteristic simulation codes and the outline of the DYSCO are described. (Kako, I.)

  8. Simvastatin Does Not Affect Vitamin D Status, but Low Vitamin D Levels Are Associated with Dyslipidemia: Results from a Randomised, Controlled Trial

    Directory of Open Access Journals (Sweden)

    Lars Rejnmark

    2010-01-01

    Full Text Available Objectives. Statin drugs act as inhibitors of the 3-hydroxy-3methylglutaryl coenzyme A (HMG-CoA reductase enzyme early in the mevalonate pathway, thereby reducing the endogenous cholesterol synthesis. In recent studies, it has been suggested from epidemiological data that statins also may improve vitamin D status, as measured by increased plasma 25-hydroxyvitamin D (25OHD levels. We now report the results from a randomised controlled trial on effects of simvastatin on plasma 25OHD levels. Design and Methods. We randomised 82 healthy postmenopausal women to one year of treatment with either simvastatin 40 mg/d or placebo and performed measurement at baseline and after 26 and 52 weeks of treatment. The study was completed by 77 subjects. Results. Compared with placebo, plasma levels of cholesterol and low-density lipoproteins decreased in response to treatment with simvastatin, but our study showed no effect of simvastatin on vitamin D status. However, plasma levels of triglycerides were inversely associated with tertiles of plasma 25OHD levels and changes in plasma triglycerides levels correlated inversely with seasonal changes in vitamin D status. Conclusion. Our data do not support a pharmacological effect of statins on vitamin D status, but do suggest that vitamin D may influence plasma lipid profile and thus be of importance to cardiovascular health.

  9. Nutritional status of indigenous children younger than five years of age in Mexico: results of a national probabilistic survey

    Directory of Open Access Journals (Sweden)

    Rivera Juan A

    2003-01-01

    Full Text Available OBJECTIVE: To compare the prevalence of undernutrition and anemia in indigenous and non-indigenous children 0.05. The prevalence of anemia in indigenous children was one third greater than in non-indigenous children at the national level (p0.05 in rural areas. These differences were reduced to about half when adjusting for SES but remained significantly higher in indigenous children (p<0.05. CONCLUSIONS: Indigenous children have higher probabilities of stunting and underweight than non-indigenous children. The differences are larger in urban areas and in higher socioeconomic geographic regions and are explained mostly by socioeconomic factors. The overall difference in the probability of anemia is small, is higher only in urban relative to rural areas, and is explained to a lesser degree by socioeconomic factors. Policy and programs should be designed and implemented to reduce the dramatic differences in nutritional status between indigenous and non-indigenous children in Mexico.

  10. The impact of bleeding disorders on the socioeconomic status of adult patients. Results of a comparative single centre cohort study.

    Science.gov (United States)

    Holstein, Katharina; von Mackensen, Sylvia; Bokemeyer, Carsten; Langer, Florian

    2017-07-10

    The impact of inherited bleeding disorders on the socioeconomic status (SES) of affected individuals is not clear. The SES of adult patients with congenital bleeding disorders (PWBD) from a centre in Germany (age 42.3 ± 15.0 years) was compared to that of a gender- and age-matched control group of patients with thrombophilia or a thrombotic event (PWT). Patients completed a questionnaire including aspects of SES, impact of the disease on their lives, and health-related quality of life (HRQoL). Forty-five patients were enrolled in each group; 71 % of PBWD had a severe form of the bleeding disorder (FVIII/IX activity impact of the disease on their lives than PWT (33.3 %, p impact of the disease on their lives compared to PWT, but not a significantly different SES in general.

  11. Sentinel node status prediction by four statistical models: results from a large bi-institutional series (n = 1132).

    Science.gov (United States)

    Mocellin, Simone; Thompson, John F; Pasquali, Sandro; Montesco, Maria C; Pilati, Pierluigi; Nitti, Donato; Saw, Robyn P; Scolyer, Richard A; Stretch, Jonathan R; Rossi, Carlo R

    2009-12-01

    To improve selection for sentinel node (SN) biopsy (SNB) in patients with cutaneous melanoma using statistical models predicting SN status. About 80% of patients currently undergoing SNB are node negative. In the absence of conclusive evidence of a SNBassociated survival benefit, these patients may be over-treated. Here, we tested the efficiency of 4 different models in predicting SN status. The clinicopathologic data (age, gender, tumor thickness, Clark level, regression, ulceration, histologic subtype, and mitotic index) of 1132 melanoma patients who had undergone SNB at institutions in Italy and Australia were analyzed. Logistic regression, classification tree, random forest, and support vector machine models were fitted to the data. The predictive models were built with the aim of maximizing the negative predictive value (NPV) and reducing the rate of SNB procedures though minimizing the error rate. After cross-validation logistic regression, classification tree, random forest, and support vector machine predictive models obtained clinically relevant NPV (93.6%, 94.0%, 97.1%, and 93.0%, respectively), SNB reduction (27.5%, 29.8%, 18.2%, and 30.1%, respectively), and error rates (1.8%, 1.8%, 0.5%, and 2.1%, respectively). Using commonly available clinicopathologic variables, predictive models can preoperatively identify a proportion of patients ( approximately 25%) who might be spared SNB, with an acceptable (1%-2%) error. If validated in large prospective series, these models might be implemented in the clinical setting for improved patient selection, which ultimately would lead to better quality of life for patients and optimization of resource allocation for the health care system.

  12. Current status of portal vein thrombosis in Japan: Results of a questionnaire survey by the Japan Society for Portal Hypertension.

    Science.gov (United States)

    Kojima, Seiichiro; Watanabe, Norihito; Koizumi, Jun; Kokubu, Shigehiro; Murashima, Naoya; Matsutani, Shoichi; Obara, Katsutoshi

    2018-03-01

    To investigate the current status of portal vein thrombosis (PVT) in Japan, the Clinical Research Committee of the Japan Society of Portal Hypertension undertook a questionnaire survey. A questionnaire survey of 539 cases of PVT over the previous 10 years was carried out at institutions affiliated with the Board of Trustees of the Japan Society of Portal Hypertension. The most frequent underlying etiology of PVT was liver cirrhosis in 75.3% of patients. Other causes included inflammatory diseases of the hepatobiliary system and the pancreas, malignant tumors, and hematologic diseases. The most frequent site was the main trunk of the portal vein (MPV) in 70.5%, and complete obstruction of the MPV was present in 11.5%. Among the medications for PVT, danaparoid was given to 45.8%, warfarin to 26.2%, heparin to 17.3%, and anti-thrombin III to 16.9%. Observation of the course was practiced in 22.4%. Factors contributing to therapeutic efficacy were implementation of various medications, thrombi localized to either the right or left portal vein only, non-complete obstruction of the MPV and Child-Pugh class A liver function. A survival analysis showed that the prognosis was favorable with PVT disappearance regardless of treatment. The questionnaire survey showed the current status of PVT in Japan. Any appropriate medication should be given to a patient with PVT when PVT is recognized. It is necessary to compile a large amount of information and reach a consensus on safe and highly effective management of PVT. © 2017 The Japan Society of Hepatology.

  13. Trends in Iron, Zinc, and Vitamin A Status Biomarkers Among Colombian Children: Results From 2 Nationally Representative Surveys.

    Science.gov (United States)

    Li, Wenchao; Herrán, Oscar F; Villamor, Eduardo

    2017-06-01

    Micronutrient deficiencies are still highly prevalent in countries undergoing the nutrition transition, but nationally representative data documenting their burden in children are exceedingly rare. To examine the distribution and recent trends in micronutrient status biomarkers of Colombian children. We compared the distributions of plasma ferritin, serum zinc, and vitamin A in Colombian children between 2005 and 2010 using 2 cross-sectional, nationally representative surveys overall and by categories of sociodemographic variables. Analysis for ferritin included boys and nonpregnant girls aged 1 to 17 years. Analyses for zinc and vitamin A included children aged 1 to 4 years. The mean 2010 to 2005 differences in ferritin, zinc, and vitamin A were 2.5 µg/L (95% confidence interval [CI]: 1.3 to 3.7), -34.9 µg/dL (95% CI: -39.6 to -30.2), and -11.5 µg/dL (95% CI: -12.3 to -10.7), respectively, after adjusting for sociodemographic characteristics. These differences varied significantly by region of residence. In 2010, region of residence was a significant correlate for all 3 micronutrients. Other important correlates included age and maternal education for ferritin and body mass index-for-age Z score, maternal education, wealth index, food insecurity, and urbanicity for vitamin A. Plasma ferritin was slightly higher in 2010 than in 2005, whereas serum zinc and vitamin A were substantially lower in 2010. In the absence of obvious causal explanations, it is uncertain whether this decline represents a worsening of micronutrient status in Colombian children or an artifact due to systematic laboratory or data management errors incurred in the surveys.

  14. Vocable Code

    DEFF Research Database (Denmark)

    Soon, Winnie; Cox, Geoff

    2018-01-01

    a computational and poetic composition for two screens: on one of these, texts and voices are repeated and disrupted by mathematical chaos, together exploring the performativity of code and language; on the other, is a mix of a computer programming syntax and human language. In this sense queer code can...... be understood as both an object and subject of study that intervenes in the world’s ‘becoming' and how material bodies are produced via human and nonhuman practices. Through mixing the natural and computer language, this article presents a script in six parts from a performative lecture for two persons...

  15. Assessment of RELAP5/MOD2 and RELAP5/MOD1-EUR codes on the basis of LOBI-MOD2 test results

    International Nuclear Information System (INIS)

    D'Auria, F.; Mazzini, M.; Oriolo, F.; Galassi, G.M.

    1989-10-01

    The present report deals with an overview of the application of RELAP5/MOD2 and RELAP5/MOD1-EUR codes to tests performed in the LOBI/MOD2 facility. The work has been carried out in the frame of a contract between Dipartimento di Costruzioni Meccaniche e Nucleari (DCMN) of Pisa University and CEC. The Universities of Roma, Pisa, Bologna and Palermo and the Polytechnic of Torino performed the post-test analysis of the LOBI experiment under the supervision of DCMN. In the report the main outcomes from the analysis of the LOBI experiments are given with the attempt to identify deficiencies in the modelling capabilities of the used codes

  16. Insurance billing and coding.

    Science.gov (United States)

    Napier, Rebecca H; Bruelheide, Lori S; Demann, Eric T K; Haug, Richard H

    2008-07-01

    The purpose of this article is to highlight the importance of understanding various numeric and alpha-numeric codes for accurately billing dental and medically related services to private pay or third-party insurance carriers. In the United States, common dental terminology (CDT) codes are most commonly used by dentists to submit claims, whereas current procedural terminology (CPT) and International Classification of Diseases, Ninth Revision, Clinical Modification (ICD.9.CM) codes are more commonly used by physicians to bill for their services. The CPT and ICD.9.CM coding systems complement each other in that CPT codes provide the procedure and service information and ICD.9.CM codes provide the reason or rationale for a particular procedure or service. These codes are more commonly used for "medical necessity" determinations, and general dentists and specialists who routinely perform care, including trauma-related care, biopsies, and dental treatment as a result of or in anticipation of a cancer-related treatment, are likely to use these codes. Claim submissions for care provided can be completed electronically or by means of paper forms.

  17. RFQ simulation code

    International Nuclear Information System (INIS)

    Lysenko, W.P.

    1984-04-01

    We have developed the RFQLIB simulation system to provide a means to systematically generate the new versions of radio-frequency quadrupole (RFQ) linac simulation codes that are required by the constantly changing needs of a research environment. This integrated system simplifies keeping track of the various versions of the simulation code and makes it practical to maintain complete and up-to-date documentation. In this scheme, there is a certain standard version of the simulation code that forms a library upon which new versions are built. To generate a new version of the simulation code, the routines to be modified or added are appended to a standard command file, which contains the commands to compile the new routines and link them to the routines in the library. The library itself is rarely changed. Whenever the library is modified, however, this modification is seen by all versions of the simulation code, which actually exist as different versions of the command file. All code is written according to the rules of structured programming. Modularity is enforced by not using COMMON statements, simplifying the relation of the data flow to a hierarchy diagram. Simulation results are similar to those of the PARMTEQ code, as expected, because of the similar physical model. Different capabilities, such as those for generating beams matched in detail to the structure, are available in the new code for help in testing new ideas in designing RFQ linacs

  18. Coding Class

    DEFF Research Database (Denmark)

    Ejsing-Duun, Stine; Hansbøl, Mikala

    Denne rapport rummer evaluering og dokumentation af Coding Class projektet1. Coding Class projektet blev igangsat i skoleåret 2016/2017 af IT-Branchen i samarbejde med en række medlemsvirksomheder, Københavns kommune, Vejle Kommune, Styrelsen for IT- og Læring (STIL) og den frivillige forening...... Coding Pirates2. Rapporten er forfattet af Docent i digitale læringsressourcer og forskningskoordinator for forsknings- og udviklingsmiljøet Digitalisering i Skolen (DiS), Mikala Hansbøl, fra Institut for Skole og Læring ved Professionshøjskolen Metropol; og Lektor i læringsteknologi, interaktionsdesign......, design tænkning og design-pædagogik, Stine Ejsing-Duun fra Forskningslab: It og Læringsdesign (ILD-LAB) ved Institut for kommunikation og psykologi, Aalborg Universitet i København. Vi har fulgt og gennemført evaluering og dokumentation af Coding Class projektet i perioden november 2016 til maj 2017...

  19. ANIMAL code

    International Nuclear Information System (INIS)

    Lindemuth, I.R.

    1979-01-01

    This report describes ANIMAL, a two-dimensional Eulerian magnetohydrodynamic computer code. ANIMAL's physical model also appears. Formulated are temporal and spatial finite-difference equations in a manner that facilitates implementation of the algorithm. Outlined are the functions of the algorithm's FORTRAN subroutines and variables

  20. Network Coding

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 15; Issue 7. Network Coding. K V Rashmi Nihar B Shah P Vijay Kumar. General Article Volume 15 Issue 7 July 2010 pp 604-621. Fulltext. Click here to view fulltext PDF. Permanent link: https://www.ias.ac.in/article/fulltext/reso/015/07/0604-0621 ...

  1. Expander Codes

    Indian Academy of Sciences (India)

    Home; Journals; Resonance – Journal of Science Education; Volume 10; Issue 1. Expander Codes - The Sipser–Spielman Construction. Priti Shankar. General Article Volume 10 ... Author Affiliations. Priti Shankar1. Department of Computer Science and Automation, Indian Institute of Science Bangalore 560 012, India.

  2. Influence of parental socio-economic status on diet quality of European adolescents: results from the HELENA study.

    Science.gov (United States)

    Béghin, L; Dauchet, L; De Vriendt, Tineke; Cuenca-García, M; Manios, Y; Toti, E; Plada, M; Widhalm, K; Repasy, J; Huybrechts, I; Kersting, M; Moreno, L A; Dallongeville, J

    2014-04-14

    Diet quality is influenced by socio-economic and geographical factors. The present study sought to assess whether adolescents' diet quality is affected by their parents' socio-economic status and whether the relationship between these factors is similar in northern and southern Europe. Data collected in the Healthy Lifestyle in Europe by Nutrition in Adolescence (HELENA) study in eight European countries were analysed. Dietary intake data were recorded via repeated 24 h recalls (using specifically developed HELENA Dietary Intake Assessment Tool software) and converted into an adolescent-specific Diet Quality Index (DQI-AM). Socio-economic status was estimated through parental educational level (Par-Educ-Lev) and parental occupation level (Par-Occ-Lev) as reported by the adolescents in a specific questionnaire. The DQI-AM data were then analysed as a function of Par-Educ-Lev and Par-Occ-Lev in northern European countries (Austria, Belgium, France, Germany and Sweden) and southern European countries (Greece, Italy and Spain). We studied a total of 1768 adolescents (age 14.7 (SD 1.3) years; percentage of girls: 52.8%; 1135 and 633 subjects from northern and southern Europe, respectively). On average, the DQI-AM score was higher in southern Europe than in northern Europe (69.1 (SD 0.1) v. 60.4 (SD 2.8), respectively; P < 0.001; Δ = 12.6%). The DQI was positively correlated with both paternal and maternal Par-Educ-Lev. However, this association was more pronounced in northern Europe than in southern Europe (P interaction = 0.004 for the mother and 0.06 for the father). The DQI was also positively correlated with Par-Occ-Lev (all P trends < 0.01), but this correlation was independent of the geographical area (P interaction = 0.51 for the mother and 0.50 for the father). In conclusion, Par-Educ-Lev and Par-Occ-Lev are associated with diet quality in adolescents in Europe. However, this association differs between northern Europe and southern Europe.

  3. Design of convolutional tornado code

    Science.gov (United States)

    Zhou, Hui; Yang, Yao; Gao, Hongmin; Tan, Lu

    2017-09-01

    As a linear block code, the traditional tornado (tTN) code is inefficient in burst-erasure environment and its multi-level structure may lead to high encoding/decoding complexity. This paper presents a convolutional tornado (cTN) code which is able to improve the burst-erasure protection capability by applying the convolution property to the tTN code, and reduce computational complexity by abrogating the multi-level structure. The simulation results show that cTN code can provide a better packet loss protection performance with lower computation complexity than tTN code.

  4. Low back pain status in elite and semi-elite Australian football codes: a cross-sectional survey of football (soccer, Australian rules, rugby league, rugby union and non-athletic controls

    Directory of Open Access Journals (Sweden)

    McHardy Andrew

    2009-04-01

    Full Text Available Abstract Background Our understanding of the effects of football code participation on low back pain (LBP is limited. It is unclear whether LBP is more prevalent in athletic populations or differs between levels of competition. Thus it was the aim of this study to document and compare the prevalence, intensity, quality and frequency of LBP between elite and semi-elite male Australian football code participants and a non-athletic group. Methods A cross-sectional survey of elite and semi-elite male Australian football code participants and a non-athletic group was performed. Participants completed a self-reported questionnaire incorporating the Quadruple Visual Analogue Scale (QVAS and McGill Pain Questionnaire (short form (MPQ-SF, along with additional questions adapted from an Australian epidemiological study. Respondents were 271 elite players (mean age 23.3, range 17–39, 360 semi-elite players (mean age 23.8, range 16–46 and 148 non-athletic controls (mean age 23.9, range 18–39. Results Groups were matched for age (p = 0.42 and experienced the same age of first onset LBP (p = 0.40. A significant linear increase in LBP from the non-athletic group, to the semi-elite and elite groups for the QVAS and the MPQ-SF was evident (p Conclusion Foolers in Australia have significantly more severe and frequent LBP than a non-athletic group and this escalates with level of competition.

  5. [Trends in the nutritional status of the Spanish population: results from the Catalan nutrition monitoring system (1992-2003)].

    Science.gov (United States)

    Serra Majem, Luis; Ribas Barba, Lourdes; Salvador Castell, Gemma; Roman Viñas, Blanca; Castell Abat, Conxa; Cabezas Peña, Carmen; Pastor Ferrer, Mari Cruz; Raidó Quintana, Blanca; Ngo de la Cruz, Joy; García Alvarez, Alicia; Serra Farró, Jaume; Salleras Sanmartí, Luis; Taradach Antoni, Plasencia

    2007-01-01

    The purpose of this study was to evaluate the changes in the nutricional habits and nutricional status of the Catalan population over 10 years interval of the two Catalan Nutricional Surveys conducted in 1992-93 and 2002-03. 2641 individuals in 1992-93 and 2060 individuals in 2002-03 aged 10 to 75 years participated in the surveys. Two 24 hour recall, a food frequency questionnaire, and a general questionnaire with information on physical activity, knowledge and opinions on nutrition and supplements use were administered. Weight (Kg), height (cm) and waist circumference (WC) (cm) were measured. A subsample of the population underwent a biochemical evaluation. Total cholesterol, HDL cholesterol, LDL cholesterol, tryglicerides and beta-carotene, alpha-tocopherol and retinol were measured. A decrease in the consumption of fruit, vegetables, potatoes, meat and fish and an increase in the consumption of dairy products and fast food (in young individuals) were reported. An increase in the mean value of Body Mass Index (BMI) was observed among males, and an increase in WC mean value was observed in males and females. BMI value decreased in females (except among the younger ones). The prevalence of obesity increased among males (from 9.9% to 16.6%), but not in females. Both total cholesterol and HDL cholesterol decreased. A decrease was observed in the percentage of population with sedentary habits during leisure time. There is a need for an effective nutrition policy promoting healthy nutrition in accordance with the ongoing dietary guidelines.

  6. Perceived Discrimination, Psychological Distress, and Current Smoking Status: Results From the Behavioral Risk Factor Surveillance System Reactions to Race Module, 2004–2008

    Science.gov (United States)

    Peppone, Luke J.; Alcaraz, Kassandra; McQueen, Amy; Guido, Joseph J.; Carroll, Jennifer K.; Shacham, Enbal; Morrow, Gary R.

    2012-01-01

    Objectives. We examined the association between perceived discrimination and smoking status and whether psychological distress mediated this relationship in a large, multiethnic sample. Methods. We used 2004 through 2008 data from the Behavioral Risk Factor Surveillance System Reactions to Race module to conduct multivariate logistic regression analyses and tests of mediation examining associations between perceived discrimination in health care and workplace settings, psychological distress, and current smoking status. Results. Regardless of race/ethnicity, perceived discrimination was associated with increased odds of current smoking. Psychological distress was also a significant mediator of the discrimination–smoking association. Conclusions. Our results indicate that individuals who report discriminatory treatment in multiple domains may be more likely to smoke, in part, because of the psychological distress associated with such treatment. PMID:22420821

  7. Relationship between socioeconomic status and type 2 diabetes: results from Korea National Health and Nutrition Examination Survey (KNHANES) 2010–2012

    OpenAIRE

    Hwang, Jongnam; Shon, Changwoo

    2014-01-01

    Objective To examine the relationship between socioeconomic status (SES) and type 2 diabetes using the Korea National Health and Nutrition Examination Survey (KNHANES) 2010–2012. Design A pooled sample cross-sectional study. Setting A nationally representative population survey data. Participants A total of 14 330 individuals who participated in the KNHANES 2010–2012 were included in our analysis. Primary outcome Prevalence of type 2 diabetes. Results The relationship between SES and type 2 d...

  8. The current status of interventional radiology in Canada: results of a survey by the Canadian Interventional Radiology Association

    Energy Technology Data Exchange (ETDEWEB)

    Millward, S.F.; Holley, M.L. [Univ. of Western Ontario, London Health Sciences Centre, Dept. of Radiology, London, Ontario (Canada)

    2001-04-01

    To evaluate the current status of interventional radiology in Canada. A questionnaire was sent to 28 Canadian interventional radiologists (defined as a physician who performs any type of interventional procedure, including biopsies, but excluding interventional neuroradiology) practising in both tertiary and community hospitals in the major centres in all provinces except Prince Edward Island. Twenty-two (79%) of 28 surveys were completed and returned, providing data about 86 interventional radiologists (IRs). IRs were performing almost all of the following procedures at their institutions: inferior vena cava filter placement, venous angioplasty, dialysis fistula angioplasty, diagnostic and therapeutic pulmonary and bronchial artery procedures, diagnostic and therapeutic procedures of the lower extremity and renal arteries, percutaneous abscess and biliary drainage procedures, percutaneous nephrostomy, and fibroid embolization. A second group of procedures, performed by both IRs and non-radiologists in most institutions, included: all types of central venous catheter placements, pleural drainage, and gastrostomy tube placement. Procedures not being performed by anyone in a number of institutions included: dialysis graft thrombolysis, varicocele embolization, transjugular intrahepatic portosystemic shunts, palliative stenting of the gastrointestinal tract, fallopian tube recannalization, and liver and prostate tumour treatments. The factors most often limiting the respondents' ability to provide a comprehensive interventional service were the interventional radiology inventory budget and the availability of interventional radiology rooms; 50% of respondents indicated the number of available nurses, technologists and IRs was also an important limiting factor. IRs in Canada still play a major role in many of the most commonly performed procedures. However, limited availability of resources and personnel in many institutions may be hampering the ability of IRs to

  9. The Minimum Distance of Graph Codes

    DEFF Research Database (Denmark)

    Høholdt, Tom; Justesen, Jørn

    2011-01-01

    We study codes constructed from graphs where the code symbols are associated with the edges and the symbols connected to a given vertex are restricted to be codewords in a component code. In particular we treat such codes from bipartite expander graphs coming from Euclidean planes and other...... geometries. We give results on the minimum distances of the codes....

  10. To report the obtained results in the operation multicycle study of the L V U-1 using design data with the FCSII (1D) and PRESTO (3D) codes of the FMS system

    International Nuclear Information System (INIS)

    Montes T, J.L.; Cortes C, C.C.

    1991-07-01

    This work is to carry out a multicycle study for the Laguna Verde U-1 reactor with the FCS-II (1 - 20 cycles) and PRESTO (1 - 6 cycles) codes and to compare the obtained results against those reported by General Electric. (Author)

  11. Non-Protein Coding RNAs

    CERN Document Server

    Walter, Nils G; Batey, Robert T

    2009-01-01

    This book assembles chapters from experts in the Biophysics of RNA to provide a broadly accessible snapshot of the current status of this rapidly expanding field. The 2006 Nobel Prize in Physiology or Medicine was awarded to the discoverers of RNA interference, highlighting just one example of a large number of non-protein coding RNAs. Because non-protein coding RNAs outnumber protein coding genes in mammals and other higher eukaryotes, it is now thought that the complexity of organisms is correlated with the fraction of their genome that encodes non-protein coding RNAs. Essential biological processes as diverse as cell differentiation, suppression of infecting viruses and parasitic transposons, higher-level organization of eukaryotic chromosomes, and gene expression itself are found to largely be directed by non-protein coding RNAs. The biophysical study of these RNAs employs X-ray crystallography, NMR, ensemble and single molecule fluorescence spectroscopy, optical tweezers, cryo-electron microscopy, and ot...

  12. Lattice polytopes in coding theory

    Directory of Open Access Journals (Sweden)

    Ivan Soprunov

    2015-05-01

    Full Text Available In this paper we discuss combinatorial questions about lattice polytopes motivated by recent results on minimum distance estimation for toric codes. We also include a new inductive bound for the minimum distance of generalized toric codes. As an application, we give new formulas for the minimum distance of generalized toric codes for special lattice point configurations.

  13. Geochemical computer codes. A review

    International Nuclear Information System (INIS)

    Andersson, K.

    1987-01-01

    In this report a review of available codes is performed and some code intercomparisons are also discussed. The number of codes treating natural waters (groundwater, lake water, sea water) is large. Most geochemical computer codes treat equilibrium conditions, although some codes with kinetic capability are available. A geochemical equilibrium model consists of a computer code, solving a set of equations by some numerical method and a data base, consisting of thermodynamic data required for the calculations. There are some codes which treat coupled geochemical and transport modeling. Some of these codes solve the equilibrium and transport equations simultaneously while other solve the equations separately from each other. The coupled codes require a large computer capacity and have thus as yet limited use. Three code intercomparisons have been found in literature. It may be concluded that there are many codes available for geochemical calculations but most of them require a user that us quite familiar with the code. The user also has to know the geochemical system in order to judge the reliability of the results. A high quality data base is necessary to obtain a reliable result. The best results may be expected for the major species of natural waters. For more complicated problems, including trace elements, precipitation/dissolution, adsorption, etc., the results seem to be less reliable. (With 44 refs.) (author)

  14. Study of nuclear computer code maintenance and management system

    International Nuclear Information System (INIS)

    Ryu, Chang Mo; Kim, Yeon Seung; Eom, Heung Seop; Lee, Jong Bok; Kim, Ho Joon; Choi, Young Gil; Kim, Ko Ryeo

    1989-01-01

    Software maintenance is one of the most important problems since late 1970's.We wish to develop a nuclear computer code system to maintenance and manage KAERI's nuclear software. As a part of this system, we have developed three code management programs for use on CYBER and PC systems. They are used in systematic management of computer code in KAERI. The first program is embodied on the CYBER system to rapidly provide information on nuclear codes to the users. The second and the third programs were embodied on the PC system for the code manager and for the management of data in korean language, respectively. In the requirement analysis, we defined each code, magnetic tape, manual and abstract information data. In the conceptual design, we designed retrieval, update, and output functions. In the implementation design, we described the technical considerations of database programs, utilities, and directions for the use of databases. As a result of this research, we compiled the status of nuclear computer codes which belonged KAERI until September, 1988. Thus, by using these three database programs, we could provide the nuclear computer code information to the users more rapidly. (Author)

  15. Panda code

    International Nuclear Information System (INIS)

    Altomare, S.; Minton, G.

    1975-02-01

    PANDA is a new two-group one-dimensional (slab/cylinder) neutron diffusion code designed to replace and extend the FAB series. PANDA allows for the nonlinear effects of xenon, enthalpy and Doppler. Fuel depletion is allowed. PANDA has a completely general search facility which will seek criticality, maximize reactivity, or minimize peaking. Any single parameter may be varied in a search. PANDA is written in FORTRAN IV, and as such is nearly machine independent. However, PANDA has been written with the present limitations of the Westinghouse CDC-6600 system in mind. Most computation loops are very short, and the code is less than half the useful 6600 memory size so that two jobs can reside in the core at once. (auth)

  16. CANAL code

    International Nuclear Information System (INIS)

    Gara, P.; Martin, E.

    1983-01-01

    The CANAL code presented here optimizes a realistic iron free extraction channel which has to provide a given transversal magnetic field law in the median plane: the current bars may be curved, have finite lengths and cooling ducts and move in a restricted transversal area; terminal connectors may be added, images of the bars in pole pieces may be included. A special option optimizes a real set of circular coils [fr

  17. Structural reliability methods: Code development status

    Science.gov (United States)

    Millwater, Harry R.; Thacker, Ben H.; Wu, Y.-T.; Cruse, T. A.

    1991-05-01

    The Probabilistic Structures Analysis Method (PSAM) program integrates state of the art probabilistic algorithms with structural analysis methods in order to quantify the behavior of Space Shuttle Main Engine structures subject to uncertain loadings, boundary conditions, material parameters, and geometric conditions. An advanced, efficient probabilistic structural analysis software program, NESSUS (Numerical Evaluation of Stochastic Structures Under Stress) was developed as a deliverable. NESSUS contains a number of integrated software components to perform probabilistic analysis of complex structures. A nonlinear finite element module NESSUS/FEM is used to model the structure and obtain structural sensitivities. Some of the capabilities of NESSUS/FEM are shown. A Fast Probability Integration module NESSUS/FPI estimates the probability given the structural sensitivities. A driver module, PFEM, couples the FEM and FPI. NESSUS, version 5.0, addresses component reliability, resistance, and risk.

  18. Perceived discrimination, psychological distress, and current smoking status: results from the Behavioral Risk Factor Surveillance System Reactions to Race module, 2004-2008.

    Science.gov (United States)

    Purnell, Jason Q; Peppone, Luke J; Alcaraz, Kassandra; McQueen, Amy; Guido, Joseph J; Carroll, Jennifer K; Shacham, Enbal; Morrow, Gary R

    2012-05-01

    We examined the association between perceived discrimination and smoking status and whether psychological distress mediated this relationship in a large, multiethnic sample. We used 2004 through 2008 data from the Behavioral Risk Factor Surveillance System Reactions to Race module to conduct multivariate logistic regression analyses and tests of mediation examining associations between perceived discrimination in health care and workplace settings, psychological distress, and current smoking status. Regardless of race/ethnicity, perceived discrimination was associated with increased odds of current smoking. Psychological distress was also a significant mediator of the discrimination-smoking association. Our results indicate that individuals who report discriminatory treatment in multiple domains may be more likely to smoke, in part, because of the psychological distress associated with such treatment.

  19. PEAR code review

    International Nuclear Information System (INIS)

    De Wit, R.; Jamieson, T.; Lord, M.; Lafortune, J.F.

    1997-07-01

    As a necessary component in the continuous improvement and refinement of methodologies employed in the nuclear industry, regulatory agencies need to periodically evaluate these processes to improve confidence in results and ensure appropriate levels of safety are being achieved. The independent and objective review of industry-standard computer codes forms an essential part of this program. To this end, this work undertakes an in-depth review of the computer code PEAR (Public Exposures from Accidental Releases), developed by Atomic Energy of Canada Limited (AECL) to assess accidental releases from CANDU reactors. PEAR is based largely on the models contained in the Canadian Standards Association (CSA) N288.2-M91. This report presents the results of a detailed technical review of the PEAR code to identify any variations from the CSA standard and other supporting documentation, verify the source code, assess the quality of numerical models and results, and identify general strengths and weaknesses of the code. The version of the code employed in this review is the one which AECL intends to use for CANDU 9 safety analyses. (author)

  20. Quasi-cyclic unit memory convolutional codes

    DEFF Research Database (Denmark)

    Justesen, Jørn; Paaske, Erik; Ballan, Mark

    1990-01-01

    Unit memory convolutional codes with generator matrices, which are composed of circulant submatrices, are introduced. This structure facilitates the analysis of efficient search for good codes. Equivalences among such codes and some of the basic structural properties are discussed. In particular......, catastrophic encoders and minimal encoders are characterized and dual codes treated. Further, various distance measures are discussed, and a number of good codes, some of which result from efficient computer search and some of which result from known block codes, are presented...

  1. Comparison and validation of the results of the AZNHEX v.1.0 code with the MCNP code simulating the core of a fast reactor cooled with sodium; Comparacion y validacion de los resultados del codigo AZNHEX v.1.0 con el codigo MCNP simulando el nucleo de un reactor rapido refrigerado con sodio

    Energy Technology Data Exchange (ETDEWEB)

    Galicia A, J.; Francois L, J. L.; Bastida O, G. E. [UNAM, Facultad de Ingenieria, Departamento de Sistemas Energeticos, Ciudad Universitaria, 04510 Ciudad de Mexico (Mexico); Esquivel E, J., E-mail: blink19871@hotmail.com [ININ, Carretera Mexico-Toluca s/n, 52750 Ocoyoacac, Estado de Mexico (Mexico)

    2016-09-15

    The development of the AZTLAN platform for the analysis and design of nuclear reactors is led by Instituto Nacional de Investigaciones Nucleares (ININ) and divided into four working groups, which have well-defined activities to achieve significant progress in this project individually and jointly. Within these working groups is the users group, whose main task is to use the codes that make up the AZTLAN platform to provide feedback to the developers, and in this way to make the final versions of the codes are efficient and at the same time reliable and easy to understand. In this paper we present the results provided by the AZNHEX v.1.0 code when simulating the core of a fast reactor cooled with sodium at steady state. The validation of these results is a fundamental part of the platform development and responsibility of the users group, so in this research the results obtained with AZNHEX are compared and analyzed with those provided by the Monte Carlo code MCNP-5, software worldwide used and recognized. A description of the methodology used with MCNP-5 is also presented for the calculation of the interest variables and the difference that is obtained with respect to the calculated with AZNHEX. (Author)

  2. Determination of the dead layer and full-energy peak efficiency of an HPGe detector using the MCNP code and experimental results

    Directory of Open Access Journals (Sweden)

    M Moeinifar

    2017-02-01

    Full Text Available One important factor in using an High Purity Germanium (HPGe detector is its efficiency that highly depends on the geometry and absorption factors, so that when the configuration of source-detector geometry is changed, the detector efficiency must be re-measured. The best way of determining the efficiency of a detector is measuring the efficiency of standard sources. But considering the fact that standard sources are hardly available and it is time consuming to find them, determinig the efficiency by simulation which gives enough efficiency in less time, is important. In this study, the dead layer thickness and the full-energy peak efficiency of an HPGe detector was obtained by Monte Carlo simulation, using MCNPX code. For this, we first measured gamma–ray spectra for different sources placed at various distances from the detector and stored the measured spectra obtained. Then the obtained spectra were simulated under similar conditions in vitro.At first, the whole volume of germanium was regarded as active, and the obtaind spectra from calculation were compared with the corresponding experimental spectra. Comparison of the calculated spectra with the measured spectra showed considerable differences. By making small variations in the dead layer thickness of the detector (about a few hundredths of a millimeter in the simulation program, we tried to remove these differences and in this way a dead layer of 0.57 mm was obtained for the detector. By incorporating this value for the dead layer in the simulating program, the full-energy peak efficiency of the detector was then obtained both by experiment and by simulation, for various sources at various distances from the detector, and both methods showed good agreements. Then, using MCNP code and considering the exact measurement system, one can conclude that the efficiency of an HPGe detector for various source-detector geometries can be calculated with rather good accuracy by simulation method

  3. The fast code

    Energy Technology Data Exchange (ETDEWEB)

    Freeman, L.N.; Wilson, R.E. [Oregon State Univ., Dept. of Mechanical Engineering, Corvallis, OR (United States)

    1996-09-01

    The FAST Code which is capable of determining structural loads on a flexible, teetering, horizontal axis wind turbine is described and comparisons of calculated loads with test data are given at two wind speeds for the ESI-80. The FAST Code models a two-bladed HAWT with degrees of freedom for blade bending, teeter, drive train flexibility, yaw, and windwise and crosswind tower motion. The code allows blade dimensions, stiffnesses, and weights to differ and models tower shadow, wind shear, and turbulence. Additionally, dynamic stall is included as are delta-3 and an underslung rotor. Load comparisons are made with ESI-80 test data in the form of power spectral density, rainflow counting, occurrence histograms, and azimuth averaged bin plots. It is concluded that agreement between the FAST Code and test results is good. (au)

  4. ASSESSING THE CONSERVATION STATUS OF EUROPEAN UNION HABITATS – RESULTS OF THE COMMUNITY REPORT WITH A CASE STUDY OF THE GERMAN NATIONAL REPORT

    Directory of Open Access Journals (Sweden)

    S. BALZER

    2010-01-01

    Full Text Available The EU Habitats Directive requires all member states to report every 6 years on the implementation of the Directive. The report covering the period 2000 – 2006 included for the first time an assessment of the conservation status of the habitats and species listed on annexes I, II, IV & V of the Habitats Directive following an agreed format. Based on national reports submitted from member States the European Topic Centre on Biological Diversity has prepared assessments for each biogeographical region at EU-level. The majority of the habitats of Annex I are not at favourable status although there is much variation both between countries and regions and between habitats. The results will be discussed at European level and at member state level with a case study of the German national report. At the same time a number of methodical problems became apparent both in Germany and at EU-level. Work is already under way to improve the next report for the period 2007 – 2012. The dimension of management needs, threats and pressures and the time scale for improvements of the conservation status are discussed. Habitats linked to agriculture appear to be particularly unfavourable.

  5. ASSESSING THE CONSERVATION STATUS OF EUROPEAN UNION HABITATS – RESULTS OF THE COMMUNITY REPORT WITH A CASE STUDY OF THE GERMAN NATIONAL REPORT

    Directory of Open Access Journals (Sweden)

    Z. SIPKOVA

    2010-04-01

    Full Text Available The EU Habitats Directive requires all member states to report every 6 years on the implementation of the Directive. The report covering the period 2000 – 2006 included for the first time an assessment of the conservation status of the habitats and species listed on annexes I, II, IV & V of the Habitats Directive following an agreed format. Based on national reports submitted from member States the European Topic Centre on Biological Diversity has prepared assessments for each biogeographical region at EU-level. The majority of the habitats of Annex I are not at favourable status although there is much variation both between countries and regions and between habitats. The results will be discussed at European level and at member state level with a case study of the German national report. At the same time a number of methodical problems became apparent both in Germany and at EU-level. Work is already under way to improve the next report for the period 2007 – 2012. The dimension of management needs, threats and pressures and the time scale for improvements of the conservation status are discussed. Habitats linked to agriculture appear to be particularly unfavourable.

  6. CVSscan : Visualization of Code Evolution

    NARCIS (Netherlands)

    Voinea, Lucian; Telea, Alex; Wijk, Jarke J. van

    2005-01-01

    During the life cycle of a software system, the source code is changed many times. We study how developers can be enabled to get insight in these changes, in order to understand the status, history and structure better, as well as for instance the roles played by various contributors. We present

  7. New quantum codes constructed from quaternary BCH codes

    Science.gov (United States)

    Xu, Gen; Li, Ruihu; Guo, Luobin; Ma, Yuena

    2016-10-01

    In this paper, we firstly study construction of new quantum error-correcting codes (QECCs) from three classes of quaternary imprimitive BCH codes. As a result, the improved maximal designed distance of these narrow-sense imprimitive Hermitian dual-containing quaternary BCH codes are determined to be much larger than the result given according to Aly et al. (IEEE Trans Inf Theory 53:1183-1188, 2007) for each different code length. Thus, families of new QECCs are newly obtained, and the constructed QECCs have larger distance than those in the previous literature. Secondly, we apply a combinatorial construction to the imprimitive BCH codes with their corresponding primitive counterpart and construct many new linear quantum codes with good parameters, some of which have parameters exceeding the finite Gilbert-Varshamov bound for linear quantum codes.

  8. Certificate of competence for the use of industrial radiography equipment - CAMARI. 2011 annual status - Organisation, results and perspectives

    International Nuclear Information System (INIS)

    Le Dirac'h, B.

    2012-01-01

    Since 2008, IRSN has been organizing the tests of the review of CAMARI (licence for using radiological installations for industry in France) in technical support of the ministry's work. This report, by reminding the modalities of the examination, supplies a synthesis of the results obtained by the candidates in 2011. The exam's organization set up by IRSN, provides a summary of results obtained by candidates in 2011. It also provides the balance sheet over the period 2008-2011 and suggests axes of improvement. (author)

  9. Evaluation of the efficacy of laser peripheral iridoplasty in reversing the darkroom provocative test result in Chinese patients with primary angle closure status post laser iridotomy

    Directory of Open Access Journals (Sweden)

    Ping Huang

    2015-06-01

    Full Text Available AIM: To investigate the efficacy and safety of krypton laser peripheral iridoplasty (LPIP for Chinese patients with primary angle closure (PAC or primary angle-closure glaucoma (PACG status post laser iridotomy in reversing the positive results of the dark room provocative test (DRPT.METHODS:This study was prospective, noncomparative, interventional case series. Thirty-three patients (thirty-eight eyes with PAC or PACG status post patent laser iridotomy and maintained normal intraocular pressure (IOP but with positive DRPT results were enrolled. All the subjects were treated with krypton LPIP. DRPT was repeated after krypton LPIP. Results of DRPT were recorded. The visual acuity, IOP and gonioscopy were analyzed before and after krypton LPIP. A minimum time limit for follow-up was 6mo.RESULTS:Thirty-three patients (thirty-eight eyes were followed for 17.7±8.37mo (range 7-41mo after LPIP. Positive results of DRPT decreased from 38 eyes to 9 eyes (23.7% after LPIP. Peripheral anterior synechiae of angle in 34 of 38 eyes (89.5% remained unchanged at dynamic gonioscopy throughout the follow-up period after LPIP.CONCLUSION:LPIP decreased positive rates of the DRPT significantly. The mechanism may be that LPIP minimized contact between the peripheral iris and trabecular meshwork, which is a key factor for developing peripheral anterior synechiae.

  10. Evaluation of the efficacy of laser peripheral iridoplasty in reversing the darkroom provocative test result in Chinese patients with primary angle closure status post laser iridotomy

    Institute of Scientific and Technical Information of China (English)

    Ping; Huang; Ling-Ling; Wu

    2015-01-01

    AIM: To investigate the efficacy and safety of krypton laser peripheral iridoplasty(LPIP) for Chinese patients with primary angle closure(PAC) or primary angle-closure glaucoma(PACG) status post laser iridotomy in reversing the positive results of the dark room provocative test(DRPT).METHODS: This study was prospective, noncomparative,interventional case series. Thirty-three patients(thirty-eight eyes) with PAC or PACG status post patent laser iridotomy and maintained normal intraocular pressure(IOP) but with positive DRPT results were enrolled. All the subjects were treated with krypton LPIP. DRPT was repeated after krypton LPIP. Results of DRPT were recorded. The visual acuity, IOP and gonioscopy were analyzed before and after krypton LPIP. A minimum time limit for follow-up was 6mo.RESULTS: Thirty-three patients(thirty-eight eyes)were followed for 17.7 ±8.37mo(range 7-41mo) after LPIP. Positive results of DRPT decreased from 38 eyes to9 eyes(23.7%) after LPIP. Peripheral anterior synechiae of angle in 34 of 38 eyes(89.5%) remained unchanged at dynamic gonioscopy throughout the follow-up period after LPIP.CONCLUSION: LPIP decreased positive rates of the DRPT significantly. The mechanism may be that LPIP minimized contact between the peripheral iris and trabecular meshwork, which is a key factor for developing peripheral anterior synechiae.

  11. Towards advanced code simulators

    International Nuclear Information System (INIS)

    Scriven, A.H.

    1990-01-01

    The Central Electricity Generating Board (CEGB) uses advanced thermohydraulic codes extensively to support PWR safety analyses. A system has been developed to allow fully interactive execution of any code with graphical simulation of the operator desk and mimic display. The system operates in a virtual machine environment, with the thermohydraulic code executing in one virtual machine, communicating via interrupts with any number of other virtual machines each running other programs and graphics drivers. The driver code itself does not have to be modified from its normal batch form. Shortly following the release of RELAP5 MOD1 in IBM compatible form in 1983, this code was used as the driver for this system. When RELAP5 MOD2 became available, it was adopted with no changes needed in the basic system. Overall the system has been used for some 5 years for the analysis of LOBI tests, full scale plant studies and for simple what-if studies. For gaining rapid understanding of system dependencies it has proved invaluable. The graphical mimic system, being independent of the driver code, has also been used with other codes to study core rewetting, to replay results obtained from batch jobs on a CRAY2 computer system and to display suitably processed experimental results from the LOBI facility to aid interpretation. For the above work real-time execution was not necessary. Current work now centers on implementing the RELAP 5 code on a true parallel architecture machine. Marconi Simulation have been contracted to investigate the feasibility of using upwards of 100 processors, each capable of a peak of 30 MIPS to run a highly detailed RELAP5 model in real time, complete with specially written 3D core neutronics and balance of plant models. This paper describes the experience of using RELAP5 as an analyzer/simulator, and outlines the proposed methods and problems associated with parallel execution of RELAP5

  12. From concatenated codes to graph codes

    DEFF Research Database (Denmark)

    Justesen, Jørn; Høholdt, Tom

    2004-01-01

    We consider codes based on simple bipartite expander graphs. These codes may be seen as the first step leading from product type concatenated codes to more complex graph codes. We emphasize constructions of specific codes of realistic lengths, and study the details of decoding by message passing...

  13. Evaluation of an electrocardiogram on QR code.

    Science.gov (United States)

    Nakayama, Masaharu; Shimokawa, Hiroaki

    2013-01-01

    An electrocardiogram (ECG) is an indispensable tool to diagnose cardiac diseases, such as ischemic heart disease, myocarditis, arrhythmia, and cardiomyopathy. Since ECG patterns vary depend on patient status, it is also used to monitor patients during treatment and comparison with ECGs with previous results is important for accurate diagnosis. However, the comparison requires connection to ECG data server in a hospital and the availability of data connection among hospitals is limited. To improve the portability and availability of ECG data regardless of server connection, we here introduce conversion of ECG data into 2D barcodes as text data and decode of the QR code for drawing ECG with Google Chart API. Fourteen cardiologists and six general physicians evaluated the system using iPhone and iPad. Overall, they were satisfied with the system in usability and accuracy of decoded ECG compared to the original ECG. This new coding system may be useful in utilizing ECG data irrespective of server connections.

  14. Status of radioactivity monitoring in French Polynesia in 2011. Synthesis of the results from the IRSN's monitoring network

    International Nuclear Information System (INIS)

    Bouisset, P.; Bernagout, S.; Leclerc, G.; Rua, J.; Delabbaye, P.; Cagnat, X.

    2012-11-01

    Radiological monitoring of the French environment is one of IRSN's permanent tasks as part of public policy on nuclear safety and radiological protection. It is helping to guarantee the best possible protection of the population. Exercised in Polynesia since 1962, this monitoring, which takes place on seven islands (Tahiti, Maupiti, Hao, Rangiroa, HivaOa, Mangareva and Tubuai) representing the five archipelagos, and consists of taking regular samples of various kinds from the different environmental compartments (air, water, soil, food...) with which the population may be in contact. Regarding food, the samples analyzed are representative of the diet of Polynesians living in the five archipelagos of that territory, and from the marine environment of the open sea, from the lagoon environment and from the terrestrial environment. Almost all samples are measured at the Laboratory for the Study and Monitoring of the Environment IRSN, based in Vairao on the island of Tahiti. The year 2011 was marked by the Fukushima nuclear accident, which occurred on March 11. In this context, IRSN conducted a strengthened monitoring of French Polynesia, thus confirming the absence of radiological impact in Caledonia and Polynesia. The results of analyzes have been published in the previous annual report (report DEI/SESURE 2011-40), this report does not include all data and results for the year 2011, but establishes a synthesis for this year. During the year 2011, results fall under the continuity of a regular reduction of the levels of radioactivity since the stop, in 1974, of the French atmospheric tests. This residual radioactivity relates to primarily the 137 Cs. In term of additional dose, this artificial and residual radioactivity is lower than 5 μSv.y -1 (5 micro-sieverts per year). This value corresponds to less than 0,5 % of exposure due to natural radioactivity in Polynesia (approximately 1 000 μSv.y -1 ). (authors)

  15. Reproductive Decision-Making in MMR Mutation Carriers After Results Disclosure: Impact of Psychological Status in Childbearing Options.

    Science.gov (United States)

    Duffour, Jacqueline; Combes, Audrey; Crapez, Evelyne; Boissière-Michot, Florence; Bibeau, Frédéric; Senesse, Pierre; Ychou, Marc; Courraud, Julie; de Forges, Hélène; Roca, Lise

    2016-06-01

    Reproductive techniques such as prenatal diagnosis (PND) or preimplantation genetic diagnosis (PGD), although debated, are legally forbidden in France in case of Lynch syndrome. The preference of mutation carriers about their reproductive options is not systematically considered in France. We aimed to prospectively assess the reproductive preferences of mismatch repair mutation carriers consulting in our institution (2003-2010, n = 100). We also considered the short- and long-term post-disclosure psychological impact using the Impact of Events Scale-Revised questionnaire to measure the prevalence of posttraumatic stress disorder (PTSD) in those patients. Complete data were obtained for 34 respondents (17 males, 17 females, median age of 33.5 years [22-59]). Seventeen respondents (57 %) preferred spontaneous natural conception versus 28 % and 35 % choosing PND and PGD, respectively. At results disclosure, respondents mainly explained their distress by fear of premature death (43 %) and transmitting mutated genes (42 %). One year later, this last fear remained predominant in 55 % of subjects. None of the main socio-demographical, psychological or medical variables (including fear of transmitting mutations) was significantly associated with the reproductive preferences. Results disclosure had a real and time-decreasing psychological impact on mutation carriers. Reproductive techniques, expected to decrease the hereditary risk, were not significantly preferred to natural conception.

  16. Results and status of the Edelweiss Wimp search experiment; Experience Edelweiss de recherche directe de Wimps: resultats et perspectives

    Energy Technology Data Exchange (ETDEWEB)

    Benoit, A.; Berge, L.; Blumer, J.; Broniatowski, A.; Censier, B.; Chabert, L.; Chambon, B.; Chapellier, M.; Chardin, G.; Charvin, P.; Jesus, M. de; Drain, D.; Di Stefano, P.; Dumoulin, L.; Eitel, K.; Fesquet, M.; Firucci, S.; Gascon, J.; Gerbier, G.; Gerlic, E.; Goldbach, C.; Goyot, M.; Gros, M.; Habermahl, F.; Horn, M.; Hadjout, J.P.; Herve, S.; Juillard, A.; Kikuchi, C.; Lesquen, A. de; Luca, M.; Mallet, J.; Marnieros, S.; Martineau, O.; Mosca, L.; Navick, X.F.; Nollez, G.; Pari, P.; Riccio, C.; Sanglard, V.; Stern, M.; Vagneron, L.; Villard, V

    2005-07-01

    In the Edelweiss experiment, nuclear recoils induced by elastic collisions with WIMPs (weakly interacting massive particle) from the galactic halo are identified in low-temperature Ge detectors where the ratio of the heat and ionization signals provide an event-by-event discrimination of nuclear recoils from the dominant background coming from {gamma}-rays interactions. The Edelweiss experiment is located in the Modane underground facility in order to cut the muon flux drastically. We present here the results obtained during the first part of the experiment named Edelweiss-I that ended in the beginning of 2004. Since october 2002, 3 optimized 320 grams detectors have been simultaneously operated at a regulated temperature of 0.017 K and about 50 kg*day were added to the previous published data. These data are still under analysis but preliminary results concerning the upper limit at 90% CL (confidence level) confirm the limit already published in 2002. The first run of Edelweiss-II is due to begin during summer 2005, we are expecting to gain 2 orders of magnitude in terms of detector sensitivity and reach 0.002 events/day*kg. (A.C.)

  17. Assessment of the radiological status of the French environment in 2008: synthesis of the results of the IRSN's watch networks

    International Nuclear Information System (INIS)

    2009-01-01

    This report presents the data obtained in 2008 within the frame of the follow-up by the IRSN of the levels of radioactivity on the French national territory. After having recalled the objectives of this radiological watch of the environment and its organization, the report describes the methodology adopted for the choice of the watch stations, the choice of the environmental matrices, the analysis plans, the sample preparation and packing. It presents the various radionuclides which are naturally or artificially present in the French environment. Then, it presents the results obtained by the different station networks by watching the atmosphere, rivers and soils, or coasts. The report recalls and comments the different radiological events which occurred in 2008, i.e. the detection of different radionuclides in different environments: nuclear plants, nuclear research centres, nuclear sites, nuclear industries, nuclear waste storage sites, nuclear marine bases, rivers

  18. FY15 Status of Immersion Phased Array Ultrasonic Probe Development and Performance Demonstration Results for Under Sodium Viewing

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, Aaron A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Larche, Michael R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mathews, Royce [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neill, Kevin J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Baldwin, David L. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Prowant, Matthew S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Edwards, Matthew K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chamberlin, Clyde E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2015-09-01

    This Technical Letter Report (TLR) describes work conducted at the Pacific Northwest National Laboratory (PNNL) during FY 2015 on the under-sodium viewing (USV) PNNL project 58745, Work Package AT-15PN230102. This TLR satisfies PNNL’s M3AT-15PN2301027 milestone, and is focused on summarizing the design, development, and evaluation of a two-dimensional matrix phased-array probe referred to as serial number 3 (SN3). In addition, this TLR also provides the results from a performance demonstration of in-sodium target detection trials at 260°C using a one-dimensional 22-element linear array developed in FY14 and referred to as serial number 2 (SN2).

  19. [Biological markers for the status of vitamins B12 and D: the importance of some analytical aspects in relation to clinical interpretation of results].

    Science.gov (United States)

    Boulat, O; Rey, F; Mooser, V

    2012-10-31

    Biological markers for the status of vitamins B12 and D: the importance of some analytical aspects in relation to clinical interpretation of results When vitamin B12 deficiency is expressed clinically, the diagnostic performance of total cobalamin is identical to that of holotranscobalamin II. In subclinical B12 deficiency, the two aforementioned markers perform less well. Additional analysis of a second, functional marker (methylmalonate or homocysteine) is recommended. Different analytical approaches for 25-hydroxyvitamin D quantification, the marker of vitamin D deficiency, are not yet standardized. Measurement biases of up to +/- 20% compared with the original method used to establish threshold values are still observed.

  20. Annual report of nuclear code evaluation committee for fiscal 2000 year

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    2002-03-01

    In this report, research results discussed in fiscal 2000 year at Nuclear Code Evaluation Committee of Nuclear Code Research Committee were summarized. In 2000, papers mainly on the three topics of (1) present status of burnup credit evaluation methods, (2) issues concerning convergence of criticality calculation and (3) estimation methods for errors associated with criticality calculation based on nuclear data covariance file, are presented and discussed. These results are sorted to grasp the present status of related technology and described in this report. (author)

  1. Separate Turbo Code and Single Turbo Code Adaptive OFDM Transmissions

    Directory of Open Access Journals (Sweden)

    Lei Ye

    2009-01-01

    Full Text Available This paper discusses the application of adaptive modulation and adaptive rate turbo coding to orthogonal frequency-division multiplexing (OFDM, to increase throughput on the time and frequency selective channel. The adaptive turbo code scheme is based on a subband adaptive method, and compares two adaptive systems: a conventional approach where a separate turbo code is used for each subband, and a single turbo code adaptive system which uses a single turbo code over all subbands. Five modulation schemes (BPSK, QPSK, 8AMPM, 16QAM, and 64QAM are employed and turbo code rates considered are 1/2 and 1/3. The performances of both systems with high (10−2 and low (10−4 BER targets are compared. Simulation results for throughput and BER show that the single turbo code adaptive system provides a significant improvement.

  2. Separate Turbo Code and Single Turbo Code Adaptive OFDM Transmissions

    Directory of Open Access Journals (Sweden)

    Burr Alister

    2009-01-01

    Full Text Available Abstract This paper discusses the application of adaptive modulation and adaptive rate turbo coding to orthogonal frequency-division multiplexing (OFDM, to increase throughput on the time and frequency selective channel. The adaptive turbo code scheme is based on a subband adaptive method, and compares two adaptive systems: a conventional approach where a separate turbo code is used for each subband, and a single turbo code adaptive system which uses a single turbo code over all subbands. Five modulation schemes (BPSK, QPSK, 8AMPM, 16QAM, and 64QAM are employed and turbo code rates considered are and . The performances of both systems with high ( and low ( BER targets are compared. Simulation results for throughput and BER show that the single turbo code adaptive system provides a significant improvement.

  3. OC3—Benchmark Exercise of Aero-elastic Offshore Wind Turbine Codes

    Science.gov (United States)

    Passon, P.; Kühn, M.; Butterfield, S.; Jonkman, J.; Camp, T.; Larsen, T. J.

    2007-07-01

    This paper introduces the work content and status of the first international investigation and verification of aero-elastic codes for offshore wind turbines as performed by the "Offshore Code Comparison Collaboration"(OC3) within the "IEA Wind Annex XXIII - Subtask 2". An overview is given on the state-of-the-art of the concerned offshore wind turbine simulation codes. Exemplary results of benchmark simulations from the first phase of the project are presented and discussed while subsequent phases are introduced. Furthermore, the paper discusses areas where differences between the codes have been identified and the sources of those differences, such as the differing theories implemented into the individual codes. Finally, further research and code development needs are presented based on the latest findings from the current state of the project.

  4. Code of practice in industrial radiography

    International Nuclear Information System (INIS)

    Karma, S. E. M.

    2010-12-01

    The aim of this research is to developing a draft for a new radiation protection code of practice in industrial radiography without ignoring that one issued in 1998 and meet the current international recommendation. Another aim of this study was to assess the current situation of radiation protection in some of the industrial radiography department in Sudan. To achieve the aims of this study, a draft of a code of practice has been developed which is based on international and local relevant recommendations. The developed code includes the following main issues: regulatory responsibilities, radiation protection program and design of radiation installation. The practical part of this study includes scientific visits to two of industrial radiography departments in Sudan so as to assess the degree of compliance of that department with what state in the developed code. The result of each scientific visits revealed that most of the department do not have an effective radiation protection program and that could lead to exposure workers and public to unnecessary dose. Some recommendations were stated that, if implemented could improve the status of radiation protection in industrial radiography department. (Author)

  5. FY16 Status of Immersion Phased Array Ultrasonic Probe Development and Performance Demonstration Results for Under Sodium Viewing

    International Nuclear Information System (INIS)

    Diaz, Aaron A.; Chamberlin, Clyde E.; Edwards, Matthew K.; Hagge, Tobias J.; Hughes, Michael S.; Larche, Michael R.; Mathews, Royce A.; Neill, Kevin J.; Prowant, Matthew S.

    2016-01-01

    This section of the Joint summary technical letter report (TLR) describes work conducted at the Pacific Northwest National Laboratory (PNNL) during FY 2016 (FY16) on the under-sodium viewing (USV) PNNL project 58745, work package AT-16PN230102. This section of the TLR satisfies PNNL's M3AT-16PN2301025 milestone and is focused on summarizing the design, development, and evaluation of two different phased-array ultrasonic testing (PA-UT) probe designs - a two-dimensional (2D) matrix phased-array probe, and two one-dimensional (1D) linear array probes, referred to as serial number 4 (SN4) engineering test units (ETUs). The 2D probe is a pulse-echo (PE), 32x2, 64-element matrix phased-array ETU. The 1D probes are 32x1 element linear array ETUs. This TLR also provides the results from a performance demonstration (PD) of in-sodium target detection trials at 260°C using both probe designs. This effort continues the iterative evolution supporting the longer term goal of producing and demonstrating a pre-manufacturing prototype ultrasonic probe that possesses the fundamental performance characteristics necessary to enable the development of a high-temperature sodium-cooled fast reactor (SFR) inspection system for in-sodium detection and imaging.

  6. FY16 Status of Immersion Phased Array Ultrasonic Probe Development and Performance Demonstration Results for Under Sodium Viewing

    Energy Technology Data Exchange (ETDEWEB)

    Diaz, Aaron A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Chamberlin, Clyde E. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Edwards, Matthew K. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hagge, Tobias J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Hughes, Michael S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Larche, Michael R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Mathews, Royce A. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Neill, Kevin J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Prowant, Matthew S. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

    2016-08-31

    This section of the Joint summary technical letter report (TLR) describes work conducted at the Pacific Northwest National Laboratory (PNNL) during FY 2016 (FY16) on the under-sodium viewing (USV) PNNL project 58745, work package AT-16PN230102. This section of the TLR satisfies PNNL’s M3AT-16PN2301025 milestone and is focused on summarizing the design, development, and evaluation of two different phased-array ultrasonic testing (PA-UT) probe designs—a two-dimensional (2D) matrix phased-array probe, and two one-dimensional (1D) linear array probes, referred to as serial number 4 (SN4) engineering test units (ETUs). The 2D probe is a pulse-echo (PE), 32×2, 64-element matrix phased-array ETU. The 1D probes are 32×1 element linear array ETUs. This TLR also provides the results from a performance demonstration (PD) of in-sodium target detection trials at 260°C using both probe designs. This effort continues the iterative evolution supporting the longer term goal of producing and demonstrating a pre-manufacturing prototype ultrasonic probe that possesses the fundamental performance characteristics necessary to enable the development of a high-temperature sodium-cooled fast reactor (SFR) inspection system for in-sodium detection and imaging.

  7. Proximity to natural gas wells and reported health status: results of a household survey in Washington County, Pennsylvania.

    Science.gov (United States)

    Rabinowitz, Peter M; Slizovskiy, Ilya B; Lamers, Vanessa; Trufan, Sally J; Holford, Theodore R; Dziura, James D; Peduzzi, Peter N; Kane, Michael J; Reif, John S; Weiss, Theresa R; Stowe, Meredith H

    2015-01-01

    Little is known about the environmental and public health impact of unconventional natural gas extraction activities, including hydraulic fracturing, that occur near residential areas. Our aim was to assess the relationship between household proximity to natural gas wells and reported health symptoms. We conducted a hypothesis-generating health symptom survey of 492 persons in 180 randomly selected households with ground-fed wells in an area of active natural gas drilling. Gas well proximity for each household was compared with the prevalence and frequency of reported dermal, respiratory, gastrointestinal, cardiovascular, and neurological symptoms. The number of reported health symptoms per person was higher among residents living 2 km from the nearest gas well (mean ± SD, 1.60 ± 2.14; p = 0.0002). In a model that adjusted for age, sex, household education, smoking, awareness of environmental risk, work type, and animals in house, reported skin conditions were more common in households 2 km from the nearest gas well (odds ratio = 4.1; 95% CI: 1.4, 12.3; p = 0.01). Upper respiratory symptoms were also more frequently reported in persons living in households gas wells (39%) compared with households 1-2 km or > 2 km from the nearest well (31 and 18%, respectively) (p = 0.004). No equivalent correlation was found between well proximity and other reported groups of respiratory, neurological, cardiovascular, or gastrointestinal conditions. Although these results should be viewed as hypothesis generating, and the population studied was limited to households with a ground-fed water supply, proximity of natural gas wells may be associated with the prevalence of health symptoms including dermal and respiratory conditions in residents living near natural gas extraction activities. Further study of these associations, including the role of specific air and water exposures, is warranted.

  8. Control of Transboundary Movement of Radioactive Material Inadvertently Incorporated into Scrap Metal and Semi-finished Products of the Metal Recycling Industries. Results of the Meetings Conducted to Develop a Draft Code of Conduct

    International Nuclear Information System (INIS)

    2014-02-01

    In 2010, the IAEA initiated the development of a code of conduct on the transboundary movement of radioactive material inadvertently incorporated into scrap metal and semi- finished products of the metal recycling industries (Metal Recycling Code of Conduct). The Metal Recycling Code of Conduct was intended to harmonize the approaches of Member States in relation to the discovery of radioactive material that may inadvertently be present in scrap metals and semi-finished products subject to transboundary movement, and their safe handling and management to facilitate regulatory control. The Metal Recycling Code of Conduct was envisaged as being complementary to the Safety Guide on Control of Orphan Sources and Other Radioactive Material in the Metal Recycling and Production Industries (IAEA Safety Standards Series No. SSG-17), which provides recommendations, principally within a national context, on the protection of workers, members of the public and the environment in relation to the control of radioactive material inadvertently incorporated in scrap metal. In February 2013, the third open-ended meeting of technical and legal experts to develop the Metal Recycling Code of Conduct was organized. The objective of this meeting was to address the comments received from Member States and to finalize the text of the draft Metal Recycling Code of Conduct. Representatives from 55 Member States, one non-Member State and the EU, together with seven observers from the metal recycling industry, reviewed the comments and revised the draft accordingly. In September 2013, in Resolution GC(57)/RES/9, the IAEA General Conference recorded that it 'Appreciates the intensive efforts undertaken by the Secretariat to develop a code of conduct on the transboundary movement of scrap metal, or materials produced from scrap metal, that may inadvertently contain radioactive material, and encourages the Secretariat to make the results of the discussion conducted on this issue available to

  9. Perturbations in the Photosynthetic Pigment Status Result in Photooxidation-Induced Crosstalk between Carotenoid and Porphyrin Biosynthetic Pathways

    Directory of Open Access Journals (Sweden)

    Joon-Heum Park

    2017-11-01

    Full Text Available Possible crosstalk between the carotenoid and porphyrin biosynthetic pathways under photooxidative conditions was investigated by using their biosynthetic inhibitors, norflurazon (NF and oxyfluorfen (OF. High levels of protoporphyrin IX (Proto IX accumulated in rice plants treated with OF, whereas Proto IX decreased in plants treated with NF. Both NF and OF treatments resulted in greater decreases in MgProto IX, MgProto IX methyl ester, and protochlorophyllide. Activities and transcript levels of most porphyrin biosynthetic enzymes, particularly in the Mg-porphyrin branch, were greatly down-regulated in NF and OF plants. In contrast, the transcript levels of GSA, PPO1, and CHLD as well as FC2 and HO2 were up-regulated in NF-treated plants, while only moderate increases in FC2 and HO2 were observed in the early stage of OF treatment. Phytoene, antheraxanthin, and zeaxanthin showed high accumulation in NF-treated plants, whereas other carotenoid intermediates greatly decreased. Transcript levels of carotenoid biosynthetic genes, PSY1 and PDS, decreased in response to NF and OF, whereas plants in the later stage of NF treatment exhibited up-regulation of BCH and VDE as well as recovery of PDS. However, perturbed porphyrin biosynthesis by OF did not noticeably influence levels of carotenoid metabolites, regardless of the strong down-regulation of carotenoid biosynthetic genes. Both NF and OF plants appeared to provide enhanced protection against photooxidative damage, not only by scavenging of Mg-porphyrins, but also by up-regulating FC2, HO2, and Fe-chelatase, particularly with increased levels of zeaxanthin via up-regulation of BCH and VDE in NF plants. On the other hand, the up-regulation of GSA, PPO1, and CHLD under inhibition of carotenogenic flux may be derived from the necessity to recover impaired chloroplast biogenesis during photooxidative stress. Our study demonstrates that perturbations in carotenoid and porphyrin biosynthesis coordinate

  10. Perturbations in the Photosynthetic Pigment Status Result in Photooxidation-Induced Crosstalk between Carotenoid and Porphyrin Biosynthetic Pathways.

    Science.gov (United States)

    Park, Joon-Heum; Tran, Lien H; Jung, Sunyo

    2017-01-01

    Possible crosstalk between the carotenoid and porphyrin biosynthetic pathways under photooxidative conditions was investigated by using their biosynthetic inhibitors, norflurazon (NF) and oxyfluorfen (OF). High levels of protoporphyrin IX (Proto IX) accumulated in rice plants treated with OF, whereas Proto IX decreased in plants treated with NF. Both NF and OF treatments resulted in greater decreases in MgProto IX, MgProto IX methyl ester, and protochlorophyllide. Activities and transcript levels of most porphyrin biosynthetic enzymes, particularly in the Mg-porphyrin branch, were greatly down-regulated in NF and OF plants. In contrast, the transcript levels of GSA, PPO1 , and CHLD as well as FC2 and HO2 were up-regulated in NF-treated plants, while only moderate increases in FC2 and HO2 were observed in the early stage of OF treatment. Phytoene, antheraxanthin, and zeaxanthin showed high accumulation in NF-treated plants, whereas other carotenoid intermediates greatly decreased. Transcript levels of carotenoid biosynthetic genes, PSY1 and PDS , decreased in response to NF and OF, whereas plants in the later stage of NF treatment exhibited up-regulation of BCH and VDE as well as recovery of PDS . However, perturbed porphyrin biosynthesis by OF did not noticeably influence levels of carotenoid metabolites, regardless of the strong down-regulation of carotenoid biosynthetic genes. Both NF and OF plants appeared to provide enhanced protection against photooxidative damage, not only by scavenging of Mg - porphyrins, but also by up-regulating FC2, HO2 , and Fe-chelatase, particularly with increased levels of zeaxanthin via up-regulation of BCH and VDE in NF plants. On the other hand, the up-regulation of GSA, PPO1 , and CHLD under inhibition of carotenogenic flux may be derived from the necessity to recover impaired chloroplast biogenesis during photooxidative stress. Our study demonstrates that perturbations in carotenoid and porphyrin biosynthesis coordinate the

  11. LDGM Codes for Channel Coding and Joint Source-Channel Coding of Correlated Sources

    Directory of Open Access Journals (Sweden)

    Javier Garcia-Frias

    2005-05-01

    Full Text Available We propose a coding scheme based on the use of systematic linear codes with low-density generator matrix (LDGM codes for channel coding and joint source-channel coding of multiterminal correlated binary sources. In both cases, the structures of the LDGM encoder and decoder are shown, and a concatenated scheme aimed at reducing the error floor is proposed. Several decoding possibilities are investigated, compared, and evaluated. For different types of noisy channels and correlation models, the resulting performance is very close to the theoretical limits.

  12. Monte Carlo simulation on nuclear energy study. Annual report of Nuclear Code Evaluation Committee

    International Nuclear Information System (INIS)

    Sakurai, Kiyoshi; Yamamoto, Toshihiro

    1999-03-01

    In this report, research results discussed in 1998 fiscal year at Nuclear Code Evaluation Special Committee of Nuclear Code Committee were summarised. Present status of Monte Carlo calculation in high energy region investigated / discussed at Monte Carlo simulation working-group and automatic compilation system for MCNP cross sections developed at MCNP high temperature library compilation working-group were described. The 6 papers are indexed individually. (J.P.N.)

  13. The sphere-PAC fuel code 'SPHERE-3'

    Energy Technology Data Exchange (ETDEWEB)

    Wallin, H

    2000-07-01

    Sphere-PAC fuel is an advanced nuclear fuel, in which the cladding tube is filled with small fuel spheres instead of the more usual fuel pellets. At PSI, the irradiation behaviour of sphere-PAC fuel is calculated using the computer code SPHERE-3. The paper describes the present status of the SPHERE-3 code, and some results of the qualification process against experimental data. (author)

  14. Supervised Convolutional Sparse Coding

    KAUST Repository

    Affara, Lama Ahmed

    2018-04-08

    Convolutional Sparse Coding (CSC) is a well-established image representation model especially suited for image restoration tasks. In this work, we extend the applicability of this model by proposing a supervised approach to convolutional sparse coding, which aims at learning discriminative dictionaries instead of purely reconstructive ones. We incorporate a supervised regularization term into the traditional unsupervised CSC objective to encourage the final dictionary elements to be discriminative. Experimental results show that using supervised convolutional learning results in two key advantages. First, we learn more semantically relevant filters in the dictionary and second, we achieve improved image reconstruction on unseen data.

  15. The effects of fatty fish intake on adolescents' nutritional status and associations with attention performance: results from the FINS-TEENS randomized controlled trial.

    Science.gov (United States)

    Handeland, Katina; Skotheim, Siv; Baste, Valborg; Graff, Ingvild E; Frøyland, Livar; Lie, Øyvind; Kjellevold, Marian; Markhus, Maria W; Stormark, Kjell M; Øyen, Jannike; Dahl, Lisbeth

    2018-02-23

    Adolescence involves changes in dietary habits that may induce imbalances in the intake of different nutrients. Fish is an important dietary source of omega-3 (n-3) long-chain polyunsaturated fatty acids (LCPUFAs), vitamin D, several minerals and high-quality protein. By using secondary outcomes and exploratory analyses, the aims of this paper were to evaluate if nutritional biomarkers (red blood cell fatty acids, serum (s)-25(OH)D, s-ferritin and urinary iodine concentration (UIC)) were altered during a dietary intervention, and if they mediated previously reported changes in attention performance. In addition, to examine the status of the biomarkers and explore associations between dietary pattern, biomarkers and attention performance cross-sectionally at baseline. The Fish Intervention Studies-TEENS (FINS-TEENS) was a three-armed intervention trial, including adolescents from eight secondary schools (n = 415; age: 14-15y) in Bergen, Norway. Participants were individually randomized to receive either fish meals, meat meals or n-3 LCPUFA supplements, three times a week for a total of 12 weeks. Blood and urine samples were collected pre and post intervention and attention performance was assessed with the d2 test of attention. Analyses of covariance (ANCOVA) assessed differences between groups in changes of biomarkers and linear mixed models were applied in analyses of attention performance and biomarkers. The trial is registered in ClinicalTrials.gov (NCT02350322). At baseline, the mean omega-3 index was 5.8 ± 1.3% and deficient status were identified for s-25(OH)D (54%), s-ferritin (10%) and UIC (40%). The intervention resulted in an increase in DHA and the omega-3 index which was larger in the supplement group compared to the fish and meat group (P < 0.01), and in the fish group compared to the meat group (P < 0.01). No differences between the groups were observed for changes in 25(OH)D, s-ferritin or UIC. None of the biomarkers mediated

  16. Diagonal Eigenvalue Unity (DEU) code for spectral amplitude coding-optical code division multiple access

    Science.gov (United States)

    Ahmed, Hassan Yousif; Nisar, K. S.

    2013-08-01

    Code with ideal in-phase cross correlation (CC) and practical code length to support high number of users are required in spectral amplitude coding-optical code division multiple access (SAC-OCDMA) systems. SAC systems are getting more attractive in the field of OCDMA because of its ability to eliminate the influence of multiple access interference (MAI) and also suppress the effect of phase induced intensity noise (PIIN). In this paper, we have proposed new Diagonal Eigenvalue Unity (DEU) code families with ideal in-phase CC based on Jordan block matrix with simple algebraic ways. Four sets of DEU code families based on the code weight W and number of users N for the combination (even, even), (even, odd), (odd, odd) and (odd, even) are constructed. This combination gives DEU code more flexibility in selection of code weight and number of users. These features made this code a compelling candidate for future optical communication systems. Numerical results show that the proposed DEU system outperforms reported codes. In addition, simulation results taken from a commercial optical systems simulator, Virtual Photonic Instrument (VPI™) shown that, using point to multipoint transmission in passive optical network (PON), DEU has better performance and could support long span with high data rate.

  17. Aztheca Code; Codigo Aztheca

    Energy Technology Data Exchange (ETDEWEB)

    Quezada G, S.; Espinosa P, G. [Universidad Autonoma Metropolitana, Unidad Iztapalapa, San Rafael Atlixco No. 186, Col. Vicentina, 09340 Ciudad de Mexico (Mexico); Centeno P, J.; Sanchez M, H., E-mail: sequga@gmail.com [UNAM, Facultad de Ingenieria, Ciudad Universitaria, Circuito Exterior s/n, 04510 Ciudad de Mexico (Mexico)

    2017-09-15

    This paper presents the Aztheca code, which is formed by the mathematical models of neutron kinetics, power generation, heat transfer, core thermo-hydraulics, recirculation systems, dynamic pressure and level models and control system. The Aztheca code is validated with plant data, as well as with predictions from the manufacturer when the reactor operates in a stationary state. On the other hand, to demonstrate that the model is applicable during a transient, an event occurred in a nuclear power plant with a BWR reactor is selected. The plant data are compared with the results obtained with RELAP-5 and the Aztheca model. The results show that both RELAP-5 and the Aztheca code have the ability to adequately predict the behavior of the reactor. (Author)

  18. ESCADRE and ICARE code systems

    International Nuclear Information System (INIS)

    Reocreux, M.; Gauvain, J.

    1992-01-01

    The French sever accident code development program is following two parallel approaches: the first one is dealing with ''integral codes'' which are designed for giving immediate engineer answers, the second one is following a more mechanistic way in order to have the capability of detailed analysis of experiments, in order to get a better understanding of the scaling problem and reach a better confidence in plant calculations. In the first approach a complete system has been developed and is being used for practical cases: this is the ESCADRE system. In the second approach, a set of codes dealing first with primary circuit is being developed: a mechanistic core degradation code, ICARE, has been issued and is being coupled with the advanced thermalhydraulic code CATHARE. Fission product codes have been also coupled to CATHARE. The ''integral'' ESCADRE system and the mechanistic ICARE and associated codes are described. Their main characteristics are reviewed and the status of their development and assessment given. Future studies are finally discussed. 36 refs, 4 figs, 1 tab

  19. Development of M3C code for Monte Carlo reactor physics criticality calculations

    International Nuclear Information System (INIS)

    Kumar, Anek; Kannan, Umasankari; Krishanani, P.D.

    2015-06-01

    The development of Monte Carlo code (M3C) for reactor design entails use of continuous energy nuclear data and Monte Carlo simulations for each of the neutron interaction processes. BARC has started a concentrated effort for developing a new general geometry continuous energy Monte Carlo code for reactor physics calculation indigenously. The code development required a comprehensive understanding of the basic continuous energy cross section sets. The important features of this code are treatment of heterogeneous lattices by general geometry, use of point cross sections along with unionized energy grid approach, thermal scattering model for low energy treatment, capability of handling the microscopic fuel particles dispersed randomly. The capability of handling the randomly dispersed microscopic fuel particles which is very useful for the modeling of High-Temperature Gas-Cooled reactor fuels which are composed of thousands of microscopic fuel particle (TRISO fuel particle), randomly dispersed in a graphite matrix. The Monte Carlo code for criticality calculation is a pioneering effort and has been used to study several types of lattices including cluster geometries. The code has been verified for its accuracy against more than 60 sample problems covering a wide range from simple (like spherical) to complex geometry (like PHWR lattice). Benchmark results show that the code performs quite well for the criticality calculation of the system. In this report, the current status of the code, features of the code, some of the benchmark results for the testing of the code and input preparation etc. are discussed. (author)

  20. Automatic coding method of the ACR Code

    International Nuclear Information System (INIS)

    Park, Kwi Ae; Ihm, Jong Sool; Ahn, Woo Hyun; Baik, Seung Kook; Choi, Han Yong; Kim, Bong Gi

    1993-01-01

    The authors developed a computer program for automatic coding of ACR(American College of Radiology) code. The automatic coding of the ACR code is essential for computerization of the data in the department of radiology. This program was written in foxbase language and has been used for automatic coding of diagnosis in the Department of Radiology, Wallace Memorial Baptist since May 1992. The ACR dictionary files consisted of 11 files, one for the organ code and the others for the pathology code. The organ code was obtained by typing organ name or code number itself among the upper and lower level codes of the selected one that were simultaneous displayed on the screen. According to the first number of the selected organ code, the corresponding pathology code file was chosen automatically. By the similar fashion of organ code selection, the proper pathologic dode was obtained. An example of obtained ACR code is '131.3661'. This procedure was reproducible regardless of the number of fields of data. Because this program was written in 'User's Defined Function' from, decoding of the stored ACR code was achieved by this same program and incorporation of this program into program in to another data processing was possible. This program had merits of simple operation, accurate and detail coding, and easy adjustment for another program. Therefore, this program can be used for automation of routine work in the department of radiology