Conocimientos sobre salud bucal en los círculos de abuelos

Directory of Open Access Journals (Sweden)

Rosa María González Ramos

Full Text Available Introducción: el envejecimiento ha estado presente en todas las etapas del desarrollo social, cada día, más personas sobrepasan las barreras cronológicas que el hombre ha situado como la vejez, lo que significa un reto importante para las sociedades modernas. La salud bucal juega un papel importante para mantener la calidad de vida en la tercera edad. Objetivo: identificar los conocimientos sobre salud bucal de los adultos mayores de los círculos de abuelos del Policlínico 19 de abril, en el periodo 2008-2010. Métodos: se realizó una investigación descriptiva. El universo quedó constituido por 101 personas, pertenecientes a los cinco círculos de abuelos del Policlínico 19 de Abril. El universo quedó constituido por 101 personas pertenecientes a los cinco círculos de abuelos. Las variables estudiadas fueron son: edad, sexo, conocimientos sobre las funciones de los dientes, el efecto de los hábitos nocivos, higiene bucal, frecuencia de cepillado. La obtención de la información se realizó por la autora y colaboradores calibrados con anterioridad. Se aplicó una encuesta previo consentimiento informado a los ancianos. Resultados: predominó el sexo femenino en 71,2 %. El 78,2 % conocen que la masticación es una de las funciones de los dientes. El 84,1 % no conocen los efectos del tabaquismo y el alcoholismo sobre la cavidad bucal; existe un desconocimiento del 76,2 % de la importancia de la higiene bucal y del cepillado correcto. Conclusiones: predomina el sexo femenino, existe desconocimiento de las funciones de los dientes, los efectos nocivos del tabaco y el alcohol, así como de la higiene bucal adecuada.

El embarazo: Su relación con la salud bucal

OpenAIRE

Hilda Elia Rodríguez Chala; Melvis López Santana

2003-01-01

Se abordan las transformaciones ocurridas en las gestantes que condicionan la aparición o desarrollo de enfermedades bucales. Variaciones en los niveles de hormonas sexuales femeninas, siliva, microorganismos, dieta, entre otros, constituyen factores que pueden incidir en el desarrollo de enfermedades bucales, que debemos tener en cuenta durante la gestación. El tejido dentario, los de soporte y sostén del diente, la mucosa bucal entre otros, son los más vulnerables a ser afectados por estos ...

A first accident simulation for Angra-1 power plant using the ALMOD computer code

International Nuclear Information System (INIS)

Camargo, C.T.M.

1981-02-01

The acquisition of the Almod computer code from GRS-Munich to CNEN has permited doing calculations of transients in PWR nuclear power plants, in which doesn't occur loss of coolant. The implementation of the german computer code Almod and its application in the calculation of Angra-1, a nuclear power plant different from the KWU power plants, demanded study and models adaptation; and due to economic reasons simplifications and optimizations were necessary. The first results define the analytical potential of the computer code, confirm the adequacy of the adaptations done and provide relevant conclusions about the Angra-1 safety analysis, showing at the same time areas in which the model can be applied or simply improved. (Author) [pt

SASSYS-1 computer code verification with EBR-II test data

International Nuclear Information System (INIS)

Warinner, D.K.; Dunn, F.E.

1985-01-01

The EBR-II natural circulation experiment, XX08 Test 8A, is simulated with the SASSYS-1 computer code and the results for the latter are compared with published data taken during the transient at selected points in the core. The SASSYS-1 results provide transient temperature and flow responses for all points of interest simultaneously during one run, once such basic parameters as pipe sizes, initial core flows, and elevations are specified. The SASSYS-1 simulation results for the EBR-II experiment XX08 Test 8A, conducted in March 1979, are within the published plant data uncertainties and, thereby, serve as a partial verification/validation of the SASSYS-1 code

Percepción en la salud bucal de adolescentes embarazadas

Directory of Open Access Journals (Sweden)

Maria Luiza da Matta Felisberto Fernandes

2012-02-01

Full Text Available Objetivo: Verificar la interferencia del embarazo en las percepciones en salud bucal de adolescentes embarazadas de 12 a 18 años, con baja condición socio-económica, residentes en Belo Horizonte, Minas Gerais. Material y Métodos: Se realizó un estudio cualitativo con las adolescentes (n=60 divididas en dos grupos: embarazada (n=30 o no embarazada (n=30. Entre las gestantes, diez estaban en el primer trimestre de gestación, trece en el segundo, y siete en el último trimestre de gestación. Los datos fueron recolectados a través de entrevistas individuales. Se realizó el análisis del contenido. Resultados: Tres categorías de análisis surgieron a través del contenido manifestado en ambos grupos: consciencia de determinantes de la salud bucal (conocimientos y actitudes, reacciones emocionales relativas a la salud bucal (sentimientos positivos, pasividad y sentimientos negativos y valores en salud bucal (apariencia, función social de los padres. Conclusión: Entre las jóvenes se observó que la experiencia del embarazo no interfirió en las percepciones en salud bucal.

The computer code Eurdyn - 1 M. (Release 1) Part 2: User's Manual

International Nuclear Information System (INIS)

Donea, J.; Giuliani, S.

1979-01-01

This report is the user's manual for the computer code Eurdyn-1 M developed at the J.R.C. Ispra for use in containment and fuel subassembly analyses for fast reactor safety studies. The input data are defined and a test problem is presented to illustrate both the input and the output of results

Liquen plano bucal y displasia epitelial

Directory of Open Access Journals (Sweden)

Joaquín Urbizo Vélez

epitelial al hallar que el 42,1 % de los casos del tipo erosivo presentaron esta alteración, con respecto al 17,7 % de los casos del tipo reticular. Conclusiones: la presencia de displasia ligera es un hallazgo posible en el liquen plano bucal, más frecuente en el tipo erosivo y que, hasta tanto no se demuestre convincentemente lo contrario, el liquen plano bucal debe ser una lesión tributaria de un seguimiento a corto, mediano y largo plazo.

Cloud Computing for Complex Performance Codes.

Energy Technology Data Exchange (ETDEWEB)

Appel, Gordon John [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hadgu, Teklu [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Klein, Brandon Thorin [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Miner, John Gifford [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-02-01

This report describes the use of cloud computing services for running complex public domain performance assessment problems. The work consisted of two phases: Phase 1 was to demonstrate complex codes, on several differently configured servers, could run and compute trivial small scale problems in a commercial cloud infrastructure. Phase 2 focused on proving non-trivial large scale problems could be computed in the commercial cloud environment. The cloud computing effort was successfully applied using codes of interest to the geohydrology and nuclear waste disposal modeling community.

Computer codes in particle transport physics

International Nuclear Information System (INIS)

Pesic, M.

2004-01-01

Simulation of transport and interaction of various particles in complex media and wide energy range (from 1 MeV up to 1 TeV) is very complicated problem that requires valid model of a real process in nature and appropriate solving tool - computer code and data library. A brief overview of computer codes based on Monte Carlo techniques for simulation of transport and interaction of hadrons and ions in wide energy range in three dimensional (3D) geometry is shown. Firstly, a short attention is paid to underline the approach to the solution of the problem - process in nature - by selection of the appropriate 3D model and corresponding tools - computer codes and cross sections data libraries. Process of data collection and evaluation from experimental measurements and theoretical approach to establishing reliable libraries of evaluated cross sections data is Ion g, difficult and not straightforward activity. For this reason, world reference data centers and specialized ones are acknowledged, together with the currently available, state of art evaluated nuclear data libraries, as the ENDF/B-VI, JEF, JENDL, CENDL, BROND, etc. Codes for experimental and theoretical data evaluations (e.g., SAMMY and GNASH) together with the codes for data processing (e.g., NJOY, PREPRO and GRUCON) are briefly described. Examples of data evaluation and data processing to generate computer usable data libraries are shown. Among numerous and various computer codes developed in transport physics of particles, the most general ones are described only: MCNPX, FLUKA and SHIELD. A short overview of basic application of these codes, physical models implemented with their limitations, energy ranges of particles and types of interactions, is given. General information about the codes covers also programming language, operation system, calculation speed and the code availability. An example of increasing computation speed of running MCNPX code using a MPI cluster compared to the code sequential option

40 CFR 194.23 - Models and computer codes.

Science.gov (United States)

2010-07-01

... 40 Protection of Environment 24 2010-07-01 2010-07-01 false Models and computer codes. 194.23... General Requirements § 194.23 Models and computer codes. (a) Any compliance application shall include: (1... obtain stable solutions; (iv) Computer models accurately implement the numerical models; i.e., computer...

El embarazo: Su relación con la salud bucal

Directory of Open Access Journals (Sweden)

Hilda Elia Rodríguez Chala

2003-08-01

Full Text Available Se abordan las transformaciones ocurridas en las gestantes que condicionan la aparición o desarrollo de enfermedades bucales. Variaciones en los niveles de hormonas sexuales femeninas, siliva, microorganismos, dieta, entre otros, constituyen factores que pueden incidir en el desarrollo de enfermedades bucales, que debemos tener en cuenta durante la gestación. El tejido dentario, los de soporte y sostén del diente, la mucosa bucal entre otros, son los más vulnerables a ser afectados por estos cambios, lo que repercute en la salud bucal.The transformations occurring among pregnant women that make possible the appearance or development of oral diseases are dealt with. The variations in the levels of female sex hormones, saliva, microorganisms and diet, among others, are some of the factors that may influence the development of oral diseases that should be taken into account during pregnancy. The dental tissue, those tissues supporting the tooth, and the oral mucose, among others, are the most vulnerable to be affected by these changes, which have a repercussion on oral health.

The first accident simulation of Angra-1 power plant using the ALMOD computer code

International Nuclear Information System (INIS)

Camargo, C.T.M.

1981-01-01

The implementation of the german computer code ALMOD and its application in the calculation of Angra-1, a nuclear power plant different from the KWU power plants, demanded study and models adaptation, and due to economic reasons simplifications and optimizations were necessary. The first results define the analytical potential of the computer code, confirm the adequacy of the adaptations done and provide relevant conclusions about the Angra-1 safety analysis, showing at the same time areas in which the model can be applied or simply improved. (E.G.) [pt

Determinantes sociais e saúde bucal de adultos nas capitais do Brasil

Directory of Open Access Journals (Sweden)

Roberto Eduardo Bueno

2014-07-01

Full Text Available OBJETIVO: Investigar a correlação entre o índice Determinantes Sociais de Saúde Bucal (DSSB e indicadores sociais, indicadores de saúde bucal e determinantes sociais intermediários, representados pelos indicadores da Política Nacional de Saúde Bucal. MÉTODOS: Este estudo ecológico abrangeu 5 915 adultos de 35 a 44 anos em 27 capitais no Brasil. Os indicadores de desfechos em saúde bucal - perda dentária, dentes restaurados e Índice de Cuidados Odontológicos (ICO - foram obtidos do levantamento epidemiológico SB Brasil 2010. Os indicadores sociais (determinantes sociais estruturais e da Política Nacional de Saúde Bucal foram obtidos de censos demográficos e do Ministério da Saúde. RESULTADOS: Uma correlação de Pearson (r moderada foi observada entre o índice DSSB e ICO (r = 0,580, dentes restaurados (r = 0,545 e perda dentária (r = - 0,490. Houve uma correlação forte do componente equidade social com o ICO (r = 0,856, dentes restaurados (r = 0,822 e perda dentária (r = -0,665. Não houve associação estatisticamente significativa desses desfechos em saúde bucal com os componentes relativos à atenção primária e secundária à saúde bucal. O componente equidade social explicou 44% da variância da perda dentária, 68% da variância de dentes restaurados e 73% da variância do ICO. CONCLUSÕES: O índice DSSB e seu componente equidade social se correlacionaram significativamente com desfechos em saúde bucal de adultos nas capitais brasileiras. Portanto, políticas equitativas devem priorizar ações direcionadas aos DSSB, tais como ampliação da cobertura de saneamento e de água fluoretada, e redução da pobreza e das iniquidades regionais.

Autopercepcao da saude bucal entre adultos na regiao Nordeste do Brasil

Directory of Open Access Journals (Sweden)

Edivania Barbosa do Vale

2013-12-01

Full Text Available OBJETIVO: Identificar a autopercepção da saúde bucal por adultos e variáveis associadas. MÉTODOS: Estudo realizado com os dados da Pesquisa Nacional de Saúde Bucal SBBrasil 2010 relativos a 2.456 adultos de 35 a 44 anos da região Nordeste. A variável dependente foi a autopercepção da saúde bucal. As variáveis independentes foram agrupadas em: demográficas, predisposição/facilitação, condição de saúde bucal e relacionadas à autopercepção da necessidade de tratamento. O teste de Rao e Scott foi utilizado para avaliar a associação entre essas variáveis. O efeito das variáveis independentes sobre o desfecho foi avaliado pelo modelo de regressão logística multinominal segundo modelo hierarquizado, em duas etapas: análise simples e análise múltipla hierarquizada. RESULTADOS: A autopercepção positiva da saúde bucal foi observada em 37% dos participantes. No modelo final, as características diretamente associadas a essa autopercepção foram: ser branco, ter renda familiar superior a R$ 500,00, possuir número de bens acima da mediana, ter maior número de dentes hígidos, não apresentar sangramento, não necessitar de prótese, Oral Impacts on Daily Performances = 0, não necessitar de tratamento e ter ido ao dentista há menos de três anos. CONCLUSÕES: Os resultados mostram que a autopercepção da saúde bucal dos adultos residentes no Nordeste brasileiro está diretamente associada a uma estrutura multidimensional de fatores. As baixas condições econômicas associadas às condições clínicas deficientes dessa população causam grande impacto na sua autopercepção da saúde bucal.

Computer-assisted Particle-in-Cell code development

International Nuclear Information System (INIS)

Kawata, S.; Boonmee, C.; Teramoto, T.; Drska, L.; Limpouch, J.; Liska, R.; Sinor, M.

1997-12-01

This report presents a new approach for an electromagnetic Particle-in-Cell (PIC) code development by a computer: in general PIC codes have a common structure, and consist of a particle pusher, a field solver, charge and current density collections, and a field interpolation. Because of the common feature, the main part of the PIC code can be mechanically developed on a computer. In this report we use the packages FIDE and GENTRAN of the REDUCE computer algebra system for discretizations of field equations and a particle equation, and for an automatic generation of Fortran codes. The approach proposed is successfully applied to the development of 1.5-dimensional PIC code. By using the generated PIC code the Weibel instability in a plasma is simulated. The obtained growth rate agrees well with the theoretical value. (author)

Determinación del estado de salud bucal en embarazadas

Directory of Open Access Journals (Sweden)

Irma Aracelia Sueiro Sánchez

2015-09-01

Full Text Available Fundamento: el embarazo puede perturbar el equilibrio bucal de la futura mamá, por lo que determinar el comportamiento de la salud bucal de estas pacientes constituye una prioridad de los servicios estomatológicos. Objetivo: determinar el estado de salud bucal en embarazadas del consultorio de Elpidio Gómez, de Palmira de enero a diciembre de 2013. Métodos: se realizó un estudio descriptivo de serie de casos. El universo estuvo constituido por 41 pacientes de 15 hasta 59 años atendidas en consulta. Las variables analizadas fueron: edad, nivel de conocimiento, clasificación epidemiológica según salud bucal, factores de riesgo y procesos inflamatorios en periodonto de protección. La recolección de la información se realizó por medio de encuestas de salud bucodental y de conocimiento, previo consentimiento informado al paciente y a la institución. Resultados: predominó el grupo de edad de 19-34, se evaluó de regular el nivel de conocimiento de salud bucal de las pacientes, prevaleció como categoría las enfermas; de los factores de riesgo que más afectaron se encontró el cepillado incorrecto. La gingivitis crónica edematosa predominó, siendo las de 15 a 18 las más perjudicadas. El índice individual para piezas dentarias permanentes aumentó con la edad, la necesidad de prótesis parcial afectó más a las de 19 a 34. Conclusión: el estado de la salud bucal de las embarazadas fue evaluado de mal, porque estas pacientes no acudieron a consulta por restarle importancia a su atención estomatológica. Deben ser reevaluadas las estrategias para incrementar la cultura sanitaria, además de un seguimiento periódico por consulta y atención al hogar de las pacientes embarazadas.

Programas educativos em saúde bucal para populações adultas

OpenAIRE

Rota, Lucimara Magon; Queluz, Dagmar de Paula; Mialhe, Fábio Luiz

2016-01-01

Este trabalho teve como objetivo avaliar os aspectos relacionados ao perfil epidemiológico e a autopercepção das condições de saúde bucal, além dos métodos de educação em saúde voltados à população adulta, a fim de contribuir no planejamento de programas educativos para esta população. Com base naanálise dos dados bibliográficos coletados, conclui-se que a educação em saúde bucal para adultos é uma importante ferramenta de manutenção da saúde bucal. Dentre elas destaca-se a cárie dentária, o ...

Verification of RESRAD-build computer code, version 3.1

International Nuclear Information System (INIS)

2003-01-01

RESRAD-BUILD is a computer model for analyzing the radiological doses resulting from the remediation and occupancy of buildings contaminated with radioactive material. It is part of a family of codes that includes RESRAD, RESRAD-CHEM, RESRAD-RECYCLE, RESRAD-BASELINE, and RESRAD-ECORISK. The RESRAD-BUILD models were developed and codified by Argonne National Laboratory (ANL); version 1.5 of the code and the user's manual were publicly released in 1994. The original version of the code was written for the Microsoft DOS operating system. However, subsequent versions of the code were written for the Microsoft Windows operating system. The purpose of the present verification task (which includes validation as defined in the standard) is to provide an independent review of the latest version of RESRAD-BUILD under the guidance provided by ANSI/ANS-10.4 for verification and validation of existing computer programs. This approach consists of a posteriori V and V review which takes advantage of available program development products as well as user experience. The purpose, as specified in ANSI/ANS-10.4, is to determine whether the program produces valid responses when used to analyze problems within a specific domain of applications, and to document the level of verification. The culmination of these efforts is the production of this formal Verification Report. The first step in performing the verification of an existing program was the preparation of a Verification Review Plan. The review plan consisted of identifying: Reason(s) why a posteriori verification is to be performed; Scope and objectives for the level of verification selected; Development products to be used for the review; Availability and use of user experience; and Actions to be taken to supplement missing or unavailable development products. The purpose, scope and objectives for the level of verification selected are described in this section of the Verification Report. The development products that were used

Associação entre resiliência e qualidade de vida relacionada à saúde bucal em idosos

Directory of Open Access Journals (Sweden)

Maurício Fernando Nunes Teixeira

2015-03-01

Full Text Available OBJETIVO: Avaliar a associação entre resiliência e qualidade de vida relacionada à saúde bucal, por meio de uma abordagem hierárquica baseada em um modelo teórico conceitual em uma coorte de idosos do Rio Grande do Sul. MÉTODOS: Foi conduzido um estudo transversal aninhado a um estudo de coorte, em 2008. Foram avaliados 498 idosos de Carlos Barbosa, Rio Grande do Sul. As medidas avaliadas foram sociodemográficas, comportamentos de saúde, qualidade de vida relacionada à saúde bucal, medida pelo Oral Health Impact Profile (OHIP-14, Escala de Resiliência e CPOD. A associação entre o potencial de resiliência e os impactos na percepção de saúde bucal relacionados à qualidade de vida foi verificada por meio de regressão binomial negativa. Razões das médias (RM são apresentadas com seus intervalos de confiança de 95% (IC95%. RESULTADOS: Maiores médias do OHIP foram encontradas entre mulheres (6,7 ± 6,3; p = 0,011, moradores da zona rural (7,3 ± 6,7; p = 0,004 e solteiros (8,0 ± 6,3; p = 0,032. O modelo final da análise multivariada mostrou que ser morador da zona rural (RM = 1,32; IC95% 1,06 - 1,65 e casado (RM = 1,36; IC95% 1,07 - 1,72 foram variáveis independentemente associadas à qualidade de vida relacionada à saúde bucal. Não houve associação entre resiliência e qualidade de vida relacionada à saúde bucal. CONCLUSÃO: Os resultados sugerem que variáveis sociodemográficas estão associados à qualidade de vida relacionada à saúde bucal. A hipótese de que a resiliência pudesse exercer um papel importante no desfecho não foi confirmada.

Improvement of Level-1 PSA computer code package -A study for nuclear safety improvement-

International Nuclear Information System (INIS)

Park, Chang Kyu; Kim, Tae Woon; Ha, Jae Joo; Han, Sang Hoon; Cho, Yeong Kyun; Jeong, Won Dae; Jang, Seung Cheol; Choi, Young; Seong, Tae Yong; Kang, Dae Il; Hwang, Mi Jeong; Choi, Seon Yeong; An, Kwang Il

1994-07-01

This year is the second year of the Government-sponsored Mid- and Long-Term Nuclear Power Technology Development Project. The scope of this subproject titled on 'The Improvement of Level-1 PSA Computer Codes' is divided into three main activities : (1) Methodology development on the under-developed fields such as risk assessment technology for plant shutdown and external events, (2) Computer code package development for Level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in the area of PSA methodology development, foreign PSA reports on shutdown and external events have been reviewed and various PSA methodologies have been compared. Level-1 PSA code KIRAP and CCF analysis code COCOA are converted from KOS to Windows. Human reliability database has been also established in this year. In the area of new technology applications, fuzzy set theory and entropy theory are used to estimate component life and to develop a new measure of uncertainty importance. Finally, in the field of application study of PSA technique to reactor regulation, a strategic study to develop a dynamic risk management tool PEPSI and the determination of inspection and test priority of motor operated valves based on risk importance worths have been studied. (Author)

Vigilancia epidemiológica del estado de salud bucal

OpenAIRE

. Amado Rodríguez Calzadilla; . Carolina Valiente Zaldívar

1999-01-01

Se exponen aspectos relacionados con la vigilancia epidemiológica del estado de salud bucal de la población general, con fines metodológicos. Se plantean los objetivos y las premisas para establecer el sistema de vigilancia, así como la caracterización de la comunidad basados en los elementos fundamentales para un sistema de vigilancia. Se pretende evaluar costo y calidad de la atención de la salud bucal para lograr el aprovechamiento eficiente de los recursos. Se realizarán investigaciones r...

Computer codes for ventilation in nuclear facilities

International Nuclear Information System (INIS)

Mulcey, P.

1987-01-01

In this paper the authors present some computer codes, developed in the last years, for ventilation and radioprotection. These codes are used for safety analysis in the conception, exploitation and dismantlement of nuclear facilities. The authors present particularly: DACC1 code used for aerosol deposit in sampling circuit of radiation monitors; PIAF code used for modelization of complex ventilation system; CLIMAT 6 code used for optimization of air conditioning system [fr

MELCOR computer code manuals

Energy Technology Data Exchange (ETDEWEB)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L. [Sandia National Labs., Albuquerque, NM (United States); Hodge, S.A.; Hyman, C.R.; Sanders, R.L. [Oak Ridge National Lab., TN (United States)

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR`s phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package.

MELCOR computer code manuals

International Nuclear Information System (INIS)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the U.S. Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

Users guide for NRC145-2 accident assessment computer code

International Nuclear Information System (INIS)

Pendergast, M.M.

1982-08-01

An accident assessment computer code has been developed for use at the Savannah River Plant. This computer code is based upon NRC Regulatory Guide 1.145 which provides guidence for accident assessements for power reactors. The code contains many options so that the user may utilize the code for many different assessments. For example the code can be used for non-nuclear assessments such as Sulpher Dioxide which may be required by the EPA. A discription of the code is contained in DP-1646. This document is a compilation of step-by-step instructions on how to use the code on the SRP IBM 3308 computer. This document consists of a number of tables which contain copies of computer listings. Some of the computer listings are copies of input; other listings give examples of computer output

Quantum computation with Turaev-Viro codes

International Nuclear Information System (INIS)

Koenig, Robert; Kuperberg, Greg; Reichardt, Ben W.

2010-01-01

For a 3-manifold with triangulated boundary, the Turaev-Viro topological invariant can be interpreted as a quantum error-correcting code. The code has local stabilizers, identified by Levin and Wen, on a qudit lattice. Kitaev's toric code arises as a special case. The toric code corresponds to an abelian anyon model, and therefore requires out-of-code operations to obtain universal quantum computation. In contrast, for many categories, such as the Fibonacci category, the Turaev-Viro code realizes a non-abelian anyon model. A universal set of fault-tolerant operations can be implemented by deforming the code with local gates, in order to implement anyon braiding. We identify the anyons in the code space, and present schemes for initialization, computation and measurement. This provides a family of constructions for fault-tolerant quantum computation that are closely related to topological quantum computation, but for which the fault tolerance is implemented in software rather than coming from a physical medium.

Higiene bucal: su repercusión en pacientes con tratamientos ortodóncicos

Directory of Open Access Journals (Sweden)

José A. Pacho Saavedra

2007-03-01

Full Text Available El éxito de los tratamientos ortodóncicos aplicados en la adolescencia radica en mantener una higiene bucal buena, la cual favorece un buen funcionamiento y evita la aparición de complicaciones en los pacientes, asociado con un correcto cepillado de los dientes y de los aparatos ortodóncicos, lo que es un elemento esencial e importante para un tratamiento exitoso, unido al mantenimiento saludable de las encías, prevención de las caries y peridontitis. Se realizó un estudio descriptivo en 50 pacientes de uno u otro sexo y raza, con edades comprendidas entre 12-16 años, procedentes de la Consulta de Ortodoncia de la Clínica Estomatológica H y 21, en el período de marzo-agosto del 2006, los cuales reciben tratamiento ortodóncico, con el objetivo de determinar la higiene bucal durante el tratamiento. Predominó el sexo masculino y el grupo de 12-14 años. Se observó que el 92 % de los pacientes estudiados se categorizó con índice de higiene bucal simplificado bueno y solo el 8 % con un índice de higiene bucal simplificado regular. Finalmente el índice de higiene bucal simplificado del colectivo fue bueno. Se recomienda incrementar y fomentar aún más el mantenimiento de la higiene bucal, para obtener un buen éxito durante el tratamiento ortodóncico y por lo tanto, que el paciente pueda disfrutar de una bonita sonrisa sin afectaciones psicológica.

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)

Caso severo de manifestaciones bucales de la hiperplasia epitelial focal

Directory of Open Access Journals (Sweden)

Jonathan Harris Ricardo

2012-01-01

Full Text Available La hiperplasia epitelial focal, conocida también como enfermedad de Heck, es una patología benigna que se caracteriza por la presencia de múltiples pápulas en la mucosa de la cavidad bucal; es producida por los subtipos 13 y 32 del virus del papiloma humano, aunque también se le relaciona con factores genéticos, inmunosupresión e higiene bucal deficiente pero con poco sustento científico; afecta principalmente a niños y adolescentes. Se reporta caso clínico de paciente femenina de 7 años de edad, remitida al servicio de Estomatología y Cirugía Oral de la Corporación Universitaria Rafael Núñez por presentar múltiples pápulas en mucosa bucal, de tamaño variable, asintomáticas, 8 meses de evolución, relacionadas clínicas e histológicamente con hiperplasia epitelial focal.

FRAP-T1: a computer code for the transient analysis of oxide fuel rods

International Nuclear Information System (INIS)

Dearien, J.A.; Miller, R.L.; Hobbins, R.R.; Siefken, L.J.; Baston, V.F.; Coleman, D.R.

1977-02-01

FRAP-T is a FORTRAN IV computer code which can be used to solve for the transient response of a light water reactor (LWR) fuel rod during accident transients such as loss-of-coolant accident (LOCA) or a power-cooling-mismatch (PCM). The coupled effects of mechanical, thermal, internal gas, and material property response on the behavior of the fuel rod are considered. FRAP-T is a modular code with each major computational model isolated within the code and coupled to the main code by subroutine calls and data transfer through argument lists. FRAP-T is coupled to a materials properties subcode (MATPRO) which is used to provide gas, fuel, and cladding properties to the FRAP-T computational subcodes. No material properties need be supplied by the code user. The needed water properties are stored in tables built into the code. Critical heat flux (CHF) and heat transfer correlations for a wide range of coolant conditions are contained in modular subroutines. FRAP-T has been evaluated by making extensive comparisons between predictions of the code and experimental data. Comparison of predicted and experimental results are presented for a range of FRAP-T calculated parameters. The code is presently programmed and running on an IBM-360/75 and a CDC 7600 computer

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

International Nuclear Information System (INIS)

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

1987-01-01

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

A study on the nuclear computer code maintenance and management system

International Nuclear Information System (INIS)

Kim, Yeon Seung; Huh, Young Hwan; Lee, Jong Bok; Choi, Young Gil; Suh, Soong Hyok; Kang, Byong Heon; Kim, Hee Kyung; Kim, Ko Ryeo; Park, Soo Jin

1990-12-01

According to current software development and quality assurance trends. It is necessary to develop computer code management system for nuclear programs. For this reason, the project started in 1987. Main objectives of the project are to establish a nuclear computer code management system, to secure software reliability, and to develop nuclear computer code packages. Contents of performing the project in this year were to operate and maintain computer code information system of KAERI computer codes, to develop application tool, AUTO-i, for solving the 1st and 2nd moments of inertia on polygon or circle, and to research nuclear computer code conversion between different machines. For better supporting the nuclear code availability and reliability, assistance from users who are using codes is required. Lastly, for easy reference about the codes information, we presented list of code names and information on the codes which were introduced or developed during this year. (Author)

BRT-1 code for IBM 370/135

International Nuclear Information System (INIS)

Preda, I.

1976-01-01

BRT-1 is a transport code to obtain the thermal neutrons spectrum, point dependent, in one reactor cell. The code BRT-1 described in this paper, is the code BRT-1, written in FORTRAN IV language for the computer UNIVAC 1108 with CSCX operating system, converted for the computer IBM 370/135 disk operating system. (author)

Validation of ASTEC v1.0 computer code against FPT2 test

International Nuclear Information System (INIS)

Mladenov, I.; Tusheva, P.; Kalchev, B.; Dimov, D.; Ivanov, I.

2005-01-01

The aim of the work is by various nodalization schemes of the model to investigate the ASTEC v1.0 computer code sensitivity and to validate the code against PHEBUS - FPT2 experiment. This code is used for severe accident analysis. The aim corresponds to the main technical objective of the experiment which is to contribute to the validation of models and computer codes to be used for the calculation of the source term in case of a severe accident in a Light Water Reactor. The objective's scope of the FPT2 is large - separately for the bundle, the experimental circuit and the containment. Additional objectives are to characterize aerosol sizing and deposition processes, and also potential FP poisoning effects on hydrogen recombiner coupons exposed to containment atmospheric conditions representative of a LWR severe accident. The analyses of the results of the performed calculations show a good accordance with the reference case calculations, and then with the experimental data. Some differences in the calculations for the thermal behavior appear locally during the oxidation phase and the heat-up phase. There is very good confirmation regarding the volatile and semi-volatile fission products release from the fuel pellets. Important for analysis of the process is the final axial distribution of the mass of fuel relocation obtained at the end of the calculation

MELCOR computer code manuals: Primer and user's guides, Version 1.8.3 September 1994. Volume 1

International Nuclear Information System (INIS)

Summers, R.M.; Cole, R.K. Jr.; Smith, R.C.; Stuart, D.S.; Thompson, S.L.; Hodge, S.A.; Hyman, C.R.; Sanders, R.L.

1995-03-01

MELCOR is a fully integrated, engineering-level computer code that models the progression of severe accidents in light water reactor nuclear power plants. MELCOR is being developed at Sandia National Laboratories for the US Nuclear Regulatory Commission as a second-generation plant risk assessment tool and the successor to the Source Term Code Package. A broad spectrum of severe accident phenomena in both boiling and pressurized water reactors is treated in MELCOR in a unified framework. These include: thermal-hydraulic response in the reactor coolant system, reactor cavity, containment, and confinement buildings; core heatup, degradation, and relocation; core-concrete attack; hydrogen production, transport, and combustion; fission product release and transport; and the impact of engineered safety features on thermal-hydraulic and radionuclide behavior. Current uses of MELCOR include estimation of severe accident source terms and their sensitivities and uncertainties in a variety of applications. This publication of the MELCOR computer code manuals corresponds to MELCOR 1.8.3, released to users in August, 1994. Volume 1 contains a primer that describes MELCOR's phenomenological scope, organization (by package), and documentation. The remainder of Volume 1 contains the MELCOR Users' Guides, which provide the input instructions and guidelines for each package. Volume 2 contains the MELCOR Reference Manuals, which describe the phenomenological models that have been implemented in each package

Comparative severe accident analysis of WWER 1000/B 320 LOCA DN100 computed by computer codes ASTEC V1.1 and SCDAP/RELAP5

International Nuclear Information System (INIS)

Kalchev, B.; Dimov, D.; Tusheva, P.; Mladenov, I.

2005-01-01

This paper presents the modelling approach for LOCA 100 mm sequence for WWER 1000-B 320 type of reactor with the integral ASTEC computer code and SCDAP/RELAP5 computer code. As a basic input deck the reference input file for Balakovo NPP from the released ASTEC CD has been applied. As a first part of the calculations for the SBLOCA sequence the ASTEC v1.1 modules CESAR, DIVA and CPA have been activated in a coupled mode. For SCDAP/RELAP5 calculation input deck for WWER 1000-B 320 has been applied which meant to be closer to the initial boundary conditions applied for ASTEC WWER 1000 input deck. A SBLOCA 100 mm comparison between ASTEC v1.1 and SCADAP/RELAP5 has been presented. ASTEC predicts vessel failure at 15620 s. ASTEC and SCDAP/RELAP5 give close but not similar results - this could be observed on the trends. The comparison of 100 mm-break shows that SCDAP/RELAP5 predicts clear phenomenological changes in primary pressure evolution and molten pool formation. Similar hydrogen production mass for both codes around 5000 s is detected

Capacidade funcional, função manual, higiene bucal e sua relação com odontogeriatria

OpenAIRE

Rafael Gustavo Dal Moro

2003-01-01

O crescimento da população idosa é um fenômeno mundial. Os profissionais da Odontologia enfrentarão um novo desafio, uma vez que a condição de saúde bucal dos idosos é precária. Investigar os fatores relacionados à saúde bucal permitirá intervir no processo saúde-doença de forma mais eficaz. A higiene bucal é um fator local primordial na saúde bucal de todos os indivíduos. Em virtude do processo de envelhecimento ser agravado por certas condições predisponentes, os idosos tendem a perder a ca...

Computer codes for designing proton linear accelerators

International Nuclear Information System (INIS)

Kato, Takao

1992-01-01

Computer codes for designing proton linear accelerators are discussed from the viewpoint of not only designing but also construction and operation of the linac. The codes are divided into three categories according to their purposes: 1) design code, 2) generation and simulation code, and 3) electric and magnetic fields calculation code. The role of each category is discussed on the basis of experience at KEK (the design of the 40-MeV proton linac and its construction and operation, and the design of the 1-GeV proton linac). We introduce our recent work relevant to three-dimensional calculation and supercomputer calculation: 1) tuning of MAFIA (three-dimensional electric and magnetic fields calculation code) for supercomputer, 2) examples of three-dimensional calculation of accelerating structures by MAFIA, 3) development of a beam transport code including space charge effects. (author)

The computer code EURDYN - 1 M (release 1) for transient dynamic fluid-structure interaction. Pt.1: governing equations and finite element modelling

International Nuclear Information System (INIS)

Donea, J.; Fasoli-Stella, P.; Giuliani, S.; Halleux, J.P.; Jones, A.V.

1980-01-01

This report describes the governing equations and the finite element modelling used in the computer code EURDYN - 1 M. The code is a non-linear transient dynamic program for the analysis of coupled fluid-structure systems; It is designed for safety studies on LMFBR components (primary containment and fuel subassemblies)

Prevalencia de Candidiasis Bucal en pacientes VIH/SIDA: Estudio retrospectivo

OpenAIRE

Tovar, V; Albornoz, E; Guerra, M; Lazarde, J

2004-01-01

El objetivo de este trabajo fue conocer la prevalencia de Candidiasis Bucal en un grupo de pacientes VIH/SIDA que acudieron al Servicio de Atención a Pacientes con Enfermedades Infectocontagiosas (SAPEI) de la Facultad de Odontología de la UCV. Se estudiaron 509 pacientes de los cuales 151 pacientes al examen clínico presentaron lesiones bucales de Candidiasis, de estos, 119 eran hombres y 32 mujeres, con un rango de edades entre 19 y 64 años y un promedio de 38,12 años. Los pacientes fueron ...

The HARWELL version of the computer code E-DEP-1

International Nuclear Information System (INIS)

Matthews, M.D.

1983-03-01

This document describes the modified HARWELL version of the computer program EDEP-1 which has been in use on the IBM Central Computer for some years. The program can be used to calculate heavy ion ranges and/or profiles of energy deposited into nuclear processes for a wide variety of ion/target combinations. The initial setting up of this program on the IBM Central Computer has been described in an earlier report. A second report was later issued to bring the first report up to date following changes to this code required to suit the needs of workers at HARWELL. This later report described in particular the provision of new electronic stopping powers and an alternative method for calculating the energy straggle of beam ions with depth in a target. This new report describes further extensions to the electronic stopping powers available in the HARWELL version of this program and, for the first time, gives details of alternative nuclear stopping powers now available. This new document is intended as a reference manual for the use of the HARWELL version of EDEP-1. In this respect this document should be the final report on the status of this program. (author)

Computer code conversion using HISTORIAN

International Nuclear Information System (INIS)

Matsumoto, Kiyoshi; Kumakura, Toshimasa.

1990-09-01

When a computer program written for a computer A is converted for a computer B, in general, the A version source program is rewritten for B version. However, in this way of program conversion, the following inconvenient problems arise. 1) The original statements to be rewritten for B version are lost. 2) If the original statements of the A version rewritten for B version would remain as comment lines, the B version source program becomes quite large. 3) When update directives of the program are mailed from the organization which developed the program or when some modifications are needed for the program, it is difficult to point out the part to be updated or modified in the B version source program. To solve these problems, the conversion method using the general-purpose software management aid system, HISTORIAN, has been introduced. This conversion method makes a large computer code a easy-to-use program for use to update, modify or improve after the conversion. This report describes the planning and procedures of the conversion method and the MELPROG-PWR/MOD1 code conversion from the CRAY version to the JAERI FACOM version as an example. This report would provide useful information for those who develop or introduce large programs. (author)

Percepciones en salud bucal de los niños y niñas

Directory of Open Access Journals (Sweden)

Catalina González-Penagos, Colombia.

2015-07-01

Full Text Available (analítico: Identificamos las necesidades de salud bucal de los niños y niñas de 2 a 5 años del programa Buen Comienzo-Fantasías de las Américas, desde la percepción de las agentes educativas en la ciudad de Medellín, en el año 2013. Realizamos un estudio cualitativo, con enfoque histórico hermenéutico; la población de estudio correspondió a 65 agentes educativas. Los resultados preliminares reflejan necesidades relacionadas con el acceso y oportunidad de atención odontológica, la deficiencia en las acciones de promoción de la salud y prevención de las enfermedades prevalentes en salud bucal, el desconocimiento y la falta de motivación de los hábitos de higiene bucal, su importancia en la prevención de las patologías bucales y su implicación con el crecimiento y desarrollo, y con la salud general de los menores y las menores.

Influencia de la salud bucal durante el embarazo en la salud del futuro bebé

OpenAIRE

Díaz Valdés, Liuba; Valle Lizama, Raúl Luis

2015-01-01

Fundamento: El embarazo se relaciona con una mayor incidencia de caries y gingivitis. Objetivo: Profundizar en el conocimiento sobre la influencia de estas afecciones bucales en la salud del futuro bebé. Conclusiones: El embarazo genera adaptaciones en la fisiología femenina las cuales pueden repercutir en la salud bucal de la gestante. Las afecciones bucales más frecuentes son la caries dental y la gingivitis, estas si no son tratadas a tiempo pueden afectar la salud del futuro bebé. Back...

Use of computer codes for system reliability analysis

International Nuclear Information System (INIS)

Sabek, M.; Gaafar, M.; Poucet, A.

1988-01-01

This paper gives a collective summary of the studies performed at the JRC, ISPRA on the use of computer codes for complex systems analysis. The computer codes dealt with are: CAFTS-SALP software package, FRANTIC, FTAP, computer code package RALLY, and BOUNDS codes. Two reference study cases were executed by each code. The results obtained logic/probabilistic analysis as well as computation time are compared

Enfermedad injerto contra huesped: sus manifestaciones bucales

Directory of Open Access Journals (Sweden)

Claudia Marcela Hernández Cancino

Full Text Available La enfermedad injerto contra huésped es la principal complicación que sufren los pacientes que han recibido trasplante alogénico. Se produce como consecuencia de una reacción inflamatoria exagerada mediada por los linfocitos del donante y estimulada por aquellos tejidos que han sido lesionados por la enfermedad de base, por las infecciones previas o por el tratamiento de acondicionamiento. El diagnóstico es clínico e histopatológico. Los pacientes presentan rash maculopapular pruriginoso y doloroso que puede extenderse por toda la superficie corporal, fiebre, vómito, náuseas, diarrea y anorexia. En la mucosa bucal se observan erosiones ulceradas, extremamente dolorosas y pueden ser la primera o la única manifestación detectable clínicamente de esta enfermedad. El objetivo es presentar un caso de enfermedad de injerto contra huésped. Se trata de una mujer de 54 años de edad con linfoma no-Hodgking, que recibió tratamiento con quimioterapia, radioterapia y trasplante de células madre hematopoyéticas en el 2009. Tres meses después, presentó lesiones en la piel diagnosticadas como enfermedad injerto contra huésped y tratadas con corticoesteroides, a los seis meses fue remitida al odontólogo porque se quejaba de ardor en la boca, xerostomía y dificultad para masticar, tenía úlceras en la mucosa bucal y en la lengua. En la ocasión recibió tratamiento con corticoesteroides, clorhexidina, orientaciones de higiene bucal y controles clínicos permanentes. Aunque existen protocolos para la prevención y el tratamiento de la enfermedad injerto contra el huésped, su frecuencia ha aumentado en los últimos años debido al incremento en el número de trasplantes. Por esta razón, es fundamental que el odontólogo forme parte del grupo multidisciplinario que asiste al paciente y que esté familiarizado con los signos y síntomas de esta enfermedad en la mucosa bucal, pues las manifestaciones clínicas pueden ser las únicas para

Heat Transfer treatment in computer codes for safety analysis

International Nuclear Information System (INIS)

Jerele, A.; Gregoric, M.

1984-01-01

Increased number of operating nuclear power plants has stressed importance of nuclear safety evaluation. For this reason, accordingly to regulatory commission request, safety analyses with computer codes are preformed. In this paper part of this thermohydraulic models dealing with wall-to-fluid heat transfer correlations in computer codes TRAC=PF1, RELAP4/MOD5, RELAP5/MOD1 and COBRA-IV is discussed. (author)

Translation of ARAC computer codes

International Nuclear Information System (INIS)

Takahashi, Kunio; Chino, Masamichi; Honma, Toshimitsu; Ishikawa, Hirohiko; Kai, Michiaki; Imai, Kazuhiko; Asai, Kiyoshi

1982-05-01

In 1981 we have translated the famous MATHEW, ADPIC and their auxiliary computer codes for CDC 7600 computer version to FACOM M-200's. The codes consist of a part of the Atmospheric Release Advisory Capability (ARAC) system of Lawrence Livermore National Laboratory (LLNL). The MATHEW is a code for three-dimensional wind field analysis. Using observed data, it calculates the mass-consistent wind field of grid cells by a variational method. The ADPIC is a code for three-dimensional concentration prediction of gases and particulates released to the atmosphere. It calculates concentrations in grid cells by the particle-in-cell method. They are written in LLLTRAN, i.e., LLNL Fortran language and are implemented on the CDC 7600 computers of LLNL. In this report, i) the computational methods of the MATHEW/ADPIC and their auxiliary codes, ii) comparisons of the calculated results with our JAERI particle-in-cell, and gaussian plume models, iii) translation procedures from the CDC version to FACOM M-200's, are described. Under the permission of LLNL G-Division, this report is published to keep the track of the translation procedures and to serve our JAERI researchers for comparisons and references of their works. (author)

Computer code development plant for SMART design

International Nuclear Information System (INIS)

Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H.

1999-03-01

In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

Computer code development plant for SMART design

Energy Technology Data Exchange (ETDEWEB)

Bae, Kyoo Hwan; Choi, S.; Cho, B.H.; Kim, K.K.; Lee, J.C.; Kim, J.P.; Kim, J.H.; Chung, M.; Kang, D.J.; Chang, M.H

1999-03-01

In accordance with the localization plan for the nuclear reactor design driven since the middle of 1980s, various computer codes have been transferred into the korea nuclear industry through the technical transfer program from the worldwide major pressurized water reactor supplier or through the international code development program. These computer codes have been successfully utilized in reactor and reload core design works. As the results, design- related technologies have been satisfactorily accumulated. However, the activities for the native code development activities to substitute the some important computer codes of which usages are limited by the original technique owners have been carried out rather poorly. Thus, it is most preferentially required to secure the native techniques on the computer code package and analysis methodology in order to establish the capability required for the independent design of our own model of reactor. Moreover, differently from the large capacity loop-type commercial reactors, SMART (SYSTEM-integrated Modular Advanced ReacTor) design adopts a single reactor pressure vessel containing the major primary components and has peculiar design characteristics such as self-controlled gas pressurizer, helical steam generator, passive residual heat removal system, etc. Considering those peculiar design characteristics for SMART, part of design can be performed with the computer codes used for the loop-type commercial reactor design. However, most of those computer codes are not directly applicable to the design of an integral reactor such as SMART. Thus, they should be modified to deal with the peculiar design characteristics of SMART. In addition to the modification efforts, various codes should be developed in several design area. Furthermore, modified or newly developed codes should be verified their reliability through the benchmarking or the test for the object design. Thus, it is necessary to proceed the design according to the

Reflexões sobre a saúde bucal no Brasil

Directory of Open Access Journals (Sweden)

Anya Pimentel Gomes Fernandes Vieira Meyer

2013-12-01

Full Text Available No último século, numerosos avanços em pesquisas e tecnologias biomédicas na área odontológica foram responsáveis por melhorias na saúde e no bem-estar das populações(1. Entretanto, apesar das grandes realizações no âmbito da saúde bucal, muitos problemas ainda permanecem, como a cárie dental, a mais comum das doenças bucais. A prevalência da cárie dentária apresentou uma tendência de declínio nas três últimas décadas do século XX e no início do século XXI, especialmente nos países desenvolvidos, contudo, ainda é considerada uma importante questão de saúde pública mundial, afetando de 60% a 90% das crianças em idade escolar, além da vasta maioria dos adultos(2-4. No levantamento epidemiológico SB Brasil 2010(5, foram observadas melhoras na condição bucal dos brasileiros, porém, ainda é alta a prevalência de cárie. Entre os adolescentes de 15 a 19 anos, por exemplo, a média de dentes afetados foi de 4,25 mais que o dobro do número médio encontrado aos 12 anos. Entre os idosos de 65a 74 anos, o número de dentes cariados, perdidos e obturados (CPO praticamente não se alterou, ficando em 27,5 em 2010, enquanto, em 2003, a média era de 27,8. Em termos internacionais, de acordo com o Ministério da Saúde brasileiro(5,um estudo realizado pela Organização Mundial da Saúde (OMS em 2004 indicou que, nos dados de 188 países, o valor médio do CPO aos 12 anos foi de 1,6, sendonas Américas a média de 2,8, enquanto na Europa ficou em 1,6. Na América do Sul,somente a Venezuela apresentou média de CPO aos 12 anos semelhante à brasileira(2,1. Nos demais países, as médias apresentaram-se mais altas, como na Argentina(3,4, Bolívia (4,7, Colômbia (2,3, Paraguai (2,8 e Peru (3,7. Os achados epidemiológicos de 2010 sobre a saúde bucal no Brasil(5mostraram que o país entrou para o grupo daqueles com baixa prevalência de carie aos 12 anos. Embora os resultados nesse quesito tenham sido animadores, a

Caso severo de manifestaciones bucales de la hiperplasia epitelial focal

OpenAIRE

Jonathan Harris Ricardo; Natalia Fortich Mesa

2012-01-01

La hiperplasia epitelial focal, conocida también como enfermedad de Heck, es una patología benigna que se caracteriza por la presencia de múltiples pápulas en la mucosa de la cavidad bucal; es producida por los subtipos 13 y 32 del virus del papiloma humano, aunque también se le relaciona con factores genéticos, inmunosupresión e higiene bucal deficiente pero con poco sustento científico; afecta principalmente a niños y adolescentes. Se reporta caso clínico de paciente femenina de 7 años de e...

GASFLOW-MPI. A scalable computational fluid dynamics code for gases, aerosols and combustion. Vol. 1. Theory and computational model (Revision 1.0)

Energy Technology Data Exchange (ETDEWEB)

Xiao, Jianjun; Travis, Jack; Royl, Peter; Necker, Gottfried; Svishchev, Anatoly; Jordan, Thomas

2016-07-01

Karlsruhe Institute of Technology (KIT) is developing the parallel computational fluid dynamics code GASFLOW-MPI as a best-estimate tool for predicting transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facility buildings. GASFLOW-MPI is a finite-volume code based on proven computational fluid dynamics methodology that solves the compressible Navier-Stokes equations for three-dimensional volumes in Cartesian or cylindrical coordinates.

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

Thermohydraulic analysis of nuclear power plant accidents by computer codes

International Nuclear Information System (INIS)

Petelin, S.; Stritar, A.; Istenic, R.; Gregoric, M.; Jerele, A.; Mavko, B.

1982-01-01

RELAP4/MOD6, BRUCH-D-06, CONTEMPT-LT-28, RELAP5/MOD1 and COBRA-4-1 codes were successful y implemented at the CYBER 172 computer in Ljubljana. Input models of NPP Krsko for the first three codes were prepared. Because of the high computer cost only one analysis of double ended guillotine break of the cold leg of NPP Krsko by RELAP4 code has been done. BRUCH code is easier and cheaper for use. Several analysis have been done. Sensitivity study was performed with CONTEMPT-LT-28 for double ended pump suction break. These codes are intended to be used as a basis for independent safety analyses. (author)

Comportamiento clínico epidemiológico de las lesiones bucales en pacientes VIH/SIDA. Artemisa. Enero-Abril 2015

Directory of Open Access Journals (Sweden)

Arahí Gómez Casañas

2016-02-01

Full Text Available Objetivo: Caracterizar el comportamiento clínico epidemiológico de las lesiones bucales en los pacientes con diagnóstico serológico confirmado de VIH/SIDA, para determinar la prevalencia de lesiones bucales en la población estudiada. Caracterizar la población de estudio según sexo, edad, tiempo de diagnóstico, presencia y tipo de lesiones bucales. Método: Se realizó un estudio observacional, descriptivo, de corte transversal, con los pacientes diagnosticados con VIH/SIDA que acudieron a su consulta de seguimiento del policlínico Tomás Romay, Artemisa en el período de Enero -Abril de 2015, el universo fue de 69 pacientes con diagnóstico confirmado de VIH/SIDA, se tomó una muestra de 25 pacientes que cumplían los criterios de inclusión. Se les realizó un exhaustivo interrogatorio y examen clínico bucal, previo consentimiento informado de los pacientes. Resultados: Del total de pacientes estudiados, el 64% presentó alguna lesión bucal; el 72% de la muestra perteneció al sexo masculino y al grupo de edad de 26 a 35 años; las lesiones bucales predominantes fueron la candidiasis bucal (24.0% seguido del eritema gingival lineal (12.0% ubicándose el mayor número de pacientes con estas lesiones (16%, en el grupo de más de 5 años de diagnóstico. Conclusiones: Se encontró una elevada prevalencia de lesiones bucales en la población objeto de estudio, con predominio del sexo masculino, en el grupo de edad de 26 a 35 años, siendo la candidiasis bucal y el eritema gingival lineal, las dos lesiones más frecuentemente encontradas en la muestra.

Validade do padrão de higiene bucal de crianças aos cinco anos de idade relatado pelas mães

OpenAIRE

Cascaes, Andreia Morales; Peres, Karen Glazer; Peres, Marco Aurélio; Demarco, Flávio Fernando; Santos, Iná; MatijasevichI, Alicia; Barros, Aluísio Jardim Dornellas de

2011-01-01

OBJETIVO: Determinar a validade de perguntas freqüentemente utilizadas em estudos epidemiológicos sobre higiene bucal de crianças e compará-la segundo renda familiar e escolaridade da mãe. MÉTODOS: Foram analisadas 1.122 crianças participantes do sub estudo de saúde bucal de 2009 da Coorte de Nascimentos de Pelotas, RS, 2004. As crianças foram examinadas e suas mães entrevistadas no domicílio. O padrão ouro da condição de higiene bucal foi avaliado por meio do Índice de Higiene Oral Simplific...

Adaptation of HAMMER computer code to CYBER 170/750 computer

International Nuclear Information System (INIS)

Pinheiro, A.M.B.S.; Nair, R.P.K.

1982-01-01

The adaptation of HAMMER computer code to CYBER 170/750 computer is presented. The HAMMER code calculates cell parameters by multigroup transport theory and reactor parameters by few group diffusion theory. The auxiliary programs, the carried out modifications and the use of HAMMER system adapted to CYBER 170/750 computer are described. (M.C.K.) [pt

Parallel computing by Monte Carlo codes MVP/GMVP

International Nuclear Information System (INIS)

Nagaya, Yasunobu; Nakagawa, Masayuki; Mori, Takamasa

2001-01-01

General-purpose Monte Carlo codes MVP/GMVP are well-vectorized and thus enable us to perform high-speed Monte Carlo calculations. In order to achieve more speedups, we parallelized the codes on the different types of parallel computing platforms or by using a standard parallelization library MPI. The platforms used for benchmark calculations are a distributed-memory vector-parallel computer Fujitsu VPP500, a distributed-memory massively parallel computer Intel paragon and a distributed-memory scalar-parallel computer Hitachi SR2201, IBM SP2. As mentioned generally, linear speedup could be obtained for large-scale problems but parallelization efficiency decreased as the batch size per a processing element(PE) was smaller. It was also found that the statistical uncertainty for assembly powers was less than 0.1% by the PWR full-core calculation with more than 10 million histories and it took about 1.5 hours by massively parallel computing. (author)

Prótesis totales y lesiones bucales en adultos mayores institucionalizados

Directory of Open Access Journals (Sweden)

Beatriz García Alpízar

2012-03-01

Full Text Available Fundamento: las prótesis dentales constituyen una alternativa al perderse los dientes, pero no están exentas de provocar daños, que junto a la susceptibilidad de los tejidos, provocada por el envejecimiento e inadecuados estilos de vida, pueden llevar a la aparición de lesiones bucales. Objetivo: describir las características de pacientes portadores de prótesis totales y su relación con las lesiones bucales. Métodos: estudio descriptivo, con 93 ancianos institucionalizados portadores de prótesis total. Se utilizaron las pruebas de chi cuadrado y el riesgo relativo para determinar la asociación entre las variables: edad, sexo, higiene, estado de conservación, tiempo y frecuencia de uso de la prótesis, necesidades de prótesis, tipo de lesión, localización, hábito de fumar, enfermedades sistémicas y medicamentos empleados. Resultados: el 78,5 % de los ancianos presentó lesiones relacionadas con el uso de la prótesis. La estomatitis subprótesis fue la lesión más frecuente. La presencia de lesiones bucales fue significativa en aquellos con 80 años y más (100 %. El 95,8 % tenían prótesis deterioradas, y en la totalidad de ellos, las prótesis tenían 21 años y más de uso. El riesgo de desarrollar lesiones fue 2,98 veces superior en aquellos con una higiene bucal deficiente. El 100 % de los ancianos diabéticos y anémicos presentaron lesiones. Conclusiones: las lesiones bucales estuvieron muy relacionadas con los factores locales: estado de conservación, higiene, tiempo de uso de las prótesis; y con factores generales como: incremento de la edad, enfermedades sistémicas y uso de medicamentos para su tratamiento.

Verification of thermal-hydraulic computer codes against standard problems for WWER reflooding

International Nuclear Information System (INIS)

Alexander D Efanov; Vladimir N Vinogradov; Victor V Sergeev; Oleg A Sudnitsyn

2005-01-01

Full text of publication follows: The computational assessment of reactor core components behavior under accident conditions is impossible without knowledge of the thermal-hydraulic processes occurring in this case. The adequacy of the results obtained using the computer codes to the real processes is verified by carrying out a number of standard problems. In 2000-2003, the fulfillment of three Russian standard problems on WWER core reflooding was arranged using the experiments on full-height electrically heated WWER 37-rod bundle model cooldown in regimes of bottom (SP-1), top (SP-2) and combined (SP-3) reflooding. The representatives from the eight MINATOM's organizations took part in this work, in the course of which the 'blind' and posttest calculations were performed using various versions of the RELAP5, ATHLET, CATHARE, COBRA-TF, TRAP, KORSAR computer codes. The paper presents a brief description of the test facility, test section, test scenarios and conditions as well as the basic results of computational analysis of the experiments. The analysis of the test data revealed a significantly non-one-dimensional nature of cooldown and rewetting of heater rods heated up to a high temperature in a model bundle. This was most pronounced at top and combined reflooding. The verification of the model reflooding computer codes showed that most of computer codes fairly predict the peak rod temperature and the time of bundle cooldown. The exception is provided by the results of calculations with the ATHLET and CATHARE codes. The nature and rate of rewetting front advance in the lower half of the bundle are fairly predicted practically by all computer codes. The disagreement between the calculations and experimental results for the upper half of the bundle is caused by the difficulties of computational simulation of multidimensional effects by 1-D computer codes. In this regard, a quasi-two-dimensional computer code COBRA-TF offers certain advantages. Overall, the closest

O acesso a informacao sobre higiene bucal e as perdas dentarias por carie entre adultos

Directory of Open Access Journals (Sweden)

Desiree Sant'Ana Haikal

2014-01-01

Full Text Available Objetivou-se testar a associação entre perdas dentárias por cárie (PDC e variáveis relativas ao acesso a informações em saúde bucal. Foram analisados dados de 780 adultos (35-44 anos participantes de um estudo epidemiológico. A variável dependente foi o total de PDC e as independentes foram reunidas em blocos de variáveis: demográficas e socioeconômicas; utilização dos serviços odontológicos; acesso a informações em saúde bucal (informações sobre como evitar problemas bucais, sobre higiene bucal e sobre dieta e; comportamentais. Conduziu-se regressão linear múltipla hierarquizada. O número médio de PDC foi de 7,03 (EP= 0,31 e 83% dos adultos haviam perdido algum dente por cárie. As PDC foram maiores entre os mais velhos, os com menor escolaridade, as mulheres, os que raramente ou nunca receberam informações sobre higiene bucal, os que escovavam os dentes uma vez ou menos ao dia e entre os que não usavam fio dental. Adultos que raramente/nunca receberam informações dos serviços odontológicos sobre higiene bucal perderam 2,15 dentes a mais por cárie que aqueles que sempre/frequentemente receberam tais informações (p = 0,000. Assim, sugere-se que a garantia do acesso à informação deva ser incentivada a fim de contribuir com maior equidade em saúde bucal.

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

APC: A new code for Atmospheric Polarization Computations

International Nuclear Information System (INIS)

Korkin, Sergey V.; Lyapustin, Alexei I.; Rozanov, Vladimir V.

2013-01-01

A new polarized radiative transfer code Atmospheric Polarization Computations (APC) is described. The code is based on separation of the diffuse light field into anisotropic and smooth (regular) parts. The anisotropic part is computed analytically. The smooth regular part is computed numerically using the discrete ordinates method. Vertical stratification of the atmosphere, common types of bidirectional surface reflection and scattering by spherical particles or spheroids are included. A particular consideration is given to computation of the bidirectional polarization distribution function (BPDF) of the waved ocean surface. -- Highlights: •A new code, APC, has been developed. •The code was validated against well-known codes. •The BPDF for an arbitrary Mueller matrix is computed

The RETRAN-03 computer code

International Nuclear Information System (INIS)

Paulsen, M.P.; McFadden, J.H.; Peterson, C.E.; McClure, J.A.; Gose, G.C.; Jensen, P.J.

1991-01-01

The RETRAN-03 code development effort is designed to overcome the major theoretical and practical limitations associated with the RETRAN-02 computer code. The major objectives of the development program are to extend the range of analyses that can be performed with RETRAN, to make the code more dependable and faster running, and to have a more transportable code. The first two objectives are accomplished by developing new models and adding other models to the RETRAN-02 base code. The major model additions for RETRAN-03 are as follows: implicit solution methods for the steady-state and transient forms of the field equations; additional options for the velocity difference equation; a new steady-state initialization option for computer low-power steam generator initial conditions; models for nonequilibrium thermodynamic conditions; and several special-purpose models. The source code and the environmental library for RETRAN-03 are written in standard FORTRAN 77, which allows the last objective to be fulfilled. Some models in RETRAN-02 have been deleted in RETRAN-03. In this paper the changes between RETRAN-02 and RETRAN-03 are reviewed

Computation of the bounce-average code

International Nuclear Information System (INIS)

Cutler, T.A.; Pearlstein, L.D.; Rensink, M.E.

1977-01-01

The bounce-average computer code simulates the two-dimensional velocity transport of ions in a mirror machine. The code evaluates and bounce-averages the collision operator and sources along the field line. A self-consistent equilibrium magnetic field is also computed using the long-thin approximation. Optionally included are terms that maintain μ, J invariance as the magnetic field changes in time. The assumptions and analysis that form the foundation of the bounce-average code are described. When references can be cited, the required results are merely stated and explained briefly. A listing of the code is appended

Implatation of MC2 computer code

International Nuclear Information System (INIS)

Seehusen, J.; Nair, R.P.K.; Becceneri, J.C.

1981-01-01

The implantation of MC2 computer code in the CDC system is presented. The MC2 computer code calculates multigroup cross sections for tipical compositions of fast reactors. The multigroup constants are calculated using solutions of PI or BI approximations for determined buckling value as weighting function. (M.C.K.) [pt

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

Use of computer codes for system reliability analysis

International Nuclear Information System (INIS)

Sabek, M.; Gaafar, M.; Poucet, A.

1989-01-01

This paper gives a summary of studies performed at the JRC, ISPRA on the use of computer codes for complex systems analysis. The computer codes dealt with are: CAFTS-SALP software package, FRACTIC, FTAP, computer code package RALLY, and BOUNDS. Two reference case studies were executed by each code. The probabilistic results obtained, as well as the computation times are compared. The two cases studied are the auxiliary feedwater system of a 1300 MW PWR reactor and the emergency electrical power supply system. (author)

Use of computer codes for system reliability analysis

Energy Technology Data Exchange (ETDEWEB)

Sabek, M.; Gaafar, M. (Nuclear Regulatory and Safety Centre, Atomic Energy Authority, Cairo (Egypt)); Poucet, A. (Commission of the European Communities, Ispra (Italy). Joint Research Centre)

1989-01-01

This paper gives a summary of studies performed at the JRC, ISPRA on the use of computer codes for complex systems analysis. The computer codes dealt with are: CAFTS-SALP software package, FRACTIC, FTAP, computer code package RALLY, and BOUNDS. Two reference case studies were executed by each code. The probabilistic results obtained, as well as the computation times are compared. The two cases studied are the auxiliary feedwater system of a 1300 MW PWR reactor and the emergency electrical power supply system. (author).

El uso del piercing en la cavidad bucal de adolescentes

Directory of Open Access Journals (Sweden)

Mercedes Haces Acosta

2014-04-01

Full Text Available Introducción: el uso del piercing intraoral en los adolescentes constituye una amenaza para la salud bucal. Objetivo: caracterizar el uso del piercing en la cavidad bucal de los adolescentes desde el punto de vista clínico y epidemiológico. Material y método: se realizó un estudio descriptivo transversal en el policlínico Dr. "Modesto Gómez Rubio" del municipio San Juan y Martínez, Pinar del Río, en el período comprendido de septiembre del 2011 a enero del 2013. El universo estuvo conformado por 400 adolescentes que acudieron al servicio del policlínico de los cuales 250 constituyeron la muestra, seleccionada a través del método aleatorio simple. Se les realizó el examen bucal, como medida de resumen se utilizaron el número absoluto y el porcentaje. Resultados: se pudo constatar que de 250 adolescentes examinados 34 presentaban perforaciones intraorales para un 13,6%, de ellos 24 son masculinos para un 70,59% y 10 femeninas representando el 29,41%, la edad de mayor uso de 15 y 18 años con 31 para un 21,85, los efectos nocivos de mayor frecuencia la gingivitis crónica con el 52,94% , seguidas por las fracturas dentarias con el 47,06%, el 97% respondieron que su motivación era la moda. Conclusiones: el uso del piercing en la cavidad bucal de los adolescentes estudiados se caracteriza por manifestarse con mayor frecuencia en las edades entre 15 y 18 años, con predominio del sexo masculino y el efecto nocivo más frecuente la enfermedad gingivitis crónica, seguidas por las fracturas dentarias, motivación la moda.

O uso do protetor bucal nas artes marciais: consciência e atitude

Directory of Open Access Journals (Sweden)

Camilla Cristina Lira Di Leone

2014-12-01

Full Text Available Introdução: O uso de protetores bucais durante a prática de esportes de contato é de fundamental importância como medida preventiva dos traumatismos orofaciais. Objetivo: Realizar um levantamento quanto a utilização do protetor bucal entre praticantes de artes marciais, assim como verificar qual é a percepção que tais esportistas têm sobre sua importância e função. Métodos: Realizou-se uma pesquisa descritiva e transversal, de caráter investigativo, composta por 231 praticantes de três diferentes modalidades de artes marciais: Jiu-jítsu, Tae kwon do e Muay Thai, nas cidades de Nova Friburgo-RJ e Macaé-RJ, Brasil, por meio de um questionário estruturado. Os dados foram tabulados no programa estatístico SPSS 16.0. Foi realizada a frequência, sendo aplicado, ainda, o teste qui-quadrado (p<0,05, para estabelecer relação entre variáveis de interesse. Resultados: Os dados indicaram que 60,6% dos entrevistados nunca receberam informações sobre o traumatismo orofacial durante a prática esportiva e que 46,3% dos esportistas já sofreram algum tipo de traumatismo orofacial. A maioria dos atletas (93,9% considera importante o uso do protetor bucal, porém este dado é desproporcional ao percentual de usuários do dispositivo: 78,7% no Muay Thai, 60,9% no Jiu-jítsu e 47,5% no Tae kwon do (p< 0,01. Dos protetores bucais existentes no mercado, o mais utilizado é o termoplástico ou tipo II (52,5% em todas as modalidades de lutas avaliadas. O protetor bucal personalizado causou menor percentual de interferência no rendimento durante a prática esportiva quando comparado com os outros tipos de protetores (p<0,07. Conclusão: A maioria dos esportistas reconhece a importância do uso do protetor bucal, apesar de relatar não ter recebido informações sobre traumatismo orofacial durante a prática esportiva; a maioria dos atletas utiliza o protetor bucal termoplástico; há necessidade de se difundir informações sobre as vantagens

Efetividade de website de educação em saúde bucal para adolescentes

Directory of Open Access Journals (Sweden)

priscilla Bittencourt de Almeida figueiredo

2014-09-01

Full Text Available RESUMO Objetivo: Avaliar a efetividade de um website desenvolvido como ferramenta de educação em saúde bucal para adolescentes. Métodos: Estudo experimental realizado no município de Belém-PA, no período entre agosto e novembro/2012. A amostra foi composta por 160 escolares, na faixa etária de 11 a 15 anos, de escolas pública e particular. Dois grupos foram formados, sendo um grupo experimental com participação em atividade educativa, com diferencial de acesso a um website contendo informações sobre saúde bucal para adolescentes. Os dados foram coletados por meio de dois questionários auto-administrados aos alunos antes e depois da intervenção educativa. Foram verificadas variáveis de conhecimentos e atitudes sobre saúde bucal. A análise dos dados foi a partir do Teste Qui-quadrado para verificar a associação entre as variáveis categóricas e da Análise de Variância (ANOVA um critério e Teste de Tukey para comparação da quantidade de acertos das questões. Resultados: Observou-se que os escolares, de ambos os grupos, após as atividades educativas, obtiveram bom conhecimento acerca das questões sobre cárie e etiologia do câncer bucal, tendo os escolares do grupo experimental apresentado melhor desempenho sobre esses temas. A maioria dos escolares participantes da pesquisa nunca realizou o autoexame bucal e não possuem conhecimento adequado sobre doença periodontal. Conclusão: O método educativo experimental avaliado demonstrou-se parcialmente efetivo na modificação de conhecimentos sobre doença periodontal. Em contrapartida, foi significantemente efetivo sobre a cárie dentária e os métodos de higienização bucal.

Computer codes for RF cavity design

International Nuclear Information System (INIS)

Ko, K.

1992-08-01

In RF cavity design, numerical modeling is assuming an increasingly important role with the help of sophisticated computer codes and powerful yet affordable computers. A description of the cavity codes in use in the accelerator community has been given previously. The present paper will address the latest developments and discuss their applications to cavity toning and matching problems

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.

Certification of version 1.2 of the PORFLO-3 code for the WHC scientific and engineering computational center

International Nuclear Information System (INIS)

Kline, N.W.

1994-01-01

Version 1.2 of the PORFLO-3 Code has migrated from the Hanford Cray computer to workstations in the WHC Scientific and Engineering Computational Center. The workstation-based configuration and acceptance testing are inherited from the CRAY-based configuration. The purpose of this report is to document differences in the new configuration as compared to the parent Cray configuration, and summarize some of the acceptance test results which have shown that the migrated code is functioning correctly in the new environment

As representações da saúde bucal na mídia impressa

Directory of Open Access Journals (Sweden)

Aline Guio Cavaca

2012-12-01

Full Text Available Buscou-se compreender como as informações sobre Saúde Bucal são veiculadas pela mídia impressa no estado do Espírito Santo - Brasil, por meio de uma pesquisa qualitativa, com análise de conteúdo de 66 matérias relacionadas à temática, veiculadas no período de março de 2004 a junho de 2009, nos jornais A Gazeta e A Tribuna.O material empírico originou sete categorias analíticas: responsabilização do indivíduo; realidades extremas; imaginário popular do dentista e do consultório dentário; patologização da halitose; valorização estética; determinantes da saúde bucal; prevenção e hábitos. A abordagem midiática da saúde bucal perpassa uma complexidade de fatores sociais, culturais, políticos, biológicos e econômicos, que destaca a importância de uma comunicação contextualizada com os interesses da sociedade, que seja interativa e dialógica e explore sua potência crítica na educação e promoção da saúde, veiculando, de maneira consciente, o consumismo em Saúde Bucal.

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

Computer codes for RF cavity design

International Nuclear Information System (INIS)

Ko, K.

1992-01-01

In RF cavity design, numerical modeling is assuming an increasingly important role with the help of sophisticated computer codes and powerful yet affordable computers. A description of the cavity codes in use in the accelerator community has been given previously. The present paper will address the latest developments and discuss their applications to cavity tuning and matching problems. (Author) 8 refs., 10 figs

O movimento da Saúde Bucal Coletiva no Brasil

Directory of Open Access Journals (Sweden)

Catharina Leite Matos Soares

Full Text Available Resumo A Saúde Bucal Coletiva (SBC pode designar um fenômeno histórico especifico, distinto das outras “Odontologias Alternativas” e um referencial teórico para as práticas odontológicas em serviços de saúde. Este estudo buscou compreender a permanência das “Odontologias Alternativas” no espaço social de luta pela saúde bucal no Brasil, a partir de posições dos agentes fundadores e precursores, levando em consideração as concepções de SBC, Saúde Coletiva (SC e SUS. Partiu-se da teoria das práticas de Pierre Bourdieu, complementada pelos conceitos de hegemonia e contra-hegemonia em Gramsci. Realizaram-se 12 entrevistas em profundidade, revisão documental e análise da produção científica, além das trajetórias dos agentes e seus capitais em 1980 e 2013. Os resultados indicam que a concepção de SBC e SC como ruptura com as práticas de saúde oriundas às “Odontologias Alternativas” prevaleceu entre aqueles com disposições políticas em defesa da democracia e da Reforma Sanitária. Embora a SBC tenha proposta crítica, permanecem antigas “Odontologias” na produção científica e nas práticas de saúde bucal.

Computer access security code system

Science.gov (United States)

Collins, Earl R., Jr. (Inventor)

1990-01-01

A security code system for controlling access to computer and computer-controlled entry situations comprises a plurality of subsets of alpha-numeric characters disposed in random order in matrices of at least two dimensions forming theoretical rectangles, cubes, etc., such that when access is desired, at least one pair of previously unused character subsets not found in the same row or column of the matrix is chosen at random and transmitted by the computer. The proper response to gain access is transmittal of subsets which complete the rectangle, and/or a parallelepiped whose opposite corners were defined by first groups of code. Once used, subsets are not used again to absolutely defeat unauthorized access by eavesdropping, and the like.

Microgravity computing codes. User's guide

Science.gov (United States)

1982-01-01

Codes used in microgravity experiments to compute fluid parameters and to obtain data graphically are introduced. The computer programs are stored on two diskettes, compatible with the floppy disk drives of the Apple 2. Two versions of both disks are available (DOS-2 and DOS-3). The codes are written in BASIC and are structured as interactive programs. Interaction takes place through the keyboard of any Apple 2-48K standard system with single floppy disk drive. The programs are protected against wrong commands given by the operator. The programs are described step by step in the same order as the instructions displayed on the monitor. Most of these instructions are shown, with samples of computation and of graphics.

HYDRA-II: A hydrothermal analysis computer code: Volume 1, Equations and numerics

International Nuclear Information System (INIS)

McCann, R.A.

1987-04-01

HYDRA-II is a hydrothermal computer code capable of three-dimensional analysis of coupled conduction, convection, and thermal radiation problems. This code is especially appropriate for simulating the steady-state performance of spent fuel storage systems. The code has been evaluated for this application for the US Department of Energy's Commercial Spent Fuel Management Program. HYDRA-II provides a finite difference solution in Cartesian coordinates to the equations governing the conservation of mass, momentum, and energy. A cylindrical coordinate system may also be used to enclose the Cartesian coordinate system. This exterior coordinate system is useful for modeling cylindrical cask bodies. The difference equations for conservation of momentum are enhanced by the incorporation of directional porosities and permeabilities that aid in modeling solid structures whose dimensions may be smaller than the computational mesh. The equation for conservation of energy permits of modeling of orthotropic physical properties and film resistances. Several automated procedures are available to model radiation transfer within enclosures and from fuel rod to fuel rod. The documentation of HYDRA-II is presented in three separate volumes. This volume, Volume I - Equations and Numerics, describes the basic differential equations, illustrates how the difference equations are formulated, and gives the solution procedures employed. Volume II - User's Manual contains code flow charts, discusses the code structure, provides detailed instructions for preparing an input file, and illustrates the operation of the code by means of a model problem. The final volume, Volume III - Verification/Validation Assessments, presents results of numerical simulations of single- and multiassembly storage systems and comparisons with experimental data. 4 refs

High performance computer code for molecular dynamics simulations

International Nuclear Information System (INIS)

Levay, I.; Toekesi, K.

2007-01-01

Complete text of publication follows. Molecular Dynamics (MD) simulation is a widely used technique for modeling complicated physical phenomena. Since 2005 we are developing a MD simulations code for PC computers. The computer code is written in C++ object oriented programming language. The aim of our work is twofold: a) to develop a fast computer code for the study of random walk of guest atoms in Be crystal, b) 3 dimensional (3D) visualization of the particles motion. In this case we mimic the motion of the guest atoms in the crystal (diffusion-type motion), and the motion of atoms in the crystallattice (crystal deformation). Nowadays, it is common to use Graphics Devices in intensive computational problems. There are several ways to use this extreme processing performance, but never before was so easy to programming these devices as now. The CUDA (Compute Unified Device) Architecture introduced by nVidia Corporation in 2007 is a very useful for every processor hungry application. A Unified-architecture GPU include 96-128, or more stream processors, so the raw calculation performance is 576(!) GFLOPS. It is ten times faster, than the fastest dual Core CPU [Fig.1]. Our improved MD simulation software uses this new technology, which speed up our software and the code run 10 times faster in the critical calculation code segment. Although the GPU is a very powerful tool, it has a strongly paralleled structure. It means, that we have to create an algorithm, which works on several processors without deadlock. Our code currently uses 256 threads, shared and constant on-chip memory, instead of global memory, which is 100 times slower than others. It is possible to implement the total algorithm on GPU, therefore we do not need to download and upload the data in every iteration. On behalf of maximal throughput, every thread run with the same instructions

Importancia del Programa de Deteccion Temprana del cancer bucal en Cuba

OpenAIRE

Morales Navarro, Denia; Rodríguez Lay, Liliana; García Jordán, Mariela

2009-01-01

El cáncer es un factor importante de la carga mundial de morbilidad, y lo será cada vez más en los decenios venideros. El aumento global del número de casos de cáncer bucal y la factibilidad de realizar acciones de salud específicas nos motivó a consultar la bibliografía que maneja este tema e indagar sobre los resultados del Programa de Detección del Cáncer Bucal en Cuba. Se realizó una revisión bibliográfica mediante la consulta de bases de datos de los sistemas referativos, como MEDLINE y ...

CONCEPT computer code

International Nuclear Information System (INIS)

Delene, J.

1984-01-01

CONCEPT is a computer code that will provide conceptual capital investment cost estimates for nuclear and coal-fired power plants. The code can develop an estimate for construction at any point in time. Any unit size within the range of about 400 to 1300 MW electric may be selected. Any of 23 reference site locations across the United States and Canada may be selected. PWR, BWR, and coal-fired plants burning high-sulfur and low-sulfur coal can be estimated. Multiple-unit plants can be estimated. Costs due to escalation/inflation and interest during construction are calculated

EL CÍRCULO DE INTERÉS COMO MÉTODO EFECTIVO PARA LA SALUD BUCAL DE LOS ESCOLARES

Directory of Open Access Journals (Sweden)

Kenya Caridad Casanova Sales

2014-06-01

Full Text Available Se realizó una investigación de intervención comunitaria en la Escuela Primaria Carlos Cuquejo, en la localidad de Vázquez, desde octubre de 2012 a mayo de 2014, mediante el círculo de interés “Educación para la salud bucal”, con una muestra de 98 escolares. El objetivo fue desarrollar la educación para la salud bucal. Se tuvo en cuenta el nivel de conocimientos, la higiene, el estado de salud bucal, así como la ingestión o no, de una dieta cariogénica. La metodología contempló encuestas, controles de placa bacteriana, historias clínicas y registros diarios de dieta de los niños. Las temáticas de educación para la salud fueron desarrolladas mediante murales, mensajes para la salud bucal, charlas demostrativas, juegos didácticos, como “Mi boquita sana”; con canciones, poesías, obras de teatro, encuentros de conocimientos, mesa cubana de frutas y vegetales, y selección de escolares con mejor higiene bucal. Al evaluar los resultados iniciales y finales se comprobó la elevación del nivel de conocimientos, de la higiene, el estado de salud bucal y la calidad de la dieta. El círculo de interés promovió la educación para la salud bucal y la disminución de los niños enfermos, lo que constituyó un logro significativo.

A importância da saúde bucal para adolescentes de diferentes estratos sociais do município de Ribeirão Preto La importancia de la salud bucal para los adolescentes de diferentes estratos sociales del municipio de Ribeirão Preto The importance of bucal health for adolescents of different social strata of Ribeirão Preto

Directory of Open Access Journals (Sweden)

Marina Sá Elias

2001-01-01

Full Text Available O objetivo do presente estudo é conhecer a importância da saúde bucal para adolescentes de diferentes estratos sociais, identificando a importância da estética dental, e o cuidado que estes dispensam em relação a sua saúde bucal. O processo metodológico adotado nesta investigação é de natureza qualitativa, utilizando como técnica de coleta de dados a entrevista semi-estruturada. Conhecemos a importância da saúde bucal em vários contextos de suas vidas, como na aparência pessoal, na sexualidade, no emprego, e na saúde geral. Esta investigação permite-nos conhecer as motivações para os adolescentes preservarem sua saúde bucal, o que acreditamos ser muito válido no intuito de desenvolvermos a promoção de saúde através da educação em saúde.El objetivo del presente estudio es conocer la importancia de la salud bucal para los adolescentes de diferentes estratos sociales, identificando la importancia de la estética dental y el cuidado que estos realizan en relación con su salud bucal. El proceso metodológico adoptado en esta investigación es de naturaleza cualitativa, utilizando como técnica de recolección de datos la entrevista semi-estructurada. Conocimos la importancia de la salud bucal en varios contextos de sus vidas, como en la apariencia personal, en la sexualidad, en el empleo y en la salud en general. Esta investigación nos permitió conocer las motivaciones que tienen los adolescentes para preservar su salud bucal, lo cual creemos será muy valioso en desarrollar programas de promoción de la salud a través de la educación en salud.The objective of the present study is to know the importance of buccal health for adolescents of different social strata, identifying the importance of dental aesthetics, and the care that these students take in relation to their buccal health. The methodological process adopted in this investigation is of qualitative nature, using as technique of collection of data the semi

User's manual for the NEFTRAN II computer code

International Nuclear Information System (INIS)

Olague, N.E.; Campbell, J.E.; Leigh, C.D.; Longsine, D.E.

1991-02-01

This document describes the NEFTRAN II (NEtwork Flow and TRANsport in Time-Dependent Velocity Fields) computer code and is intended to provide the reader with sufficient information to use the code. NEFTRAN II was developed as part of a performance assessment methodology for storage of high-level nuclear waste in unsaturated, welded tuff. NEFTRAN II is a successor to the NEFTRAN and NWFT/DVM computer codes and contains several new capabilities. These capabilities include: (1) the ability to input pore velocities directly to the transport model and bypass the network fluid flow model, (2) the ability to transport radionuclides in time-dependent velocity fields, (3) the ability to account for the effect of time-dependent saturation changes on the retardation factor, and (4) the ability to account for time-dependent flow rates through the source regime. In addition to these changes, the input to NEFTRAN II has been modified to be more convenient for the user. This document is divided into four main sections consisting of (1) a description of all the models contained in the code, (2) a description of the program and subprograms in the code, (3) a data input guide and (4) verification and sample problems. Although NEFTRAN II is the fourth generation code, this document is a complete description of the code and reference to past user's manuals should not be necessary. 19 refs., 33 figs., 25 tabs

Manifestaciones clínicas bucales detectadas en pacientes con giardiasis

Directory of Open Access Journals (Sweden)

Juan Carlos Quintana Díaz

1997-12-01

Full Text Available Se realizó un estudio de la posible relación existente entre la giardiasis y la aparición de manifestaciones bucales en un grupo de pacientes mayores de 16 años, a los que se les diagnosticó esta afección mediante el drenaje biliar. Se asevera que la malabsorción producida por este parásito hace que se origine un déficit de vitaminas, proteínas, carbohidratos y grasas, que según varios autores y nosostros, son la causa de las alteraciones bucales encontradas. De los 50 pacientes con giardiasis estudiados, el 46 % correspondió al sexo masculino y el 54 % al femenino, las manifestaciones bucales encontradas fueron: aftas, glositis y queilitis en un total del 52 % de los casos examinados.A study on the possible relationship existing between giardiasis and the appereance of oral manifestations in a group of patients over 16, who were diagnosed this affection by biliary drainage, was conducted. It is affirmed that the malabsorption produced by this parasite provokes a deficit of vitamins, proteins, carbohydrates and fats, that in some authora' opinions and in our own, causes the oral alterations found. Of the 50 patients with giardiasis studied, 46 % were males and 54 % females. The oral manifestations detected in 52 % of the cases examined were: aphthas, glossitis, and cheilitis.

SWIMS: a small-angle multiple scattering computer code

International Nuclear Information System (INIS)

Sayer, R.O.

1976-07-01

SWIMS (Sigmund and WInterbon Multiple Scattering) is a computer code for calculation of the angular dispersion of ion beams that undergo small-angle, incoherent multiple scattering by gaseous or solid media. The code uses the tabulated angular distributions of Sigmund and Winterbon for a Thomas-Fermi screened Coulomb potential. The fraction of the incident beam scattered into a cone defined by the polar angle α is computed as a function of α for reduced thicknesses over the range 0.01 less than or equal to tau less than or equal to 10.0. 1 figure, 2 tables

Determinación del estado de salud bucal en pacientes discapacitados del Área VII en Cienfuegos

Directory of Open Access Journals (Sweden)

Ana Belkys Hernández Millán

2014-10-01

Full Text Available Fundamento: la discapacidad constituye una preocupación social, sin embargo, se cuenta con pocos estudios sobre el estado de salud bucal de los pacientes discapacitados. Objetivo: determinar el estado de salud bucal en pacientes discapacitados del Área VII de la provincia Cienfuegos. Métodos: se realizó un estudio descriptivo, de serie de casos, del Área VII del municipio de Cienfuegos, en el periodo de enero-diciembre de 2013. Se estudiaron 192 discapacitados que acudieron a consulta estomatológica o fueron visitados en terreno. Las variables analizadas fueron: edad, sexo, nivel de escolaridad, tipo de discapacidad, clasificación epidemiológica en cuanto al estado de salud bucal, enfermedades sistémicas, factores de riesgo a tener en cuenta para las enfermedades bucales, estado de salud bucal, periodontopatías, maloclusiones, lesiones premalignas, necesidad de prótesis total o parcial y necesidad de tratamiento en Atención Primaria o Secundaria. La información se recogió en historia clínica individual, planilla de clasificación de discapacidad. Los resultados se presentan en número y porcentaje. Resultados: el género femenino fue el más afectado, y la edad más representativa la de 35-59 años, predominaron las enfermedades crónicas degenerativas, los enfermos en la clasificación epidemiológica según estado de salud bucal, la hipertensión arterial entre las enfermedades sistémicas. Antecedentes de caries fue el factor de riesgo más relevante, resultando la gingivitis crónica edematosa, con un mayor porcentaje. Conclusiones: se determinó que la salud bucal en el grupo estudiado fue deficiente y existen dificultades por parte del Estomatólogo General Integral para tratar a estos pacientes a pesar de existir programas de atención a discapacitados.

Research on the improvement of nuclear safety -Improvement of level 1 PSA computer code package-

International Nuclear Information System (INIS)

Park, Chang Kyoo; Kim, Tae Woon; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae; Jang, Seung Chul; Yang, Joon Un; Choi, Yung; Sung, Tae Yong; Son, Yung Suk; Park, Won Suk; Jung, Kwang Sub; Kang Dae Il; Park, Jin Heui; Hwang, Mi Jung; Hah, Jae Joo

1995-07-01

This year is the third year of the Government-sponsored mid- and long-term nuclear power technology development project. The scope of this sub project titled on 'The improvement of level-1 PSA computer codes' is divided into three main activities : (1) Methodology development on the underdeveloped fields such as risk assessment technology for plant shutdown and low power situations, (2) Computer code package development for level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in this area of shutdown risk assessment technology development, plant outage experiences of domestic plants are reviewed and plant operating states (POS) are decided. A sample core damage frequency is estimated for over draining event in RCS low water inventory i.e. mid-loop operation. Human reliability analysis and thermal hydraulic support analysis are identified to be needed to reduce uncertainty. Two design improvement alternatives are evaluated using PSA technique for mid-loop operation situation: one is use of containment spray system as backup of shutdown cooling system and the other is installation of two independent level indication system. Procedure change is identified more preferable option to hardware modification in the core damage frequency point of view. Next, level-1 PSA code KIRAP is converted to PC-windows environment. For the improvement of efficiency in performing PSA, the fast cutest generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. 48 figs, 15 tabs, 59 refs. (Author)

Research on the improvement of nuclear safety -Improvement of level 1 PSA computer code package-

Energy Technology Data Exchange (ETDEWEB)

Park, Chang Kyoo; Kim, Tae Woon; Kim, Kil Yoo; Han, Sang Hoon; Jung, Won Dae; Jang, Seung Chul; Yang, Joon Un; Choi, Yung; Sung, Tae Yong; Son, Yung Suk; Park, Won Suk; Jung, Kwang Sub; Kang Dae Il; Park, Jin Heui; Hwang, Mi Jung; Hah, Jae Joo [Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

1995-07-01

This year is the third year of the Government-sponsored mid- and long-term nuclear power technology development project. The scope of this sub project titled on `The improvement of level-1 PSA computer codes` is divided into three main activities : (1) Methodology development on the underdeveloped fields such as risk assessment technology for plant shutdown and low power situations, (2) Computer code package development for level-1 PSA, (3) Applications of new technologies to reactor safety assessment. At first, in this area of shutdown risk assessment technology development, plant outage experiences of domestic plants are reviewed and plant operating states (POS) are decided. A sample core damage frequency is estimated for over draining event in RCS low water inventory i.e. mid-loop operation. Human reliability analysis and thermal hydraulic support analysis are identified to be needed to reduce uncertainty. Two design improvement alternatives are evaluated using PSA technique for mid-loop operation situation: one is use of containment spray system as backup of shutdown cooling system and the other is installation of two independent level indication system. Procedure change is identified more preferable option to hardware modification in the core damage frequency point of view. Next, level-1 PSA code KIRAP is converted to PC-windows environment. For the improvement of efficiency in performing PSA, the fast cutest generation algorithm and an analytical technique for handling logical loop in fault tree modeling are developed. 48 figs, 15 tabs, 59 refs. (Author).

Autoavaliação da saúde bucal e fatores associados entre adultos em áreas de assentamento rural, Estado de Pernambuco, Brasil

Directory of Open Access Journals (Sweden)

Cristiano Moura

2014-03-01

Full Text Available O objetivo deste estudo foi estimar a prevalência de autoavaliação negativa de saúde bucal e fatores associados entre adultos em áreas de assentamento rural. A amostra probabilística consistiu de 557 adultos entre 20 a 59 anos em áreas de assentamento rural no Estado de Pernambuco, Brasil. A variável dependente foi autoavaliação da condição de saúde bucal e as independentes foram: características demográficas, de predisposição/disponibilidade de recursos, comportamentos relacionados à saúde bucal, condições objetivas e subjetivas relacionadas à saúde bucal. Foram estimadas as razões de prevalência bruta e ajustada por meio de regressão de Poisson. A prevalência de autopercepção negativa da saúde bucal foi de 70,5%. A autoavaliação negativa da saúde bucal foi mais prevalente em indivíduos mais jovens, de baixa escolaridade, entre as mulheres, e entre os de cor preta e parda. Os preditores da autoavaliação negativa da saúde bucal foram a cor da pele, a necessidade autorreferida de tratamento odontológico e o impacto das condições de saúde bucal na qualidade de vida.

FLASH: A finite element computer code for variably saturated flow

International Nuclear Information System (INIS)

Baca, R.G.; Magnuson, S.O.

1992-05-01

A numerical model was developed for use in performance assessment studies at the INEL. The numerical model, referred to as the FLASH computer code, is designed to simulate two-dimensional fluid flow in fractured-porous media. The code is specifically designed to model variably saturated flow in an arid site vadose zone and saturated flow in an unconfined aquifer. In addition, the code also has the capability to simulate heat conduction in the vadose zone. This report presents the following: description of the conceptual frame-work and mathematical theory; derivations of the finite element techniques and algorithms; computational examples that illustrate the capability of the code; and input instructions for the general use of the code. The FLASH computer code is aimed at providing environmental scientists at the INEL with a predictive tool for the subsurface water pathway. This numerical model is expected to be widely used in performance assessments for: (1) the Remedial Investigation/Feasibility Study process and (2) compliance studies required by the US Department of Energy Order 5820.2A

Independent peer review of nuclear safety computer codes

International Nuclear Information System (INIS)

Boyack, B.E.; Jenks, R.P.

1993-01-01

A structured, independent computer code peer-review process has been developed to assist the US Nuclear Regulatory Commission (NRC) and the US Department of Energy in their nuclear safety missions. This paper describes a structured process of independent code peer review, benefits associated with a code-independent peer review, as well as the authors' recent peer-review experience. The NRC adheres to the principle that safety of plant design, construction, and operation are the responsibility of the licensee. Nevertheless, NRC staff must have the ability to independently assess plant designs and safety analyses submitted by license applicants. According to Ref. 1, open-quotes this requires that a sound understanding be obtained of the important physical phenomena that may occur during transients in operating power plants.close quotes The NRC concluded that computer codes are the principal products to open-quotes understand and predict plant response to deviations from normal operating conditionsclose quotes and has developed several codes for that purpose. However, codes cannot be used blindly; they must be assessed and found adequate for the purposes they are intended. A key part of the qualification process can be accomplished through code peer reviews; this approach has been adopted by the NRC

La rehabilitación protésica en las lesiones bucales del adulto mayor

Directory of Open Access Journals (Sweden)

Yaimara Pérez Hernández

2015-02-01

Full Text Available Introducción: las lesiones en la mucosa bucal relacionadas con el uso de prótesis constituyen un problema importante de salud, fundamentalmente en pacientes geriátricos. Objetivo: caracterizar las lesiones bucales en pacientes geriátricos rehabilitados protésicamente. Material y método: se realizó un estudio descriptivo, transversal y prospectivo en los consultorios médicos #9 y 47 de la Clínica Estomatológica Hermanos Saiz, municipio San Juan y Martínez, Pinar del Río, de septiembre de 2012 a septiembre de 2013. El universo estuvo conformado por 165 pacientes rehabilitados protésicamente, de los cuales 98 constituyeron la muestra, siendo pacientes que presentaron lesiones bucales producto del uso de prótesis. Como medida de resumen se utilizaron el número absoluto y el porcentaje. Resultados: el mayor número de pacientes se encontraban en edades entre 65 y 69 años, el sexo más afectado fue el femenino y las lesiones se encontraron principalmente en el maxilar y en pacientes que usaban prótesis totales de acrílico. Los pacientes que presentaban mala higiene de la prótesis eran más propensos a lesiones bucales. El mayor número de lesiones se encontró en pacientes que no practicaban el hábito de fumar. Conclusiones: se caracterizaron las lesiones bucales en pacientes geriátricos rehabilitados protésicamente, lo que posibilita proponer nuevas investigaciones sobre factores relacionados con el origen y prevención de dichas lesiones producto del uso de prótesis, y así mantener la comunicación necesaria de los implicados en el diagnóstico y atención de las personas longevas.

Computer code MLCOSP for multiple-correlation and spectrum analysis with a hybrid computer

International Nuclear Information System (INIS)

Oguma, Ritsuo; Fujii, Yoshio; Usui, Hozumi; Watanabe, Koichi

1975-10-01

Usage of the computer code MLCOSP(Multiple Correlation and Spectrum) developed is described for a hybrid computer installed in JAERI Functions of the hybrid computer and its terminal devices are utilized ingeniously in the code to reduce complexity of the data handling which occurrs in analysis of the multivariable experimental data and to perform the analysis in perspective. Features of the code are as follows; Experimental data can be fed to the digital computer through the analog part of the hybrid computer by connecting with a data recorder. The computed results are displayed in figures, and hardcopies are taken when necessary. Series-messages to the code are shown on the terminal, so man-machine communication is possible. And further the data can be put in through a keyboard, so case study according to the results of analysis is possible. (auth.)

Radiological impact assessment in Malaysia using RESRAD computer code

International Nuclear Information System (INIS)

Syed Hakimi Sakuma Syed Ahmad; Khairuddin Mohamad Kontol; Razali Hamzah

1999-01-01

Radiological Impact Assessment (RIA) can be conducted in Malaysia by using the RESRAD computer code developed by Argonne National Laboratory, U.S.A. The code can do analysis to derive site specific guidelines for allowable residual concentrations of radionuclides in soil. Concepts of the RIA in the context of waste management concern in Malaysia, some regulatory information and assess status of data collection are shown. Appropriate use scenarios and site specific parameters are used as much as possible so as to be realistic so that will reasonably ensure that individual dose limits and or constraints will be achieved. Case study have been conducted to fulfil Atomic Energy Licensing Board (AELB) requirements where for disposal purpose the operator must be required to carry out. a radiological impact assessment to all proposed disposals. This is to demonstrate that no member of public will be exposed to more than 1 mSv/year from all activities. Results obtained from analyses show the RESRAD computer code is able to calculate doses, risks, and guideline values. Sensitivity analysis by the computer code shows that the parameters used as input are justified so as to improve confidence to the public and the AELB the results of the analysis. The computer code can also be used as an initial assessment to conduct screening assessment in order to determine a proper disposal site. (Author)

Turbo Pascal Computer Code for PIXE Analysis

International Nuclear Information System (INIS)

Darsono

2002-01-01

To optimal utilization of the 150 kV ion accelerator facilities and to govern the analysis technique using ion accelerator, the research and development of low energy PIXE technology has been done. The R and D for hardware of the low energy PIXE installation in P3TM have been carried on since year 2000. To support the R and D of PIXE accelerator facilities in harmonize with the R and D of the PIXE hardware, the development of PIXE software for analysis is also needed. The development of database of PIXE software for analysis using turbo Pascal computer code is reported in this paper. This computer code computes the ionization cross-section, the fluorescence yield, and the stopping power of elements also it computes the coefficient attenuation of X- rays energy. The computer code is named PIXEDASIS and it is part of big computer code planed for PIXE analysis that will be constructed in the near future. PIXEDASIS is designed to be communicative with the user. It has the input from the keyboard. The output shows in the PC monitor, which also can be printed. The performance test of the PIXEDASIS shows that it can be operated well and it can provide data agreement with data form other literatures. (author)

Computer codes for simulation of Angra 1 reactor steam generator

International Nuclear Information System (INIS)

Pinto, A.C.

1978-01-01

A digital computer code is developed for the simulation of the steady-state operation of a u-tube steam generator with natural recirculation used in Pressurized Water Reactors. The steam generator is simulated with two flow channel separated by a metallic wall, with a preheating section with counter flow and a vaporizing section with parallel flow. The program permits the changes in flow patterns and heat transfer correlations, in accordance with the local conditions along the vaporizing section. Various sub-routines are developed for the determination of steam and water properties and a mathematical model is established for the simulation of transients in the same steam generator. The steady state operating conditions in one of the steam generators of ANGRA 1 reactor are determined utilizing this programme. Global results obtained agree with published values [pt

SCALE: A modular code system for performing Standardized Computer Analyses for Licensing Evaluation. Volume 1, Part 2: Control modules S1--H1; Revision 5

International Nuclear Information System (INIS)

1997-03-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automated the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.3 of the system

Avancos e desafios a Politica de Vigilancia a Saude Bucal no Brasil

Directory of Open Access Journals (Sweden)

Samuel Jorge Moyses

2013-12-01

Full Text Available Revisão crítica e integrativa, de caráter descritivo-discursivo, dedicada à explanação da política de vigilância à saúde bucal vigente atualmente no Brasil. Com base em uma apreciação crítica dos trabalhos nacionais e internacionais consultados sobre a temática da vigilância à saúde, examina-se a formulação de uma agenda política e científica em vigilância à saúde bucal, ancorada na institucionalidade do Sistema Único de Saúde. A efetivação da referida agenda é exemplificada com a apresentação da Pesquisa Nacional de Saúde Bucal (SBBrasil 2010. Uma síntese conclusiva é apresentada, buscando a convergência teórico-metodológica entre a identificação, por um lado, dos obstáculos e fragilidades ainda detectáveis na implementação da agenda e, por outro, no reconhecimento do seu mérito, discernível em expressivos avanços e conquistas já consolidados.

Evaluation of the SCANAIR Computer Code

International Nuclear Information System (INIS)

Jernkvist, Lars Olof; Massih, Ali

2001-11-01

The SCANAIR computer code, version 3.2, has been evaluated from the standpoint of its capability to analyze, simulate and predict nuclear fuel behavior during severe power transients. SCANAIR calculates the thermal and mechanical behavior of a pressurized water reactor (PWR) fuel rod during a postulated reactivity initiated accident (RIA), and our evaluation indicates that SCANAIR is a state of the art computational tool for this purpose. Our evaluation starts by reviewing the basic theoretical models in SCANAIR, namely the governing equations for heat transfer, the mechanical response of fuel and clad, and the fission gas release behavior. The numerical methods used to solve the governing equations are briefly reviewed, and the range of applicability of the models and their limitations are discussed and illustrated with examples. Next, the main features of the SCANAIR user interface are delineated. The code requires an extensive amount of input data, in order to define burnup-dependent initial conditions to the simulated RIA. These data must be provided in a special format by a thermal-mechanical fuel rod analysis code. The user also has to supply the transient power history under RIA as input, which requires a code for neutronics calculation. The programming structure and documentation of the code are also addressed in our evaluation. SCANAIR is programmed in Fortran-77, and makes use of several general Fortran-77 libraries for handling input/output, data storage and graphical presentation of computed results. The documentation of SCANAIR and its helping libraries is generally of good quality. A drawback with SCANAIR in its present form, is that the code and its pre- and post-processors are tied to computers running the Unix or Linux operating systems. As part of our evaluation, we have performed a large number of computations with SCANAIR, some of which are documented in this report. The computations presented here include a hypothetical RIA in a high

Computer codes used in particle accelerator design: First edition

International Nuclear Information System (INIS)

1987-01-01

This paper contains a listing of more than 150 programs that have been used in the design and analysis of accelerators. Given on each citation are person to contact, classification of the computer code, publications describing the code, computer and language runned on, and a short description of the code. Codes are indexed by subject, person to contact, and code acronym

MISER-I: a computer code for JOYO fuel management

International Nuclear Information System (INIS)

Yamashita, Yoshioki

1976-06-01

A computer code ''MISER-I'' is for a nuclear fuel management of Japan Experimental Fast Breeder Reactor JOYO. The nuclear fuel management in JOYO can be regarded as a fuel assembly management because a handling unit of fuel in JOYO plant is a fuel subassembly (core and blanket subassembly), and so the recording of material balance in computer code is made with each subassembly. The input information into computer code is given with each subassembly for a transfer operation, or with one reactor cycle and every one month for a burn-up in reactor core. The output information of MISER-I code is the fuel assembly storage record, fuel storage weight record in each material balance subarea at any specified day, and fuel subassembly transfer history record. Change of nuclear fuel composition and weight due to a burn-up is calculated with JOYO-Monitoring Code by off-line computation system. MISER-I code is written in FORTRAN-IV language for FACOM 230-48 computer. (auth.)

Selection of a computer code for Hanford low-level waste engineered-system performance assessment. Revision 1

International Nuclear Information System (INIS)

McGrail, B.P.; Bacon, D.H.

1998-02-01

Planned performance assessments for the proposed disposal of low-activity waste (LAW) glass produced from remediation of wastes stored in underground tanks at Hanford, Washington will require calculations of radionuclide release rates from the subsurface disposal facility. These calculations will be done with the aid of computer codes. The available computer codes with suitable capabilities at the time Revision 0 of this document was prepared were ranked in terms of the feature sets implemented in the code that match a set of physical, chemical, numerical, and functional capabilities needed to assess release rates from the engineered system. The needed capabilities were identified from an analysis of the important physical and chemical processes expected to affect LAW glass corrosion and the mobility of radionuclides. This analysis was repeated in this report but updated to include additional processes that have been found to be important since Revision 0 was issued and to include additional codes that have been released. The highest ranked computer code was found to be the STORM code developed at PNNL for the US Department of Energy for evaluation of arid land disposal sites

Qualidade de vida e saúde bucal em crianças e adolescentes: aspectos conceituais e metodológicos

OpenAIRE

Barbosa,Taís de Souza; Mialhe,Fábio Luiz; Castilho,Aline Rogéria Freire de; Gavião,Maria Beatriz Duarte

2010-01-01

O interesse pela qualidade de vida e saúde bucal em crianças e adolescentes vem aumentando, já que as desordens orais provavelmente apresentam efeito negativo na qualidade de vida das mesmas. Neste sentido, questionários que visam a avaliar o impacto da saúde bucal no bem-estar têm sido desenvolvidos e adaptados para este grupo específico. O objetivo deste trabalho é descrever a relação entre qualidade de vida e saúde bucal em crianças e adolescentes, focalizando aspectos conceituais e metodo...

Hamor-2: a computer code for LWR inventory calculation

International Nuclear Information System (INIS)

Guimaraes, L.N.F.; Marzo, M.A.S.

1985-01-01

A method for calculating the accuracy inventory of LWR reactors is presented. This method uses the Hamor-2 computer code. Hamor-2 is obtained from the coupling of two other computer codes Hammer-Techion and Origen-2 for testing Hamor-2, its results were compared to concentration values measured from activides of two PWR reactors; Kernkraftwerk Obrighein (KWO) and H.B. Robinson (HBR). These actinides are U 235 , U 236 , U 238 , Pu 239 , Pu 241 and PU 242 . The computer code Hammor-2 shows better results than the computer code Origem-2, when both are compared with experimental results. (E.G.) [pt

FLICA-4 (version 1). A computer code for three dimensional thermal analysis of nuclear reactor cores

International Nuclear Information System (INIS)

Raymond, P.; Allaire, G.; Boudsocq, G.; Caruge, D.; Gramont, T. de; Toumi, I.

1995-01-01

FLICA-4 is a thermal-hydraulic computer code, developed at the French Atomic Energy Commission (CEA) for three-dimensional steady-state or transient two-phase flow, and aimed at design and safety thermal analysis of nuclear reactor cores. It is available for various UNIX workstations and CRAY computers under UNICOS.It is based on four balance equations which include three balance equations for the mixture and a mass balance equation for the less concentrated phase which allows for the calculation of non equilibrium flows such as sub-cooled boiling and superheated steam. A drift velocity model takes into account the velocity unbalance between phases. The equations are solved using a finite volume numerical scheme. Typical running time, specific features (coupling with other codes) and auxiliary programs are presented. 1 tab., 9 refs

Poisson/Superfish codes for personal computers

International Nuclear Information System (INIS)

Humphries, S.

1992-01-01

The Poisson/Superfish codes calculate static E or B fields in two-dimensions and electromagnetic fields in resonant structures. New versions for 386/486 PCs and Macintosh computers have capabilities that exceed the mainframe versions. Notable improvements are interactive graphical post-processors, improved field calculation routines, and a new program for charged particle orbit tracking. (author). 4 refs., 1 tab., figs

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

ODONTOLOGIA NO ESPORTE: CONHECIMENTO E HÁBITOS DE ATLETAS DO FUTEBOL E BASQUETEBOL SOBRE SAÚDE BUCAL

Directory of Open Access Journals (Sweden)

Daniela Cristina Barbosa Alves

Full Text Available RESUMO Introdução: A saúde bucal é parte integrante da saúde sistêmica e é necessária para o bom rendimento físico. Objetivo: Este estudo teve como propósito avaliar e comparar o grau de conhecimento, atitudes e hábitos de atletas do gênero masculino, confederados do futebol e basquetebol, sobre a interrelação de saúde bucal e esporte. Métodos: Elaborou-se um questionário semiestruturado, composto por dezesseis questões objetivas e uma questão dissertativa, que foi respondido por 42 atletas do futebol e 40 atletas do basquetebol. Os esportistas foram questionados sobre seus conhecimentos a respeito do uso de protetores bucais na prática esportiva, interferências das alterações bucais no rendimento esportivo, utilização de medicamentos com finalidade odontológica e doping. Foram também questionados sobre o histórico de trauma durante a prática esportiva, uso de protetores bucais, suplementos, consumo de isotônicos ou energéticos, presença de alteração na articulação temporomandibular e participação em programa de saúde bucal no clube de origem. Resultados: Os resultados obtidos permitiram evidenciar que os atletas entrevistados não têm o conhecimento adequado sobre a influência da saúde bucal na prática esportiva, apesar de concordarem que os profissionais da odontologia contribuem para a manutenção da saúde bucal e a consequente melhoria do rendimento esportivo. Observou-se ainda, que os atletas do basquetebol relataram uma porcentagem maior de traumatismo com relação aos do futebol. A maioria dos atletas das duas modalidades relatou fazer uso de bebidas esportivas, não fazer uso de suplementos alimentares e não ser respirador bucal. Conclusão: Há necessidade de divulgação da importância da saúde bucal no meio esportivo para a manutenção da saúde sistêmica e melhora da prática esportiva.

HUDU: The Hanford Unified Dose Utility computer code

International Nuclear Information System (INIS)

Scherpelz, R.I.

1991-02-01

The Hanford Unified Dose Utility (HUDU) computer program was developed to provide rapid initial assessment of radiological emergency situations. The HUDU code uses a straight-line Gaussian atmospheric dispersion model to estimate the transport of radionuclides released from an accident site. For dose points on the plume centerline, it calculates internal doses due to inhalation and external doses due to exposure to the plume. The program incorporates a number of features unique to the Hanford Site (operated by the US Department of Energy), including a library of source terms derived from various facilities' safety analysis reports. The HUDU code was designed to run on an IBM-PC or compatible personal computer. The user interface was designed for fast and easy operation with minimal user training. The theoretical basis and mathematical models used in the HUDU computer code are described, as are the computer code itself and the data libraries used. Detailed instructions for operating the code are also included. Appendices to the report contain descriptions of the program modules, listings of HUDU's data library, and descriptions of the verification tests that were run as part of the code development. 14 refs., 19 figs., 2 tabs

FLICA-4 (version 1) a computer code for three dimensional thermal analysis of nuclear reactor cores

International Nuclear Information System (INIS)

Raymond, P.; Allaire, G.; Boudsocq, G.

1995-01-01

FLICA-4 is a thermal-hydraulic computer code developed at the French Energy Atomic Commission (CEA) for three dimensional steady state or transient two phase flow for design and safety thermal analysis of nuclear reactor cores. The two phase flow model of FLICA-4 is based on four balance equations for the fluid which includes: three balance equations for the mixture and a mass balance equation for the less concentrated phase which permits the calculation of non-equilibrium flows as sub cooled boiling and superheated steam. A drift velocity model takes into account the velocity disequilibrium between phases. The thermal behaviour of fuel elements can be computed by a one dimensional heat conduction equation in plane, cylindrical or spherical geometries and coupled to the fluid flow calculation. Convection and diffusion of solution products which are transported either by the liquid or by the gas, can be evaluated by solving specific mass conservation equations. A one dimensional two phase flow model can also be used to compute 1-D flow in pipes, guide tubes, BWR assemblies or RBMK channels. The FLICA-4 computer code uses fast running time steam-water functions. Phasic and saturation physical properties are computed by using bi-cubic spline functions. Polynomial coefficients are tabulated from 0.1 to 22 MPa and 0 to 800 degrees C. Specific modules can be utilised in order to generate the spline coefficients for any other fluid properties

Oral lichen planus versus epithelial dysplasia: difficulties in diagnosis Líquen plano bucal versus displasia epitelial: dificuldades diagnósticas

Directory of Open Access Journals (Sweden)

Fernando Augusto Cervantes Garcia de Sousa

2009-10-01

Full Text Available Histopathological diagnosis of oral lichen planus is not easy since some cases of epithelial dysplasia may present traits which are very similar to those from lichen planus. AIM: to compare cell alterations which suggest malignancy present in oral lichen planus with those from epithelial dysplasia. MATERIAL AND METHODS: histological cross-sections of oral lichen planus and dysplasia, dyed by hematoxylin-eosin, were analyzed by means of light microscopy. RESULTS: variance analysis (alpha=5% revealed a statistically significant difference between the average number of cell alterations in the lichen planus (5.83±1.61 and epithelial dysplasia (4.46±1.26. The chi-squared test did not show statistically significant differences between oral lichen planus and epithelial dysplasia in relation to the following cell alterations: increase in nucleus/cytoplasm ratio, nuclear hyperchromatism, irregular chromatin distribution and enlarged nuclei (p>0.05. CONCLUSION: Some cell alterations which suggest malignancy present in the oral lichen planus may also be found in epithelial dysplasia, impairing its diagnosis and, consequently, stressing the importance of following these patients in the long run.O diagnóstico histopatológico do líquen plano bucal não é fácil, pois alguns casos de displasia epitelial podem apresentar características bastante semelhantes às do líquen plano. OBJETIVO: Comparar as alterações celulares sugestivas de malignidade presentes no líquen plano bucal com as da displasia epitelial. MATERIAL E MÉTODOS: Cortes histológicos de líquen plano bucal e displasia, corados com hematoxilina-eosina, foram analisados por meio da microscopia de luz. RESULTADOS: A análise de variância (alfa=5% revelou haver diferença estatisticamente significante entre o número médio de alterações celulares no líquen plano bucal (5,83±1,61 e na displasia epitelial (4,46±1,26. O teste de qui-quadrado não mostrou diferença estatisticamente

Nonuniform code concatenation for universal fault-tolerant quantum computing

Science.gov (United States)

Nikahd, Eesa; Sedighi, Mehdi; Saheb Zamani, Morteza

2017-09-01

Using transversal gates is a straightforward and efficient technique for fault-tolerant quantum computing. Since transversal gates alone cannot be computationally universal, they must be combined with other approaches such as magic state distillation, code switching, or code concatenation to achieve universality. In this paper we propose an alternative approach for universal fault-tolerant quantum computing, mainly based on the code concatenation approach proposed in [T. Jochym-O'Connor and R. Laflamme, Phys. Rev. Lett. 112, 010505 (2014), 10.1103/PhysRevLett.112.010505], but in a nonuniform fashion. The proposed approach is described based on nonuniform concatenation of the 7-qubit Steane code with the 15-qubit Reed-Muller code, as well as the 5-qubit code with the 15-qubit Reed-Muller code, which lead to two 49-qubit and 47-qubit codes, respectively. These codes can correct any arbitrary single physical error with the ability to perform a universal set of fault-tolerant gates, without using magic state distillation.

CONTAIN LMR/1B-Mod.1, A computer code for containment analysis of accidents in liquid-metal-cooled nuclear reactors

International Nuclear Information System (INIS)

Murata, K.K.; Carroll, D.E.; Bergeron, K.D.; Valdez, G.D.

1993-01-01

The CONTAIN computer code is a best-estimate, integrated analysis tool for predicting the physical, chemical, and radiological conditions inside a nuclear reactor containment building following the release of core material from the primary system. CONTAIN is supported primarily by the U. S. Nuclear Regulatory Commission (USNRC), and the official code versions produced with this support are intended primarily for the analysis of light water reactors (LWR). The present manual describes CONTAIN LMR/1B-Mod. 1, a code version designed for the analysis of reactors with liquid metal coolant. It is a variant of the official CONTAIN 1.11 LWR code version. Some of the features of CONTAIN-LMR for treating the behavior of liquid metal coolant are in fact present in the LWR code versions but are discussed here rather than in the User's Manual for the LWR versions. These features include models for sodium pool and spray fires. In addition to these models, new or substantially improved models have been installed in CONTAIN-LMR. The latter include models for treating two condensables (sodium and water) simultaneously, sodium atmosphere and pool chemistry, sodium condensation on aerosols, heat transfer from core-debris beds and to sodium pools, and sodium-concrete interactions. A detailed description of each of the above models is given, along with the code input requirements

Estado de salud bucal en la población geriátrica de la casa de abuelos 28 de septiembre

Directory of Open Access Journals (Sweden)

Karelia Castro Figueredo

2015-01-01

Full Text Available Se realizó un estudio descriptivo transversal en la casa de abuelos “28 de Septiembre”, perteneciente al municipio de Las Tunas, en el periodo de septiembre de 2013 a junio de 2014, con el objetivo de caracterizar el estado de salud bucal de esta población, conformada por los 44 gerontes que asistieron a la referida casa de abuelos en el periodo de estudio. Se evaluaron variables como el nivel de escolaridad, las enfermedades bucales presentes, los factores asociados y el nivel de conocimiento sobre salud bucal. Se utilizaron los porcentajes como medidas de resumen para las variables seleccionadas. El grupo de edad que predominó fue el de 80 y más, la mayor parte de ellos fue del sexo masculino y con primaria terminada. La enfermedad bucal que más abundó fue la caries dental y el factor asociado predominante fue la deficiente higiene bucal. La mayor parte de los pacientes estudiados formó parte del grupo II de los enfermos, según la clasificación epidemiológica. Primaron los pacientes con bajos conocimientos sobre las enfermedades bucodentales

PORPST: A statistical postprocessor for the PORMC computer code

International Nuclear Information System (INIS)

Eslinger, P.W.; Didier, B.T.

1991-06-01

This report describes the theory underlying the PORPST code and gives details for using the code. The PORPST code is designed to do statistical postprocessing on files written by the PORMC computer code. The data written by PORMC are summarized in terms of means, variances, standard deviations, or statistical distributions. In addition, the PORPST code provides for plotting of the results, either internal to the code or through use of the CONTOUR3 postprocessor. Section 2.0 discusses the mathematical basis of the code, and Section 3.0 discusses the code structure. Section 4.0 describes the free-format point command language. Section 5.0 describes in detail the commands to run the program. Section 6.0 provides an example program run, and Section 7.0 provides the references. 11 refs., 1 fig., 17 tabs

Amiloidosis bucal Oral amyloidosis

Directory of Open Access Journals (Sweden)

Isabella Lima Arrais Ribeiro

2012-03-01

Full Text Available A amiloidose é uma doença complexa rara de difícil diagnóstico que ocorre devido à deposição de substância amilóide no meio extracelular. Ao ser diagnosticado na cavidade bucal, deve-se monitorar o paciente a fim de avaliar possíveis complicações sistêmicas da doença. Diante disso, o objetivo do presente estudo é relatar um caso de amiloidose oral em uma paciente do gênero feminino de 72 anos de idade. Baseado nos sinais clínicos observados, a hipótese diagnóstica foi de fibroma traumático. Após realização de biópsia e exame histopatológico, o diagnóstico foi de amiloidose oral, o que foi confirmado com a coloração do espécime com o reagente vermelho congo. Depósitos de amilóide foram encontrados no tecido conjuntivo, na avaliação através da luz polarizada, que apresentou birrefringência. Tal achado foi preocupante, já que a amiloidose geralmente acomete diversos tecidos levando a comprometimentos sistêmicos. Por essa razão a paciente foi encaminhada a procurar atendimento médico. No entanto, houve abandono do tratamento e a mesma veio a óbito 6 meses após o diagnóstico da doença. Lesões orais aparentemente simples podem revelar doenças raras e de difícil tratamento. O diagnóstico preciso e acompanhamentos médicos são fundamentais na sobrevida do paciente.La amiloidosis es una enfermedad compleja, rara, de difícil diagnóstico, que ocurre debido al depósito de sustancia amiloidea en medio extracelular. Al ser diagnosticada en la cavidad bucal, el paciente debe tener supervisión médica para evaluar las posibles complicaciones sistémicas de la enfermedad. El objetivo del presente estudio fue presentar un caso de amiloidosis bucal en un paciente del género femenino de 72 años de edad. Basados en las señales clínicas observadas, la hipótesis diagnóstica fue de un fibroma traumático. Después de la realización de una biopsia y del examen histopatológico, el diagnóstico fue de amiloidosis

Automated uncertainty analysis methods in the FRAP computer codes

International Nuclear Information System (INIS)

Peck, S.O.

1980-01-01

A user oriented, automated uncertainty analysis capability has been incorporated in the Fuel Rod Analysis Program (FRAP) computer codes. The FRAP codes have been developed for the analysis of Light Water Reactor fuel rod behavior during steady state (FRAPCON) and transient (FRAP-T) conditions as part of the United States Nuclear Regulatory Commission's Water Reactor Safety Research Program. The objective of uncertainty analysis of these codes is to obtain estimates of the uncertainty in computed outputs of the codes is to obtain estimates of the uncertainty in computed outputs of the codes as a function of known uncertainties in input variables. This paper presents the methods used to generate an uncertainty analysis of a large computer code, discusses the assumptions that are made, and shows techniques for testing them. An uncertainty analysis of FRAP-T calculated fuel rod behavior during a hypothetical loss-of-coolant transient is presented as an example and carried through the discussion to illustrate the various concepts

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)

Implantation of FRAPCON-2 code in HB computer

International Nuclear Information System (INIS)

Silva, C.F. da.

1987-05-01

The modifications carried out for implanting FRAPCON-2 computer code in the HB DPS-T7 computer are presented. The FRAPCON-2 code calculates thermo-mechanical response during long period of burnup in stationary state for fuel rods of PWR type reactors. (M.C.K.)

CASKETSS: a computer code system for thermal and structural analysis of nuclear fuel shipping casks

International Nuclear Information System (INIS)

Ikushima, Takeshi

1989-02-01

A computer program CASKETSS has been developed for the purpose of thermal and structural analysis of nuclear fuel shipping casks. CASKETSS measn a modular code system for CASK Evaluation code system Thermal and Structural Safety. Main features of CASKETSS are as follow; (1) Thermal and structural analysis computer programs for one-, two-, three-dimensional geometries are contained in the code system. (2) Some of the computer programs in the code system has been programmed to provide near optimal speed on vector processing computers. (3) Data libralies fro thermal and structural analysis are provided in the code system. (4) Input data generator is provided in the code system. (5) Graphic computer program is provided in the code system. In the paper, brief illustration of calculation method, input data and sample calculations are presented. (author)

Intervención educativa sobre higiene bucal en escolares del seminternado “Jesús Argüelles Hidalgo”

Directory of Open Access Journals (Sweden)

Nivia M. Aguilera Trotman

2015-11-01

Full Text Available Se realizó una intervención educativa en la rama de las Ciencias Médicas, específicamente en la estomatología, con el objetivo de elevar el nivel de conocimiento sobre higiene bucal en escolares de ocho a doce años de edad del seminternado “Jesús Argüelles Hidalgo”, perteneciente a la clínica estomatológica “Guillermo Tejas” del municipio de Las Tunas, en el período comprendido de mayo de 2010 a mayo de 2012. El universo estuvo constituido por 392 escolares, seleccionándose una muestra de 150 que cumplió con los criterios establecidos. La intervención educativa se desarrolló con previa organización de los temas en ocho sesiones, y con el empleo de técnicas educativas y diferentes medios de enseñanza. A los escolares se les aplicó un cuestionario, determinándose así el nivel de conocimiento sobre salud bucal y para determinar el comportamiento de la higiene bucal se utilizó el índice de higiene bucal de Love, al inicio y final del estudio; además, se ejecutó una lluvia de ideas para conocer las necesidades sentidas al inicio de la intervención. Se aplicó el modelo de David Leyva, determinándose las necesidades de aprendizaje. Prevaleció el grupo de ocho a diez años de edad, así como el sexo masculino. Se compararon los resultados iniciales con los obtenidos al finalizar la intervención, concluyendo que se logró elevar el nivel de conocimientos sobre salud bucal de los escolares y se mejoró la higiene bucal de los mismos; la intervención educativa fue satisfactoria.

Alteraciones de la mucosa bucal causadas por la asociación entre el tabaco y los colutorios bucales con una concentración de alcohol del 26,9 %

Directory of Open Access Journals (Sweden)

Anna Christina Medeiros Fossati

Full Text Available Se analizaron el epitelio y la capa de queratina de la mucosa oral de 15 ratas que durante 45 días fueron sometidas a una aplicación tópica de picadura de tabaco y de colutorio bucal con una concentración de alcohol del 26,9 %. Tras ese período, se extrajeron las mucosas y se les realizó un análisis histológico. Se observó una significativa disminución del espesor del epitelio y de la capa de queratina, lo que indica que la picadura asociada con colutorios bucales con alta concentración de alcohol, provoca la reducción del espesor de la capa de queratina y del epitelio de la boca.

Algorithms and computer codes for atomic and molecular quantum scattering theory

International Nuclear Information System (INIS)

Thomas, L.

1979-01-01

This workshop has succeeded in bringing up 11 different coupled equation codes on the NRCC computer, testing them against a set of 24 different test problems and making them available to the user community. These codes span a wide variety of methodologies, and factors of up to 300 were observed in the spread of computer times on specific problems. A very effective method was devised for examining the performance of the individual codes in the different regions of the integration range. Many of the strengths and weaknesses of the codes have been identified. Based on these observations, a hybrid code has been developed which is significantly superior to any single code tested. Thus, not only have the original goals been fully met, the workshop has resulted directly in an advancement of the field. All of the computer programs except VIVS are available upon request from the NRCC. Since an improved version of VIVS is contained in the hybrid program, VIVAS, it was not made available for distribution. The individual program LOGD is, however, available. In addition, programs which compute the potential energy matrices of the test problems are also available. The software library names for Tests 1, 2 and 4 are HEH2, LICO, and EN2, respectively

Cirugía bucal mayor ambulatoria

OpenAIRE

Carranza Pelegrina, Daniela; Bellorbí Malet, I.; Brescó Salinas, Vicente Miguel; Berini Aytés, Leonardo; Gay Escoda, Cosme

2004-01-01

La Cirugía Bucal Mayor Ambulatoria ( CBMA) se define como un modelo organizativo óptimo de asis­tencia quirúrgica multidisci­plinaria que permite tratar a determinados pacientes de una forma segura y efectiva sin necesidad de contar con la cama de hospitalización tradicional. De esta manera se llevan a cabo distintos procedimientos diagnósticos y terapéuticos de mediana complejidad en los que el enfermo regresa a su domici­lio después de un periodo de observación y control. Entre las ventajas...

El embarazo y la salud bucal

OpenAIRE

Bouza Vera, Meylín; Martínez Abreu, Judit; Carmenate Rodríguez, Yamila; Betancourt González, Magdalena; García Nicieza, Maydelis

2016-01-01

El embarazo es un proceso natural y sublime en la vida de una mujer, etapa que está acompañada de cambios fisiológicos, patológicos y psicológicos. El aumento de los niveles hormonales, entre ellos, de estrógenos y progesteronas indispensables para el desarrollo del feto, se asocian a enfermedades bucales como la gingivitis del embarazo. Por su parte, la gonadotropina, se relaciona con náuseas y vómitos, que pueden llegar a producir erosión del esmalte. Este malestar trae consigo un inadecuad...

Reorientación de la Atención Básica en Salud Bucal en Unaí – Minas Gerais

Directory of Open Access Journals (Sweden)

Luciano José ARANTES

2011-12-01

Full Text Available Este trabajo tuvo como objetivo estudiar como ocurre la atención básica en salud bucal en el municipio de la ciudad de Unaí – M.G y, también, proponer una reorientación del modelo encontrado adoptando como parámetro una programación estratégica. Esa programación fue elaborada con base en las políticas nacionales del estado de Minas Gerais y del municipio de Unaí para el desarrollo de las prácticas de salud bucal. Fue utilizado un cuestionario tipo “Likert” para recolección de datos en una muestra con formación de profesionales de salud bucal, gestor municipal y consejero de salud. La atención básica en salud bucal fue caracterizada como incipiente debido a la programación y evaluación de los servicios, territorialización y restricción de la población, realización de exámenes epidemiológicos y, también, de la primera consulta odontológica y establecimiento de mecanismos de referencia y contra referencia. Las acciones de acogida, educación en salud bucal, precaución específica, fluoración del abastecimiento de agua y diagnóstico precoz de incidentes en el estómago resgistraron en el grado intermediario. La atención de emergencia y el tratamiento realizado en grupos prioritarios fueron considerados por la mayoría de los entrevistados como satisfactorios. La inserción de profesionales de la salud bucal en la filosofía de trabajo de la estrategia salud de la familia parece ser la opción más viable para una reorientación del modelo de atención básica en salud bucal en Unaí-MG.

Computer code FIT

International Nuclear Information System (INIS)

Rohmann, D.; Koehler, T.

1987-02-01

This is a description of the computer code FIT, written in FORTRAN-77 for a PDP 11/34. FIT is an interactive program to decude position, width and intensity of lines of X-ray spectra (max. length of 4K channels). The lines (max. 30 lines per fit) may have Gauss- or Voigt-profile, as well as exponential tails. Spectrum and fit can be displayed on a Tektronix terminal. (orig.) [de

A new 3-D integral code for computation of accelerator magnets

International Nuclear Information System (INIS)

Turner, L.R.; Kettunen, L.

1991-01-01

For computing accelerator magnets, integral codes have several advantages over finite element codes; far-field boundaries are treated automatically, and computed field in the bore region satisfy Maxwell's equations exactly. A new integral code employing edge elements rather than nodal elements has overcome the difficulties associated with earlier integral codes. By the use of field integrals (potential differences) as solution variables, the number of unknowns is reduced to one less than the number of nodes. Two examples, a hollow iron sphere and the dipole magnet of Advanced Photon Source injector synchrotron, show the capability of the code. The CPU time requirements are comparable to those of three-dimensional (3-D) finite-element codes. Experiments show that in practice it can realize much of the potential CPU time saving that parallel processing makes possible. 8 refs., 4 figs., 1 tab

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Landers, N.F.; Petrie, L.M.; Knight, J.R. [Oak Ridge National Lab., TN (United States)] [and others

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Control modules -- Volume 1, Revision 4

International Nuclear Information System (INIS)

Landers, N.F.; Petrie, L.M.; Knight, J.R.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. This manual is divided into three volumes: Volume 1--for the control module documentation, Volume 2--for the functional module documentation, and Volume 3 for the documentation of the data libraries and subroutine libraries

Fracture Analysis of Vessels. Oak Ridge FAVOR, v06.1, Computer Code: Theory and Implementation of Algorithms, Methods, and Correlations

Energy Technology Data Exchange (ETDEWEB)

Williams, P. T. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Dickson, T. L. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Yin, S. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2007-12-01

The current regulations to insure that nuclear reactor pressure vessels (RPVs) maintain their structural integrity when subjected to transients such as pressurized thermal shock (PTS) events were derived from computational models developed in the early-to-mid 1980s. Since that time, advancements and refinements in relevant technologies that impact RPV integrity assessment have led to an effort by the NRC to re-evaluate its PTS regulations. Updated computational methodologies have been developed through interactions between experts in the relevant disciplines of thermal hydraulics, probabilistic risk assessment, materials embrittlement, fracture mechanics, and inspection (flaw characterization). Contributors to the development of these methodologies include the NRC staff, their contractors, and representatives from the nuclear industry. These updated methodologies have been integrated into the Fracture Analysis of Vessels -- Oak Ridge (FAVOR, v06.1) computer code developed for the NRC by the Heavy Section Steel Technology (HSST) program at Oak Ridge National Laboratory (ORNL). The FAVOR, v04.1, code represents the baseline NRC-selected applications tool for re-assessing the current PTS regulations. This report is intended to document the technical bases for the assumptions, algorithms, methods, and correlations employed in the development of the FAVOR, v06.1, code.

Percepção de equipes de saúde bucal no norte de Minas Gerais sobre a formação de técnicos em saúde bucal do SUS

OpenAIRE

Silva, Maria Patrícia da; Costa, Georgia Sarmento; Crispim, Zaida Angela Marinho de Paiva; Castro, Eveline Andries; Cerqueira, Marília Borborema Rodrigues; Garibalde, Elika

2014-01-01

A inclusão das Equipes de Saúde Bucal na Estratégia Saúde da Família representa uma mudança na saúde pública. Este estudo tem como objetivo conhecer percepções de egressos e coordenadores da formação técnica ministrada pela Escola Técnica de Saúde para Técnicos em Saúde Bucal em municípios do Norte de Minas Gerais, a partir do Programa Brasil Sorridente. A metodologia utilizada é exploratória-descritiva, com ênfase qualitativa. Os egressos afirmam que a participação no curso beneficia o servi...

APC: A New Code for Atmospheric Polarization Computations

Science.gov (United States)

Korkin, Sergey V.; Lyapustin, Alexei I.; Rozanov, Vladimir V.

2014-01-01

A new polarized radiative transfer code Atmospheric Polarization Computations (APC) is described. The code is based on separation of the diffuse light field into anisotropic and smooth (regular) parts. The anisotropic part is computed analytically. The smooth regular part is computed numerically using the discrete ordinates method. Vertical stratification of the atmosphere, common types of bidirectional surface reflection and scattering by spherical particles or spheroids are included. A particular consideration is given to computation of the bidirectional polarization distribution function (BPDF) of the waved ocean surface.

Quantum computing with Majorana fermion codes

Science.gov (United States)

Litinski, Daniel; von Oppen, Felix

2018-05-01

We establish a unified framework for Majorana-based fault-tolerant quantum computation with Majorana surface codes and Majorana color codes. All logical Clifford gates are implemented with zero-time overhead. This is done by introducing a protocol for Pauli product measurements with tetrons and hexons which only requires local 4-Majorana parity measurements. An analogous protocol is used in the fault-tolerant setting, where tetrons and hexons are replaced by Majorana surface code patches, and parity measurements are replaced by lattice surgery, still only requiring local few-Majorana parity measurements. To this end, we discuss twist defects in Majorana fermion surface codes and adapt the technique of twist-based lattice surgery to fermionic codes. Moreover, we propose a family of codes that we refer to as Majorana color codes, which are obtained by concatenating Majorana surface codes with small Majorana fermion codes. Majorana surface and color codes can be used to decrease the space overhead and stabilizer weight compared to their bosonic counterparts.

Two-dimensional color-code quantum computation

International Nuclear Information System (INIS)

Fowler, Austin G.

2011-01-01

We describe in detail how to perform universal fault-tolerant quantum computation on a two-dimensional color code, making use of only nearest neighbor interactions. Three defects (holes) in the code are used to represent logical qubits. Triple-defect logical qubits are deformed into isolated triangular sections of color code to enable transversal implementation of all single logical qubit Clifford group gates. Controlled-NOT (CNOT) is implemented between pairs of triple-defect logical qubits via braiding.

Establishment of computer code system for nuclear reactor design - analysis

International Nuclear Information System (INIS)

Subki, I.R.; Santoso, B.; Syaukat, A.; Lee, S.M.

1996-01-01

Establishment of computer code system for nuclear reactor design analysis is given in this paper. This establishment is an effort to provide the capability in running various codes from nuclear data to reactor design and promote the capability for nuclear reactor design analysis particularly from neutronics and safety points. This establishment is also an effort to enhance the coordination of nuclear codes application and development existing in various research centre in Indonesia. Very prospective results have been obtained with the help of IAEA technical assistance. (author). 6 refs, 1 fig., 1 tab

GASFLOW: A Computational Fluid Dynamics Code for Gases, Aerosols, and Combustion, Volume 1: Theory and Computational Model

International Nuclear Information System (INIS)

Nichols, B.D.; Mueller, C.; Necker, G.A.; Travis, J.R.; Spore, J.W.; Lam, K.L.; Royl, P.; Redlinger, R.; Wilson, T.L.

1998-01-01

Los Alamos National Laboratory (LANL) and Forschungszentrum Karlsruhe (FzK) are developing GASFLOW, a three-dimensional (3D) fluid dynamics field code as a best-estimate tool to characterize local phenomena within a flow field. Examples of 3D phenomena include circulation patterns; flow stratification; hydrogen distribution mixing and stratification; combustion and flame propagation; effects of noncondensable gas distribution on local condensation and evaporation; and aerosol entrainment, transport, and deposition. An analysis with GASFLOW will result in a prediction of the gas composition and discrete particle distribution in space and time throughout the facility and the resulting pressure and temperature loadings on the walls and internal structures with or without combustion. A major application of GASFLOW is for predicting the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facilities. It has been applied to situations involving transporting and distributing combustible gas mixtures. It has been used to study gas dynamic behavior (1) in low-speed, buoyancy-driven flows, as well as sonic flows or diffusion dominated flows; and (2) during chemically reacting flows, including deflagrations. The effects of controlling such mixtures by safety systems can be analyzed. The code version described in this manual is designated GASFLOW 2.1, which combines previous versions of the United States Nuclear Regulatory Commission code HMS (for Hydrogen Mixing Studies) and the Department of Energy and FzK versions of GASFLOW. The code was written in standard Fortran 90. This manual comprises three volumes. Volume I describes the governing physical equations and computational model. Volume II describes how to use the code to set up a model geometry, specify gas species and material properties, define initial and boundary conditions, and specify different outputs, especially graphical displays. Sample problems are included

Calidad de vida y problemas bucales en preescolares de la provincia de Huaura, Lima.

OpenAIRE

López-Ramos, Roxana Patricia; García-Rupaya, Carmen Rosa

2014-01-01

Objetivos: Evaluar el impacto de los problemas bucales en la calidad de vida en niños de 3 a 5 años de la Institución Educativa Inicial del distrito Hualmay de la provincia de Huaura, departamento de Lima en el 2011. Material y Métodos: Este estudio fue de tipo descriptiva, transversal. Evaluó a 153 niños, a quienes se les examinó la cavidad bucal y al responsable del cuidado del niño se aplicó el Early Childhood Oral Health Impact Scale (ECOHIS); previamente se realizó la validación peruana....

Procedure and code for calculating black control rods taking into account epithermal absorption, code CAS-1

International Nuclear Information System (INIS)

Martinc, R.; Trivunac, N.; Zivkovic, Z.

1964-12-01

This report describes the computer code CAS-1, calculation method and procedure applied for calculating the black control rods taking into account the epithermal neutron absorption. Results obtained for supercell method applied for regular lattice reflected in the multiplication medium is part of this report in addition to the computer code manual

The archaeology of computer codes - illustrated on the basis of the code SABINE

International Nuclear Information System (INIS)

Sdouz, G.

1987-02-01

Computer codes used by the physics group of the Institute for Reactor Safety are stored on back-up-tapes. However during the last years both the computer and the system have been changed. For new tasks these programmes have to be available. A new procedure is necessary to find and to activate a stored programme. This procedure is illustrated on the basis of the code SABINE. (Author)

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

Computation of the Genetic Code

Science.gov (United States)

Kozlov, Nicolay N.; Kozlova, Olga N.

2018-03-01

One of the problems in the development of mathematical theory of the genetic code (summary is presented in [1], the detailed -to [2]) is the problem of the calculation of the genetic code. Similar problems in the world is unknown and could be delivered only in the 21st century. One approach to solving this problem is devoted to this work. For the first time provides a detailed description of the method of calculation of the genetic code, the idea of which was first published earlier [3]), and the choice of one of the most important sets for the calculation was based on an article [4]. Such a set of amino acid corresponds to a complete set of representations of the plurality of overlapping triple gene belonging to the same DNA strand. A separate issue was the initial point, triggering an iterative search process all codes submitted by the initial data. Mathematical analysis has shown that the said set contains some ambiguities, which have been founded because of our proposed compressed representation of the set. As a result, the developed method of calculation was limited to the two main stages of research, where the first stage only the of the area were used in the calculations. The proposed approach will significantly reduce the amount of computations at each step in this complex discrete structure.

Computer codes for problems of isotope and radiation research

International Nuclear Information System (INIS)

Remer, M.

1986-12-01

A survey is given of computer codes for problems in isotope and radiation research. Altogether 44 codes are described as titles with abstracts. 17 of them are in the INIS scope and are processed individually. The subjects are indicated in the chapter headings: 1) analysis of tracer experiments, 2) spectrum calculations, 3) calculations of ion and electron trajectories, 4) evaluation of gamma irradiation plants, and 5) general software

SKEMA - A computer code to estimate atmospheric dispersion

International Nuclear Information System (INIS)

Sacramento, A.M. do.

1985-01-01

This computer code is a modified version of DWNWND code, developed in Oak Ridge National Laboratory. The Skema code makes an estimative of concentration in air of a material released in atmosphery, by ponctual source. (C.M.) [pt

Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 1

International Nuclear Information System (INIS)

Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

1993-08-01

The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

Setting oral health goals that include oral health-related quality of life measures: a study carried out among adolescents in Thailand Incorporação da qualidade de vida relacionada à saúde bucal em metas de saúde bucal: estudo conduzido em adolescentes tailandeses

Directory of Open Access Journals (Sweden)

Sudaduang Krisdapong

2012-10-01

Full Text Available The aim of this study was to assess the association between oral diseases and condition-specific oral health-related quality of life (CS-OHRQoL as a basis for proposing OHRQoL-based goals for the population of 15-year-olds in Thailand. Oral examinations and OHRQoL interviews were conducted with 871 15-year-olds as part of the Sixth Thailand National Oral Health Survey. The severity of oral impacts was categorized using "intensity". Associations between oral diseases and CS-OHRQoL were analyzed using chi-square and logistic regression. Thirty-nine percent of 15-year-olds experienced moderate/higher levels oral impacts on quality of life. Compared to those individuals with no tooth decay, adolescents with one or four or more decaying teeth were three and seven times more likely to experience moderate/higher impacts, respectively. Adolescents with extensive gingivitis in 3 or more mouth sextants were twice as likely to experience moderate/higher CS-impacts. Based on these findings, it is proposed that goals should focus on untreated decaying teeth and extensive gingivitis. Oral health goals for 15-year-olds should include specific OHRQoL measures.O objetivo deste estudo foi avaliar a associação entre doença bucal e a condição específica de qualidade de vida associada à saúde bucal (CS-OHRQoL, como base para propor OHRQoL metas para adolescentes tailandeses. Exame clínico bucal e entrevista foram realizados em 871 adolescentes na faixa etária de 15 anos, como parte da 6ª Pesquisa Nacional Tailandesa de Saúde Bucal. A severidade do impacto bucal foi categorizada usando-se a "intensidade". A associação entre doença bucal e CS-OHRQoL foi investigada usando-se o teste qui-quadrado e regressão lógica. Trinta e nove por cento da amostra reportaram impactos bucais de grau moderado/elevado. A probabilidade de reportar um impacto bucal de grau moderado/elevado dos adolescentes com um dente cariado e aqueles com 4 ou mais foi 3 e 7 vezes

A computer code for fault tree calculations: PATREC

International Nuclear Information System (INIS)

Blin, A.; Carnino, A.; Koen, B.V.; Duchemin, B.; Lanore, J.M.; Kalli, H.

1978-01-01

A computer code for evaluating the reliability of complex system by fault tree is described in this paper. It uses pattern recognition approach and programming techniques from IBM PL1 language. It can take account of many of the present day problems: multi-dependencies treatment, dispersion in the reliability data parameters, influence of common mode failures. The code is running currently since two years now in Commissariat a l'Energie Atomique Saclay center and shall be used in a future extension for automatic fault trees construction

Pautas orientadoras para la promoción de la salud bucal en la primera infancia para profesionales de salud

Directory of Open Access Journals (Sweden)

Gloria Esperanza González C.

2012-11-01

Full Text Available La salud bucal es parte integral de la salud general del individuo. Lasafecciones bucales más prevalentes en niños son las alteraciones delcrecimiento y desarrollo bucodental, y la caries. Las primeras, generalmente están relacionadas con hábitos orales nocivos, patronesalimentarios inadecuados y la adquisición tardía de funciones comola masticación que generan maloclusiones. La caries, enfermedadcrónica más frecuente en la infancia, causa graves consecuencias enla salud del niño como dolor, infecciones faciales, hospitalizacionesy consultas frecuentes a los servicios de urgencia. Se pretende proponer una guía que permita detectar tempranamente los factoresde riesgo para la caries de infancia temprana y maloclusiones a losprofesionales de salud que entran tempranamente en contacto conel bebé y su familia para la promoción de salud bucal. Es esencial elcuidado de la salud oral de la madre gestante incentivando la lactanciamaterna como factor protector sobre la salud general y bucal delrecién nacido.

A política de saúde bucal em pauta no Conselho Municipal de Saúde no Município de Nova Friburgo - RJ

Directory of Open Access Journals (Sweden)

Rafael Gomes Ditterich

Full Text Available Objetivo O presente estudo teve como objetivo analisar, por meio dos documentos técnicos do Conselho Municipal de Saúde (CMS, a organização dos serviços de saúde bucal no Município de Nova Friburgo - RJ, a partir da institucionalização da Política Nacional de Saúde Bucal. Metodologia Para a análise documental, utilizou-se o registro de frequência e categorização por assunto: saúde bucal das atas do CMS de junho/2006 a agosto/2011, do Plano Municipal de Saúde de 2003-2005 e 2010-2013, e os documentos encaminhados entre 2005 e 2011. Resultado Os registros analisados até 2012 indicaram que a população estava desassistida na questão da média complexidade, como também no acesso à água fluoretada. As equipes de saúde bucal ainda não tinham sido qualificadas e ampliadas, como é bem colocado como prioridade no Brasil Sorridente. O Município ainda não desenvolvia programas de prevenção e promoção de saúde bucal de forma contínua e efetiva. Conclusão Concluiu-se que a Política Nacional de Saúde Bucal, até o ano de 2012, não tinha ainda reflexo nas ações de saúde bucal em Nova Friburgo.

Computer code qualification program for the Advanced CANDU Reactor

International Nuclear Information System (INIS)

Popov, N.K.; Wren, D.J.; Snell, V.G.; White, A.J.; Boczar, P.G.

2003-01-01

Atomic Energy of Canada Ltd (AECL) has developed and implemented a Software Quality Assurance program (SQA) to ensure that its analytical, scientific and design computer codes meet the required standards for software used in safety analyses. This paper provides an overview of the computer programs used in Advanced CANDU Reactor (ACR) safety analysis, and assessment of their applicability in the safety analyses of the ACR design. An outline of the incremental validation program, and an overview of the experimental program in support of the code validation are also presented. An outline of the SQA program used to qualify these computer codes is also briefly presented. To provide context to the differences in the SQA with respect to current CANDUs, the paper also provides an overview of the ACR design features that have an impact on the computer code qualification. (author)

Vectorization of nuclear codes on FACOM 230-75 APU computer

International Nuclear Information System (INIS)

Harada, Hiroo; Higuchi, Kenji; Ishiguro, Misako; Tsutsui, Tsuneo; Fujii, Minoru

1983-02-01

To provide for the future usage of supercomputer, we have investigated the vector processing efficiency of nuclear codes which are being used at JAERI. The investigation is performed by using FACOM 230-75 APU computer. The codes are CITATION (3D neutron diffusion), SAP5 (structural analysis), CASCMARL (irradiation damage simulation). FEM-BABEL (3D neutron diffusion by FEM), GMSCOPE (microscope simulation). DWBA (cross section calculation at molecular collisions). A new type of cell density calculation for particle-in-cell method is also investigated. For each code we have obtained a significant speedup which ranges from 1.8 (CASCMARL) to 7.5 (GMSCOPE), respectively. We have described in this report the running time dynamic profile analysis of the codes, numerical algorithms used, program restructuring for the vectorization, numerical experiments of the iterative process, vectorized ratios, speedup ratios on the FACOM 230-75 APU computer, and some vectorization views. (author)

Introduction and immigration of TRAC-PF1 code

International Nuclear Information System (INIS)

Yan Yuhua; Gao Zuying; Gao Cheng; Li Jincai

1997-01-01

TRAC-PF1 code performs best-estimate predictions of postulated accidents for pressurized light water reactors. It is one of the few system analyse codes which use two fluid model to treat two phase problems in nuclear system. In order to use this advanced software in China and make it possible to be run in different compute systems, IBM version of TRAC-PF1 code, imported from USA National Energy Software Center, is immigrated to CDC NOS/VE system and SUN workstation. The differences in computer languages from IBM 370 to CDC NOS/VE and to SUN workstation are modified properly. All the benchmark problems are calculated, and the results show that the immigration is successful

Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes

Energy Technology Data Exchange (ETDEWEB)

Virtanen, E.; Haapalehto, T. [Lappeenranta Univ. of Technology, Lappeenranta (Finland); Kouhia, J. [VTT Energy, Nuclear Energy, Lappeenranta (Finland)

1995-09-01

Three experiments were conducted to study the behavior of the new horizontal steam generator construction of the PACTEL test facility. In the experiments the secondary side coolant level was reduced stepwise. The experiments were calculated with two computer codes RELAP5/MOD3.1 and APROS version 2.11. A similar nodalization scheme was used for both codes to that the results may be compared. Only the steam generator was modelled and the rest of the facility was given as a boundary condition. The results show that both codes calculate well the behaviour of the primary side of the steam generator. On the secondary side both codes calculate lower steam temperatures in the upper part of the heat exchange tube bundle than was measured in the experiments.

Repercusiones de la salud bucal sobre calidad de vida por ciclo vital individual

Directory of Open Access Journals (Sweden)

Iván Porto Puerta

2017-07-01

Full Text Available La calidad de vida re ere ser un tema muy debatido y estudiado, por ser el objetivo nal básico de la salud pública. Diversas investigaciones reportan su relación con el estado de salud personal apareciendo el concepto Calidad de vida relacionada con la Salud (CVRS y a su vez se encuentran relaciones más especí cas que reportan como alteraciones en diferentes sistemas y órganos del cuerpo como la boca, impactan en ella, apareciendo también el concepto de Calidad de vida relacionada con la Salud Bucal (CVRSB. El impacto de la CVRSB ha sido estudiado principalmente en adultos mayores pero solo a través de estos últimos años se ha estudiado en diferentes etapas de la vida y poco se dispone de manera conjunta de la evolución de este concepto a través de las etapas de la vida. Objetivo. Identi car principales afecciones bucales y sus repercusiones sobre la CVRSB por cada etapa del ciclo vital individual (CVI. Metodología. Se realizó una revisión sistemática, a través de buscadores Med-line, Pubmed, Scielo, Scopus, Latin index, Redalyc y Google académico seleccionando artículos de investigación originales, casos clínicos y revisiones realizadas en español, francés e inglés. Resultados. En las primeras etapas de la vida la caries dental corresponde a la enfermedad bucal que más impacta sobre la Calidad de vida, por otro lado las limitaciones funcionales, tales como comer, dormir y hablar son las repercusiones más comprometidas; a partir de la adolescencia hasta el nal de la vida, una inadecuada estética dento-facial representa la afección que más compromete CVRSB generando así, alteraciones psicosociales tales como depresión, ansiedad y aislamiento. Conclusiones. El impacto de las diferentes afecciones bucales sobre la CVRSB cambia a través del CVI por las diferentes percepciones y prioridades propias de cada etapa y prevalencia de las enfermedades bucales. Estos resultados re ejan un gran

Low Computational Complexity Network Coding For Mobile Networks

DEFF Research Database (Denmark)

Heide, Janus

2012-01-01

Network Coding (NC) is a technique that can provide benefits in many types of networks, some examples from wireless networks are: In relay networks, either the physical or the data link layer, to reduce the number of transmissions. In reliable multicast, to reduce the amount of signaling and enable......-flow coding technique. One of the key challenges of this technique is its inherent computational complexity which can lead to high computational load and energy consumption in particular on the mobile platforms that are the target platform in this work. To increase the coding throughput several...

Continuous Materiality: Through a Hierarchy of Computational Codes

Directory of Open Access Journals (Sweden)

Jichen Zhu

2008-01-01

Full Text Available The legacy of Cartesian dualism inherent in linguistic theory deeply influences current views on the relation between natural language, computer code, and the physical world. However, the oversimplified distinction between mind and body falls short of capturing the complex interaction between the material and the immaterial. In this paper, we posit a hierarchy of codes to delineate a wide spectrum of continuous materiality. Our research suggests that diagrams in architecture provide a valuable analog for approaching computer code in emergent digital systems. After commenting on ways that Cartesian dualism continues to haunt discussions of code, we turn our attention to diagrams and design morphology. Finally we notice the implications a material understanding of code bears for further research on the relation between human cognition and digital code. Our discussion concludes by noticing several areas that we have projected for ongoing research.

Computer code SICHTA-85/MOD 1 for thermohydraulic and mechanical modelling of WWER fuel channel behaviour during LOCA and comparison with original version of the SICHTA code

International Nuclear Information System (INIS)

Bujan, A.; Adamik, V.; Misak, J.

1986-01-01

A brief description is presented of the expansion of the SICHTA-83 computer code for the analysis of the thermal history of the fuel channel for large LOCAs by modelling the mechanical behaviour of fuel element cladding. The new version of the code has a more detailed treatment of heat transfer in the fuel-cladding gap because it also respects the mechanical (plastic) deformations of the cladding and the fuel-cladding interaction (magnitude of contact pressure). Also respected is the change in pressure of the gas filling of the fuel element, the mechanical criterion is considered of a failure of the cladding and the degree is considered of the blockage of the through-flow cross section for coolant flow in the fuel channel. The LOCA WWER-440 model computation provides a comparison of the new SICHTA-85/MOD 1 code with the results of the original 83 version of SICHTA. (author)

Experiences of family members regarding the oral health care of children Experiencias del familiar en relación al cuidado con la salud bucal de niños Experiências do familiar em relação ao cuidado com a saúde bucal de crianças

Directory of Open Access Journals (Sweden)

Célia Mara Garcia de Lima

2011-02-01

Full Text Available The aim of this study was to comprehend the experiences of family members regarding the oral health care of children. This was a qualitative study, conducted in 2007, in the health district of Ribeirão Preto, with 12 caregivers. The theoretical framework of vulnerability and the hermeneutical perspective were used. Three empirical categories were established: the meanings of oral health care, in search of the causes and prevention of oral diseases, and the reality of oral health services. Among other potentiating factors of infantile vulnerability to oral diseases, the overvaluation of biological causality, of high complexity care and of esthetic dentistry emerged, and among the protective factors, the valorization of popular knowledge and the integration of professional actions and knowledge were observed. This study indicates the necessity for a review of prevention and oral health promotion strategies and provides elements to assist health services to reorganize oral health care for children.Este estudio objetivó verificar la comprensión de las experiencias de los familiares en relación al cuidado con la salud bucal de los niños. Es un estudio cualitativo, realizado en 2007, en un distrito de salud del municipio de Ribeirao Preto-SP, con 12 cuidadores. Se utilizó el referencial teórico de la vulnerabilidad y la perspectiva hermenéutica. Tres categorías empíricas fueron elaboradas: los significados del cuidado con la salud bucal, en busca de las causas y de la prevención de daños bucales, y la realidad de los servicios de salud bucal. Entre otros elementos potencializadores de la vulnerabilidad infantil a los daños bucales, emergieron la supervalorización de la causalidad biológica, la atención de alta complejidad y la odontología estética; y, entre los protectores, la valorización de la sabiduría popular y la integración de acciones y conocimientos profesionales. Se señala que debe ser efectuada la revisión de las

Present state of the SOURCES computer code

International Nuclear Information System (INIS)

Shores, Erik F.

2002-01-01

In various stages of development for over two decades, the SOURCES computer code continues to calculate neutron production rates and spectra from four types of problems: homogeneous media, two-region interfaces, three-region interfaces and that of a monoenergetic alpha particle beam incident on a slab of target material. Graduate work at the University of Missouri - Rolla, in addition to user feedback from a tutorial course, provided the impetus for a variety of code improvements. Recently upgraded to version 4B, initial modifications to SOURCES focused on updates to the 'tape5' decay data library. Shortly thereafter, efforts focused on development of a graphical user interface for the code. This paper documents the Los Alamos SOURCES Tape1 Creator and Library Link (LASTCALL) and describes additional library modifications in more detail. Minor improvements and planned enhancements are discussed.

Holonomic surface codes for fault-tolerant quantum computation

Science.gov (United States)

Zhang, Jiang; Devitt, Simon J.; You, J. Q.; Nori, Franco

2018-02-01

Surface codes can protect quantum information stored in qubits from local errors as long as the per-operation error rate is below a certain threshold. Here we propose holonomic surface codes by harnessing the quantum holonomy of the system. In our scheme, the holonomic gates are built via auxiliary qubits rather than the auxiliary levels in multilevel systems used in conventional holonomic quantum computation. The key advantage of our approach is that the auxiliary qubits are in their ground state before and after each gate operation, so they are not involved in the operation cycles of surface codes. This provides an advantageous way to implement surface codes for fault-tolerant quantum computation.

Epidemiologia e saúde bucal coletiva: um caminhar compartilhado Epidemiology and public health dentistry: a shared walkway

Directory of Open Access Journals (Sweden)

Angelo Giuseppe Roncalli

2006-03-01

Full Text Available A saúde bucal coletiva, na medida em que surge como um modo de trazer a saúde bucal para o SUS (e vice-versa, tem, na epidemiologia, um de seus mais contundentes aliados. Este artigo discute o modo como se deu esse caminhar, trilhado compartilhadamente, entre a saúde bucal coletiva e a epidemiologia. Analisa, inicialmente, os esforços na tentativa de estabelecer modelos metodológicos para pesquisas transversais, bem como a possibilidade da construção de uma base de dados nacional. Num segundo momento, discute-se como esse conjunto de conhecimentos tem se corporificado em uma produção científica qualificada e compartilhada com seus pares, refletindo sobre o modo como este processo vem contribuindo para a consolidação do campo da saúde bucal coletiva. Percebe-se que este caminhar compartilhado esteve e está condicionado pela conjuntura política que, em momentos distintos, proporcionou o crescimento da saúde bucal coletiva. A epidemiologia em saúde bucal, ao mesmo tempo em que se consolida como área de conhecimento no plano da produção científica no Brasil, articula-se com este movimento, proporcionando, de um lado, uma ferramenta que aproxima os modelos assistenciais em saúde bucal do ideário do SUS; e, de outro, aprofunda as discussões a respeito dos determinantes biopsicossociais das doenças bucais.The public health dentistry is a way to bring oral health to Brazilian National Health System (SUS and vice-versa. Thus, the epidemiology, in this context, it is one of the most important allies. In this article we intend to discuss the "shared walkway" between epidemiology and public health dentistry, through two views: first, we analyzed the efforts to establish methodological models for oral health sectional studies and the possibilities to construct a national data base. Second, we discussed how this knowledge has been transformed in a qualified scientific production presented in meetings and papers, which reflects, at the

Multi keno-VAX a modified version of the reactor computer code Multi keno-2

Energy Technology Data Exchange (ETDEWEB)

Imam, M [National center for nuclear safety and radiation control, atomic energy authority, Cairo, (Egypt)

1995-10-01

The reactor computer code Multi keno-2 is developed in Japan from the original Monte Carlo Keno-IV. By applications of this code on some real problems, fatal errors were detected. These errors are related to the restart option in the code. The restart option is essential for solving time-consuming problems on mini-computer like VAX-6320. These errors were corrected and other modifications were carried out in the code. Because of these modifications new input data description was written for the code. Thus a new VAX/VMS version for the program was developed which is also adaptable for mini-mainframes. This new developed program, called Multi keno-VAX is accepted in the Nea-IAEA data bank and is added to its international computer codes library. 1 fig.

Multi keno-VAX a modified version of the reactor computer code Multi keno-2

International Nuclear Information System (INIS)

Imam, M.

1995-01-01

The reactor computer code Multi keno-2 is developed in Japan from the original Monte Carlo Keno-IV. By applications of this code on some real problems, fatal errors were detected. These errors are related to the restart option in the code. The restart option is essential for solving time-consuming problems on mini-computer like VAX-6320. These errors were corrected and other modifications were carried out in the code. Because of these modifications new input data description was written for the code. Thus a new VAX/VMS version for the program was developed which is also adaptable for mini-mainframes. This new developed program, called Multi keno-VAX is accepted in the Nea-IAEA data bank and is added to its international computer codes library. 1 fig

Material educativo computarizado sobre salud bucal diseñado para sordos. Experiencia en Mérida, Venezuela

OpenAIRE

Perdomo, Bexi J.; Dávila, Deysimar; Flores, Marco; Morales, Oscar Alberto

2014-01-01

Artículo publicado en la Revista Multiciencias Vol. 14 Nº 3, 2014 (289 - 296). ISSN 1317-2255 / Dep. legal pp. 200002FA828. Universidad del Zulia (LUZ) - Núcleo Punto Fijo Las comunidades con diversidad funcional, dentro de las cuales se encuentra la Comunidad Sorda, tienden a verse en desventaja al momento de tener acceso a información sobre salud bucal.Enese contexto surgió un proyecto amplio orientado a la generación recursos educativos en salud bucal para poblaciones con diversidad fun...

La prótesis bucal como causante del carcinoma espinocelular oral

OpenAIRE

Caballero Herrera, Rafael; Bru de Sala Oms, Carlos

1998-01-01

La aparición de cáncer bucal está vinculada a múltiples factores de riesgo. En este artículo queremos exponer como uno de ellos la úlcera crónica producida por las prótesis dentales removibles o fijas.

Computer Security: is your code sane?

CERN Multimedia

Stefan Lueders, Computer Security Team

2015-01-01

How many of us write code? Software? Programs? Scripts? How many of us are properly trained in this and how well do we do it? Do we write functional, clean and correct code, without flaws, bugs and vulnerabilities*? In other words: are our codes sane?   Figuring out weaknesses is not that easy (see our quiz in an earlier Bulletin article). Therefore, in order to improve the sanity of your code, prevent common pit-falls, and avoid the bugs and vulnerabilities that can crash your code, or – worse – that can be misused and exploited by attackers, the CERN Computer Security team has reviewed its recommendations for checking the security compliance of your code. “Static Code Analysers” are stand-alone programs that can be run on top of your software stack, regardless of whether it uses Java, C/C++, Perl, PHP, Python, etc. These analysers identify weaknesses and inconsistencies including: employing undeclared variables; expressions resu...

Computer codes for shaping the magnetic field of the JINR phasotron

International Nuclear Information System (INIS)

Zaplatin, N.L.; Morozov, N.A.

1983-01-01

The computer codes providing for the shaping the magnetic field of the JINR high current phasotron are presented. Using these codes the control for the magnetic field mapping was realized in on- or off-line regimes. Then these field parameters were calculated and ferromagnetic correcting elements and trim coils setting were chosen. Some computer codes were realised for the magnetic field horizontal component measurements. The data are presented on some codes possibilities. The codes were used on the EC-1010 and the CDC-6500 computers

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4

Energy Technology Data Exchange (ETDEWEB)

Greene, N.M.; Petrie, L.M.; Westfall, R.M.; Bucholz, J.A.; Hermann, O.W.; Fraley, S.K. [Oak Ridge National Lab., TN (United States)

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries.

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation. Functional modules F1--F8 -- Volume 2, Part 1, Revision 4

International Nuclear Information System (INIS)

Greene, N.M.; Petrie, L.M.; Westfall, R.M.; Bucholz, J.A.; Hermann, O.W.; Fraley, S.K.

1995-04-01

SCALE--a modular code system for Standardized Computer Analyses Licensing Evaluation--has been developed by Oak Ridge National Laboratory at the request of the US Nuclear Regulatory Commission. The SCALE system utilizes well-established computer codes and methods within standard analysis sequences that (1) allow an input format designed for the occasional user and/or novice, (2) automate the data processing and coupling between modules, and (3) provide accurate and reliable results. System development has been directed at problem-dependent cross-section processing and analysis of criticality safety, shielding, heat transfer, and depletion/decay problems. Since the initial release of SCALE in 1980, the code system has been heavily used for evaluation of nuclear fuel facility and package designs. This revision documents Version 4.2 of the system. The manual is divided into three volumes: Volume 1--for the control module documentation; Volume 2--for functional module documentation; and Volume 3--for documentation of the data libraries and subroutine libraries

COMPUTATION FORMAT computer codes X4TOC4 and PLOTC4. Implementing and Testing on a Personal Computer

International Nuclear Information System (INIS)

McLaughlin, P.K.

1987-05-01

This document describes the contents of the diskette containing the COMPUTATION FORMAT codes X4TOC4 and PLOTC4 by D.E. Cullen, and example data for use in implementing and testing these codes on a Personal Computer of the type IBM-PC/AT. Upon request the codes are available from the IAEA Nuclear Data Section, free of charge, on a single diskette. (author)

Analysis of steam generator loss-of-feedwater experiments with APROS and RELAP5/MOD3.1 computer codes

International Nuclear Information System (INIS)

Virtanen, E.; Haapalehto, T.; Kouhia, J.

1997-01-01

Three experiments were conducted to study the behaviour of the new horizontal steam generator construction of the PACTEL test facility. In the experiments the secondary side coolant level was reduced stepwise. The experiments were calculated with two computer codes RELAP5/MOD3.1 and APROS version 2.11. A similar nodalization scheme was used for both codes so that the results may be compared. Only the steam generator was modeled and the rest of the facility was given as a boundary condition. The results show that both codes calculate well the behaviour of the primary side of the steam generator. On the secondary side both codes calculate lower steam temperatures in the upper part of the heat exchange tube bundle than was measured in the experiments. (orig.)

TASS code topical report. V.1 TASS code technical manual

International Nuclear Information System (INIS)

Sim, Suk K.; Chang, W. P.; Kim, K. D.; Kim, H. C.; Yoon, H. Y.

1997-02-01

TASS 1.0 code has been developed at KAERI for the initial and reload non-LOCA safety analysis for the operating PWRs as well as the PWRs under construction in Korea. TASS code will replace various vendor's non-LOCA safety analysis codes currently used for the Westinghouse and ABB-CE type PWRs in Korea. This can be achieved through TASS code input modifications specific to each reactor type. The TASS code can be run interactively through the keyboard operation. A simimodular configuration used in developing the TASS code enables the user easily implement new models. TASS code has been programmed using FORTRAN77 which makes it easy to install and port for different computer environments. The TASS code can be utilized for the steady state simulation as well as the non-LOCA transient simulations such as power excursions, reactor coolant pump trips, load rejections, loss of feedwater, steam line breaks, steam generator tube ruptures, rod withdrawal and drop, and anticipated transients without scram (ATWS). The malfunctions of the control systems, components, operator actions and the transients caused by the malfunctions can be easily simulated using the TASS code. This technical report describes the TASS 1.0 code models including reactor thermal hydraulic, reactor core and control models. This TASS code models including reactor thermal hydraulic, reactor core and control models. This TASS code technical manual has been prepared as a part of the TASS code manual which includes TASS code user's manual and TASS code validation report, and will be submitted to the regulatory body as a TASS code topical report for a licensing non-LOCA safety analysis for the Westinghouse and ABB-CE type PWRs operating and under construction in Korea. (author). 42 refs., 29 tabs., 32 figs

SIMCRI: a simple computer code for calculating nuclear criticality parameters

International Nuclear Information System (INIS)

Nakamaru, Shou-ichi; Sugawara, Nobuhiko; Naito, Yoshitaka; Katakura, Jun-ichi; Okuno, Hiroshi.

1986-03-01

This is a user's manual for a simple criticality calculation code SIMCRI. The code has been developed to facilitate criticality calculation on a single unit of nuclear fuel. SIMCRI makes an extensive survey with a little computing time. Cross section library MGCL for SIMCRI is the same one for the Monte Carlo criticality code KENOIV; it is, therefore, easy to compare the results of the two codes. SIMCRI solves eigenvalue problems and fixed source problems based on the one space point B 1 equation. The results include infinite and effective multiplication factor, critical buckling, migration area, diffusion coefficient and so on. SIMCRI is comprised in the criticality safety evaluation code system JACS. (author)

Program EPICSHOW. A computer code to allow interactive viewing of the EPIC data libraries (Version 98-1). Summary documentation

International Nuclear Information System (INIS)

Pronyaev, V.G.; McLaughlin, P.K.

1999-01-01

EPICSHOW (Electron Photon Interactive Code - Show Data) is an interactive graphics code that allows users to view and interact with neutron, photon, electron and light charged particle data. Besides on screen graphics the code provides hard copy in the form of tabulated listings and Postscript output files. The code has been implemented on UNIX, IBM-PC, Power MAC, and even Laptop computers. It should be relatively easy to use it on almost any computer. All of the data included in this system is based on the Lawrence Livermore National Laboratory Databases and the neutron and photon data is used in the TART97 Monte Carlo transport code system. (author)

Use of computer codes to improve nuclear power plant operation

International Nuclear Information System (INIS)

Misak, J.; Polak, V.; Filo, J.; Gatas, J.

1985-01-01

For safety and economic reasons, the scope for carrying out experiments on operational nuclear power plants (NPPs) is very limited and any changes in technical equipment and operating parameters or conditions have to be supported by theoretical calculations. In the Nuclear Power Plant Scientific Research Institute (NIIAEhS), computer codes are systematically used to analyse actual operating events, assess safety aspects of changes in equipment and operating conditions, optimize the conditions, preparation and analysis of NPP startup trials and review and amend operating instructions. In addition, calculation codes are gradually being introduced into power plant computer systems to perform real time processing of the parameters being measured. The paper describes a number of specific examples of the use of calculation codes for the thermohydraulic analysis of operating and accident conditions aimed at improving the operation of WWER-440 units at the Jaslovske Bohunice V-1 and V-2 nuclear power plants. These examples confirm that computer calculations are an effective way of solving operating problems and of further increasing the level of safety and economic efficiency of NPP operation. (author)

ACDOS1: a computer code to calculate dose rates from neutron activation of neutral beamlines and other fusion-reactor components

International Nuclear Information System (INIS)

Keney, G.S.

1981-08-01

A computer code has been written to calculate neutron induced activation of neutral-beam injector components and the corresponding dose rates as a function of geometry, component composition, and time after shutdown. The code, ACDOS1, was written in FORTRAN IV to calculate both activity and dose rates for up to 30 target nuclides and 50 neutron groups. Sufficient versatility has also been incorporated into the code to make it applicable to a variety of general activation problems due to neutrons of energy less than 20 MeV

Theoretical Atomic Physics code development IV: LINES, A code for computing atomic line spectra

International Nuclear Information System (INIS)

Abdallah, J. Jr.; Clark, R.E.H.

1988-12-01

A new computer program, LINES, has been developed for simulating atomic line emission and absorption spectra using the accurate fine structure energy levels and transition strengths calculated by the (CATS) Cowan Atomic Structure code. Population distributions for the ion stages are obtained in LINES by using the Local Thermodynamic Equilibrium (LTE) model. LINES is also useful for displaying the pertinent atomic data generated by CATS. This report describes the use of LINES. Both CATS and LINES are part of the Theoretical Atomic PhysicS (TAPS) code development effort at Los Alamos. 11 refs., 9 figs., 1 tab

User manual of FRAPCON-I computer code

International Nuclear Information System (INIS)

Chia, C.T.

1985-11-01

The manual for using the FRAPCON-I code implanted by Reactor Department of Brazilian-CNEN to convert IBM FORTRAN in FORTRAN 77 of Honeywell Bull computer is presented. The FRAPCON-I code describes the behaviour of fuel rods of PWR type reactors at stationary state during long periods of burnup. (M.C.K.)

Some neutronics and thermal-hydraulics codes for reactor analysis using personal computers

International Nuclear Information System (INIS)

Woodruff, W.L.

1990-01-01

Some neutronics and thermal-hydraulics codes formerly available only for main frame computers may now be run on personal computers. Brief descriptions of the codes are provided. Running times for some of the codes are compared for an assortment of personal and main frame computers. With some limitations in detail, personal computer versions of the codes can be used to solve many problems of interest in reactor analyses at very modest costs. 11 refs., 4 tabs

Coesão familiar associada à saúde bucal, fatores socioeconômicos e comportamentos em saúde

Directory of Open Access Journals (Sweden)

Luale Leão Ferreira

2013-08-01

Full Text Available Pesquisas sobre saúde geral têm relacionado coesão familiar a fatores socioeconômicos e comportamentais. O objetivo deste estudo foi investigar a associação entre coesão familiar e fatores socioeconômicos, comportamentais e de saúde bucal. Este foi um estudo transversal com amostra por conglomerados em dois estágios. A amostra randomizada de 524 adolescentes era proveniente de escolas públicas da cidade de Piracicaba-SP. As variáveis foram avaliadas por questionários autoaplicáveis e os dados de saúde bucal, pelos índices CPO e CPI. A coesão familiar percebida pelo adolescente foi avaliada por meio da escala de adaptabilidade e coesão familiar. Análise univariada e regressão logística multinominal mostraram que adolescentes com baixa coesão familiar apresentaram mais chance de terem baixa renda (OR 2,28 IC95% 1,14-4,55, presença de cárie (OR 2,23 IC95% 1,21-4,09 e baixa frequência de escovação diária (OR 1,91 IC95% 1,03-3,54. Adolescentes com alta coesão familiar apresentaram mais chance que adolescentes com média coesão de terem alta renda e fator de proteção contra o hábito de tabagismo. Desta forma, a coesão familiar percebida pelo adolescente associou-se com variáveis comportamentais, socioeconômicas e de saúde bucal, indicando a importância de uma abordagem integral da saúde do paciente.

FLAME: A finite element computer code for contaminant transport n variably-saturated media

International Nuclear Information System (INIS)

Baca, R.G.; Magnuson, S.O.

1992-06-01

A numerical model was developed for use in performance assessment studies at the INEL. The numerical model referred to as the FLAME computer code, is designed to simulate subsurface contaminant transport in a variably-saturated media. The code can be applied to model two-dimensional contaminant transport in an and site vadose zone or in an unconfined aquifer. In addition, the code has the capability to describe transport processes in a porous media with discrete fractures. This report presents the following: description of the conceptual framework and mathematical theory, derivations of the finite element techniques and algorithms, computational examples that illustrate the capability of the code, and input instructions for the general use of the code. The development of the FLAME computer code is aimed at providing environmental scientists at the INEL with a predictive tool for the subsurface water pathway. This numerical model is expected to be widely used in performance assessments for: (1) the Remedial Investigation/Feasibility Study process and (2) compliance studies required by the US Department of energy Order 5820.2A

FLAME: A finite element computer code for contaminant transport n variably-saturated media

Energy Technology Data Exchange (ETDEWEB)

Baca, R.G.; Magnuson, S.O.

1992-06-01

A numerical model was developed for use in performance assessment studies at the INEL. The numerical model referred to as the FLAME computer code, is designed to simulate subsurface contaminant transport in a variably-saturated media. The code can be applied to model two-dimensional contaminant transport in an and site vadose zone or in an unconfined aquifer. In addition, the code has the capability to describe transport processes in a porous media with discrete fractures. This report presents the following: description of the conceptual framework and mathematical theory, derivations of the finite element techniques and algorithms, computational examples that illustrate the capability of the code, and input instructions for the general use of the code. The development of the FLAME computer code is aimed at providing environmental scientists at the INEL with a predictive tool for the subsurface water pathway. This numerical model is expected to be widely used in performance assessments for: (1) the Remedial Investigation/Feasibility Study process and (2) compliance studies required by the US Department of energy Order 5820.2A.

Quantum computation with topological codes from qubit to topological fault-tolerance

CERN Document Server

Fujii, Keisuke

2015-01-01

This book presents a self-consistent review of quantum computation with topological quantum codes. The book covers everything required to understand topological fault-tolerant quantum computation, ranging from the definition of the surface code to topological quantum error correction and topological fault-tolerant operations. The underlying basic concepts and powerful tools, such as universal quantum computation, quantum algorithms, stabilizer formalism, and measurement-based quantum computation, are also introduced in a self-consistent way. The interdisciplinary fields between quantum information and other fields of physics such as condensed matter physics and statistical physics are also explored in terms of the topological quantum codes. This book thus provides the first comprehensive description of the whole picture of topological quantum codes and quantum computation with them.

Rede de atencao a saude bucal: organizacao em municipios de grande porte de Santa Catarina, Brasil

Directory of Open Access Journals (Sweden)

Heloisa Godoi

2014-02-01

Full Text Available O estudo objetivou analisar a rede de atenção à saúde bucal em municípios com mais de 100 mil habitantes de Santa Catarina, Brasil, pela identificação e integração de seus elementos constitutivos. Dados primários foram obtidos por meio da aplicação de questionário aos gestores municipais de saúde bucal. Dados secundários foram coletados em bases de dados do SUS e fornecidos pelas Secretarias Municipais e Estadual de Saúde. Os municípios ofertam serviços de saúde bucal em todos os níveis de atenção, mas encontram-se em distintos estágios de implementação da rede. Também realizam algumas ações para consolidação desta, como inserção de ferramentas para integração dos serviços de atenção básica aos especializados e reorientação da atenção básica, como coordenadora da rede. As limitações incluem dificuldade em definir a população da rede de acordo com critérios epidemiológicos, fragilidade dos sistemas logísticos e de governança, além da necessidade de ampliação das equipes de saúde bucal na Estratégia Saúde da Família, operando segundo princípios de vigilância à saúde.

A importância do médico pediatra na promoção da saúde bucal

Directory of Open Access Journals (Sweden)

Mariângela M. S. Schalka

1996-04-01

Full Text Available Objetivou-se realizar avaliação da conduta preventiva em relação à saúde bucal exercida por médicos pediatras da cidade de São José dos Campos-SP, Brasil. A análise foi feita através das respostas a um questionário descritivo entregue a 85 pediatras da cidade. Obteve-se um retorno de 48 (56,4%. O questionário abordou aspectos relativos a amamentação, dieta, higiene bucal, uso da chupeta e do flúor e encaminhamento ao dentista. A análise dos resultados mostrou que a freqüência das orientações a respeito dessas condutas preventivas aos pacientes foi baixa. Concluiu-se ser necessário um esforço maior dos profissionais, médicos e dentistas, de promover a melhoria da saúde bucal dos pacientes infantis.

SURE: a system of computer codes for performing sensitivity/uncertainty analyses with the RELAP code

International Nuclear Information System (INIS)

Bjerke, M.A.

1983-02-01

A package of computer codes has been developed to perform a nonlinear uncertainty analysis on transient thermal-hydraulic systems which are modeled with the RELAP computer code. Using an uncertainty around the analyses of experiments in the PWR-BDHT Separate Effects Program at Oak Ridge National Laboratory. The use of FORTRAN programs running interactively on the PDP-10 computer has made the system very easy to use and provided great flexibility in the choice of processing paths. Several experiments simulating a loss-of-coolant accident in a nuclear reactor have been successfully analyzed. It has been shown that the system can be automated easily to further simplify its use and that the conversion of the entire system to a base code other than RELAP is possible

Two-phase computer codes for zero-gravity applications

International Nuclear Information System (INIS)

Krotiuk, W.J.

1986-10-01

This paper discusses the problems existing in the development of computer codes which can analyze the thermal-hydraulic behavior of two-phase fluids especially in low gravity nuclear reactors. The important phenomenon affecting fluid flow and heat transfer in reduced gravity is discussed. The applicability of using existing computer codes for space applications is assessed. Recommendations regarding the use of existing earth based fluid flow and heat transfer correlations are made and deficiencies in these correlations are identified

Neutron spectrum unfolding using computer code SAIPS

International Nuclear Information System (INIS)

Karim, S.

1999-01-01

The main objective of this project was to study the neutron energy spectrum at rabbit station-1 in Pakistan Research Reactor (PARR-I). To do so, multiple foils activation method was used to get the saturated activities. The computer code SAIPS was used to unfold the neutron spectra from the measured reaction rates. Of the three built in codes in SAIPS, only SANDI and WINDOWS were used. Contribution of thermal part of the spectra was observed to be higher than the fast one. It was found that the WINDOWS gave smooth spectra while SANDII spectra have violet oscillations in the resonance region. The uncertainties in the WINDOWS results are higher than those of SANDII. The results show reasonable agreement with the published results. (author)

Fuel burnup analysis for the Moroccan TRIGA research reactor

International Nuclear Information System (INIS)

El Bakkari, B.; El Bardouni, T.; Nacir, B.; El Younoussi, C.; Boulaich, Y.; Boukhal, H.; Zoubair, M.

2013-01-01

Highlights: ► A fuel burnup analysis of the 2 MW TRIGA MARK II Moroccan research reactor was established. ► Burnup calculations were done by means of the in-house developed burnup code BUCAL1. ► BUCAL1 uses the MCNP tallies directly in the calculation of the isotopic inventories. ► The reactor life time was found to be 3360 MW h considering full power operating conditions. ► Power factors and fluxes of the in-core irradiation positions are strongly affected by burnup. -- Abstract: The fundamental advantage and main reason to use Monte Carlo methods for burnup calculations is the possibility to generate extremely accurate burnup dependent one group cross-sections and neutron fluxes for arbitrary core and fuel geometries. Yet, a set of values determined for a material at a given position and time remains accurate only in a local region, in which neutron spectrum and flux vary weakly — and only for a limited period of time, during which changes of the local isotopic composition are minor. This paper presents the approach of fuel burnup evaluation used at the Moroccan TRIGA MARK II research reactor. The approach is essentially based upon the utilization of BUCAL1, an in-house developed burnup code. BUCAL1 is a FORTRAN computer code designed to aid in analysis, prediction, and optimization of fuel burnup performance in nuclear reactors. The code was developed to incorporate the neutron absorption reaction tally information generated directly by MCNP5 code in the calculation of fissioned or neutron-transmuted isotopes for multi-fueled regions. The fuel cycle length and changes in several core parameters such as: core excess reactivity, control rods position, fluxes at the irradiation positions, axial and radial power factors and other parameters are estimated. Besides, this study gives valuable insight into the behavior of the reactor and will ensure better utilization and operation of the reactor during its life-time and it will allow the establishment of

Quality assurance and verification of the MACCS [MELCOR Accident Consequence Code System] code, Version 1.5

International Nuclear Information System (INIS)

Dobbe, C.A.; Carlson, E.R.; Marshall, N.H.; Marwil, E.S.; Tolli, J.E.

1990-02-01

An independent quality assurance (QA) and verification of Version 1.5 of the MELCOR Accident Consequence Code System (MACCS) was performed. The QA and verification involved examination of the code and associated documentation for consistent and correct implementation of the models in an error-free FORTRAN computer code. The QA and verification was not intended to determine either the adequacy or appropriateness of the models that are used MACCS 1.5. The reviews uncovered errors which were fixed by the SNL MACCS code development staff prior to the release of MACCS 1.5. Some difficulties related to documentation improvement and code restructuring are also presented. The QA and verification process concluded that Version 1.5 of the MACCS code, within the scope and limitations process concluded that Version 1.5 of the MACCS code, within the scope and limitations of the models implemented in the code is essentially error free and ready for widespread use. 15 refs., 11 tabs

SHEAT for PC. A computer code for probabilistic seismic hazard analysis for personal computer, user's manual

International Nuclear Information System (INIS)

Yamada, Hiroyuki; Tsutsumi, Hideaki; Ebisawa, Katsumi; Suzuki, Masahide

2002-03-01

The SHEAT code developed at Japan Atomic Energy Research Institute is for probabilistic seismic hazard analysis which is one of the tasks needed for seismic Probabilistic Safety Assessment (PSA) of a nuclear power plant. At first, SHEAT was developed as the large sized computer version. In addition, a personal computer version was provided to improve operation efficiency and generality of this code in 2001. It is possible to perform the earthquake hazard analysis, display and the print functions with the Graphical User Interface. With the SHEAT for PC code, seismic hazard which is defined as an annual exceedance frequency of occurrence of earthquake ground motions at various levels of intensity at a given site is calculated by the following two steps as is done with the large sized computer. One is the modeling of earthquake generation around a site. Future earthquake generation (locations, magnitudes and frequencies of postulated earthquake) is modeled based on the historical earthquake records, active fault data and expert judgment. Another is the calculation of probabilistic seismic hazard at the site. An earthquake ground motion is calculated for each postulated earthquake using an attenuation model taking into account its standard deviation. Then the seismic hazard at the site is calculated by summing the frequencies of ground motions by all the earthquakes. This document is the user's manual of the SHEAT for PC code. It includes: (1) Outline of the code, which include overall concept, logical process, code structure, data file used and special characteristics of code, (2) Functions of subprogram and analytical models in them, (3) Guidance of input and output data, (4) Sample run result, and (5) Operational manual. (author)

A compendium of computer codes in fault tree analysis

International Nuclear Information System (INIS)

Lydell, B.

1981-03-01

In the past ten years principles and methods for a unified system reliability and safety analysis have been developed. Fault tree techniques serve as a central feature of unified system analysis, and there exists a specific discipline within system reliability concerned with the theoretical aspects of fault tree evaluation. Ever since the fault tree concept was established, computer codes have been developed for qualitative and quantitative analyses. In particular the presentation of the kinetic tree theory and the PREP-KITT code package has influenced the present use of fault trees and the development of new computer codes. This report is a compilation of some of the better known fault tree codes in use in system reliability. Numerous codes are available and new codes are continuously being developed. The report is designed to address the specific characteristics of each code listed. A review of the theoretical aspects of fault tree evaluation is presented in an introductory chapter, the purpose of which is to give a framework for the validity of the different codes. (Auth.)

Development of a computer code for thermohydraulic analysis of a heated channel in transients

International Nuclear Information System (INIS)

Jafari, J.; Kazeminejad, H.; Davilu, H.

2004-01-01

This paper discusses the thermohydraulic analysis of a heated channel of a nuclear reactor in transients by a computer code that has been developed by the writer. The considered geometry is a channel of a nuclear reactor with cylindrical or planar fuel rods. The coolant is water and flows from the outer surface of the fuel rod. To model the heat transfer in the fuel rod, two dimensional time dependent conduction equations has been solved by combination of numerical methods, O rthogonal Collocation Method in radial direction and finite difference method in axial direction . For coolant modelling the single phase time dependent energy equation has been used and solved by finite difference method . The combination of the first module that solves the conduction in the fuel rod and a second one that solved the energy balance in the coolant region constitute the computer code (Thyc-1) to analysis thermohydraulic of a heated channel in transients. The Orthogonal collocation method maintains the accuracy and computing time of conventional finite difference methods, while the computer storage is reduced by a factor of two. The same problem has been modelled by RELAP5/M3 system code to asses the validity of the Thyc-1 code. The good agreement of the results qualifies the developed code

Computer code ANISN multiplying media and shielding calculation II. Code description (input/output)

International Nuclear Information System (INIS)

Maiorino, J.R.

1990-01-01

The user manual of the ANISN computer code describing input and output subroutines is presented. ANISN code was developed to solve one-dimensional transport equation for neutron or gamma rays in slab, sphere or cylinder geometry with general anisotropic scattering. The solution technique is the discrete ordinate method. (M.C.K.)

Evaluation of the FRAPCON-3 Computer Code

Energy Technology Data Exchange (ETDEWEB)

Jernkvist, Lars Olof; Massih, Ali [Quantum Technologies AB, Uppsala (Sweden)

2002-03-01

The FRAPCON-3 computer code has been evaluated with respect to its applicability, modeling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under steady-state operational conditions and moderate power excursions. It is applicable to both boiling- and pressurized water reactor fuel rods with UO{sub 2} fuel, ranging up to about 65 MWd/kg U in rod average burnup. The models and numerical methods in FRAPCON-3 are relatively simple, which makes the code transparent and also fairly easy to modify and extend for the user. The fundamental equations for heat transfer, structural analysis and fuel fission gas release are solved in one-dimensional (radial) and stationary (time-independent) form, and interaction between axial segments of the rod is confined to calculations of coolant axial flow and rod internal gas pressure. The code is fairly easy to use; fuel rod design data and time histories of fuel rod power and coolant inlet conditions are input via a single text file, and the corresponding calculated variation with time of important fuel rod parameters are printed to a single output file in textual form. The results can also be presented in graphical form through an interface to the general graphics program xmgr. FRAPCON-3 also provides the possibility to export calculated results to the transient fuel rod analysis code FRAPTRAN, where the data can be used as burnup-dependent initial conditions to a postulated transient. Most of the source code to FRAPCON-3 is written in Fortran-IV, which is an archaic, non-standard dialect of the Fortran programming language. Since Fortran-IV is not accepted by all compilers for the latest standard of the language, Fortran-95, there is a risk that the source code must be partly rewritten in the future. Documentation of the code comprises (i) a general code description, which briefly presents models

Evaluation of the FRAPCON-3 Computer Code

International Nuclear Information System (INIS)

Jernkvist, Lars Olof; Massih, Ali

2002-03-01

The FRAPCON-3 computer code has been evaluated with respect to its applicability, modeling capability, user friendliness, source code structure and supporting experimental database. The code is intended for thermo-mechanical analyses of light water reactor nuclear fuel rods under steady-state operational conditions and moderate power excursions. It is applicable to both boiling- and pressurized water reactor fuel rods with UO 2 fuel, ranging up to about 65 MWd/kg U in rod average burnup. The models and numerical methods in FRAPCON-3 are relatively simple, which makes the code transparent and also fairly easy to modify and extend for the user. The fundamental equations for heat transfer, structural analysis and fuel fission gas release are solved in one-dimensional (radial) and stationary (time-independent) form, and interaction between axial segments of the rod is confined to calculations of coolant axial flow and rod internal gas pressure. The code is fairly easy to use; fuel rod design data and time histories of fuel rod power and coolant inlet conditions are input via a single text file, and the corresponding calculated variation with time of important fuel rod parameters are printed to a single output file in textual form. The results can also be presented in graphical form through an interface to the general graphics program xmgr. FRAPCON-3 also provides the possibility to export calculated results to the transient fuel rod analysis code FRAPTRAN, where the data can be used as burnup-dependent initial conditions to a postulated transient. Most of the source code to FRAPCON-3 is written in Fortran-IV, which is an archaic, non-standard dialect of the Fortran programming language. Since Fortran-IV is not accepted by all compilers for the latest standard of the language, Fortran-95, there is a risk that the source code must be partly rewritten in the future. Documentation of the code comprises (i) a general code description, which briefly presents models

Model of nuclear reactor type VVER-1000/V-320 built by computer code ATHLET-CD

International Nuclear Information System (INIS)

Georgiev, Yoto; Filipov, Kalin; Velev, Vladimir

2014-01-01

A model of nuclear reactor type VVER-1000 V-320 developed for computer code ATHLET-CD2.1A is presented. Validation of the has been made, in the analysis of the station blackout scenario with LOCA on fourth cold leg is shown. As the calculation has been completed, the results are checked through comparison with the results from the computer codes ATHLET-2.1A, ASTEC-2.1 and RELAP5mod3.2

SALE: Safeguards Analytical Laboratory Evaluation computer code

International Nuclear Information System (INIS)

Carroll, D.J.; Bush, W.J.; Dolan, C.A.

1976-09-01

The Safeguards Analytical Laboratory Evaluation (SALE) program implements an industry-wide quality control and evaluation system aimed at identifying and reducing analytical chemical measurement errors. Samples of well-characterized materials are distributed to laboratory participants at periodic intervals for determination of uranium or plutonium concentration and isotopic distributions. The results of these determinations are statistically-evaluated, and each participant is informed of the accuracy and precision of his results in a timely manner. The SALE computer code which produces the report is designed to facilitate rapid transmission of this information in order that meaningful quality control will be provided. Various statistical techniques comprise the output of the SALE computer code. Assuming an unbalanced nested design, an analysis of variance is performed in subroutine NEST resulting in a test of significance for time and analyst effects. A trend test is performed in subroutine TREND. Microfilm plots are obtained from subroutine CUMPLT. Within-laboratory standard deviations are calculated in the main program or subroutine VAREST, and between-laboratory standard deviations are calculated in SBLV. Other statistical tests are also performed. Up to 1,500 pieces of data for each nuclear material sampled by 75 (or fewer) laboratories may be analyzed with this code. The input deck necessary to run the program is shown, and input parameters are discussed in detail. Printed output and microfilm plot output are described. Output from a typical SALE run is included as a sample problem

A DOE Computer Code Toolbox: Issues and Opportunities

International Nuclear Information System (INIS)

Vincent, A.M. III

2001-01-01

The initial activities of a Department of Energy (DOE) Safety Analysis Software Group to establish a Safety Analysis Toolbox of computer models are discussed. The toolbox shall be a DOE Complex repository of verified and validated computer models that are configuration-controlled and made available for specific accident analysis applications. The toolbox concept was recommended by the Defense Nuclear Facilities Safety Board staff as a mechanism to partially address Software Quality Assurance issues. Toolbox candidate codes have been identified through review of a DOE Survey of Software practices and processes, and through consideration of earlier findings of the Accident Phenomenology and Consequence Evaluation program sponsored by the DOE National Nuclear Security Agency/Office of Defense Programs. Planning is described to collect these high-use codes, apply tailored SQA specific to the individual codes, and implement the software toolbox concept. While issues exist such as resource allocation and the interface among code developers, code users, and toolbox maintainers, significant benefits can be achieved through a centralized toolbox and subsequent standardized applications

Computer code for qualitative analysis of gamma-ray spectra

International Nuclear Information System (INIS)

Yule, H.P.

1979-01-01

Computer code QLN1 provides complete analysis of gamma-ray spectra observed with Ge(Li) detectors and is used at both the National Bureau of Standards and the Environmental Protection Agency. It locates peaks, resolves multiplets, identifies component radioisotopes, and computes quantitative results. The qualitative-analysis (or component identification) algorithms feature thorough, self-correcting steps which provide accurate isotope identification in spite of errors in peak centroids, energy calibration, and other typical problems. The qualitative-analysis algorithm is described in this paper

Salud bucal en nativos Maká de 12 a 15 años, Mariano Roque Alonso, Paraguay

Directory of Open Access Journals (Sweden)

Claudia Patricia Burgos Florentín

2016-01-01

Full Text Available Objetivo: describir el estado de salud bucal en nativos Maká de 12 a 15 años de edad que residen en la ciudad de Mariano Roque Alonso, Paraguay. Materiales y métodos: Estudio observacional descriptivo de corte transversal en 59 niños de 12 a 15 años, evaluados por medio de la inspección oral y la aplicación de un cuestionario para indagar aspectos relativos a factores de riesgo presentes. Resultados: El Índice CPO-D fue de 10.5, se pudo constatar la ausencia del componente de piezas obturadas. El 94.9% presentó gingivitis leve. Se halló una prevalencia de 30.5% de Fluorosis y lesiones no cariosas en un 11% de la población examinada. Conclusión: los resultados de los índices obtenidos para medir las condiciones bucales se encuentran por encima de la meta establecida por la OMS; demuestrando un importante deterioro en el estado bucal de los niños nativos Maká.

Utilization of KENO-IV computer code with HANSEN-ROACH library

International Nuclear Information System (INIS)

Lima Barros, M. de; Vellozo, S.O.

1982-01-01

Several analysis with KENO-IV computer code, which is based in the Monte Carlo method, and the cross section library HANSEN-ROACH, were done, aiming to present the more convenient form to execute criticality calculations with this computer code and this cross sections. (E.G.) [pt

La paciente embarazada: repercusión en la cavidad bucal y consideraciones respecto al tratamiento odontológico

OpenAIRE

Bueno Lafuente, Susana; Berini Aytés, Leonardo; Gay Escoda, Cosme

1997-01-01

El embarazo conlleva una serie de cambios orgánicos, fisiológicos (del sistema cardiovascular y gastrointestinal, de la función pulmonar, hematológicos...) y de conducta que pueden repercutir en la cavidad bucal. El granuloma gravídico se considera una entidad patológica propia del embarazo. Podremos observar también en las pacientes gestantes un aumento en la incidencia de caries, asociado fundamentalmente a un incremento de Jos factores locales cariogénicos (descuido de la higiene bucal, ca...

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

Computing the Feng-Rao distances for codes from order domains

DEFF Research Database (Denmark)

Ruano Benito, Diego

2007-01-01

We compute the Feng–Rao distance of a code coming from an order domain with a simplicial value semigroup. The main tool is the Apéry set of a semigroup that can be computed using a Gröbner basis.......We compute the Feng–Rao distance of a code coming from an order domain with a simplicial value semigroup. The main tool is the Apéry set of a semigroup that can be computed using a Gröbner basis....

Development Of A Navier-Stokes Computer Code

Science.gov (United States)

Yoon, Seokkwan; Kwak, Dochan

1993-01-01

Report discusses aspects of development of CENS3D computer code, solving three-dimensional Navier-Stokes equations of compressible, viscous, unsteady flow. Implements implicit finite-difference or finite-volume numerical-integration scheme, called "lower-upper symmetric-Gauss-Seidel" (LU-SGS), offering potential for very low computer time per iteration and for fast convergence.

TRANGE: computer code to calculate the energy beam degradation in target stack

International Nuclear Information System (INIS)

Bellido, Luis F.

1995-07-01

A computer code to calculate the projectile energy degradation along a target stack was developed for an IBM or compatible personal microcomputer. A comparison of protons and deuterons bombarding uranium and aluminium targets was made. The results showed that the data obtained with TRANGE were in agreement with other computers code such as TRIM, EDP and also using Williamsom and Janni range and stopping power tables. TRANGE can be used for any charged particle ion, for energies between 1 to 100 MeV, in metal foils and solid compounds targets. (author). 8 refs., 2 tabs

Control rod computer code IAMCOS: general theory and numerical methods

International Nuclear Information System (INIS)

West, G.

1982-11-01

IAMCOS is a computer code for the description of mechanical and thermal behavior of cylindrical control rods for fast breeders. This code version was applied, tested and modified from 1979 to 1981. In this report are described the basic model (02 version), theoretical definitions and computation methods [fr

Computations for Truck Sliding with TRUCK 3.1 Code

Science.gov (United States)

1989-08-01

16 REFERENCES 1. L u. \\Villiam N.. Hobbs. Norman P. and Atkinson, Michael. TRUCK 3.1-An Improrcd Digital (’oiputtr Program for Calculating the Response...for Operations and Plans ATIN: Technical Libary Director of Chemical & Nuear Operations Dpartnt of the AIW Waskbington, DC 20310 1 Cocaeder US Ay...Lawrenoe Livermore Lab. ATIN: Code 2124, Tedhnical ATTN: Tech Info Dept L-3 Reports Libary P.O. Be 808 Monterey, CA 93940 Livermore, CA 94550 AFSC

Linking CATHENA with other computer codes through a remote process

Energy Technology Data Exchange (ETDEWEB)

Vasic, A.; Hanna, B.N.; Waddington, G.M. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Sabourin, G. [Atomic Energy of Canada Limited, Montreal, Quebec (Canada); Girard, R. [Hydro-Quebec, Montreal, Quebec (Canada)

2005-07-01

starts, ends, controls, receives boundary conditions from CATHENA, calls ELOCA-IST subroutines for computation and sends feedback to CATHENA through PVM calls. The benefit of this dynamic link is that CATHENA's GENeralized Heat Transfer Package (GENHTP) is replaced with a specialized detailed model for CANDU fuel elements. The stand-alone plant conTROL Gentilly-2 (TROLG2) program, developed jointly by AECL and Hydro-Quebec, simulates the control system of the Gentilly-2 generating station operated by Hydro Quebec. The dynamic link with a CATHENA plant idealization couples the thermalhydraulic reactor behavior to reactor control system behavior of the Gentilly-2 generating station plant during transient conditions. CATHENA can perform simulations of CANDU channels by dynamically linking with one or more ELOCA driver programs. Each link to an independent instance of the ELOCA driver program is associated with one fuel element having up to 20 axial nodes (current ELOCA-IST limit) and one circumferential segment. Figure 1 in the full paper shows graphically the data transfers involved in the connection between the CATHENA and ELOCA driver through the PVM interface. Variables transferred from CATHENA to ELOCA-IST at each time step are: number of axial segments; number of circumferential segments (currently one only); coolant pressure; coolant temperature; sheath-to-coolant heat transfer coefficient; thermal radiation heat flux; and, power fraction. Variables that are returned for each axial segment from ELOCA-IST are: fuel sheath temperature; fuel element outer diameter; and, fuel length. CATHENA linked with ELOCA through PVM allows independent development of separate codes and achieves direct coupling during execution ensuring convergence between the codes. This coupling also eliminates the preparation and conversion of data transfer necessary between the codes by an analyst. This coupling process saves analyst time while reducing the possibility of inadvertent errors

Linking CATHENA with other computer codes through a remote process

International Nuclear Information System (INIS)

Vasic, A.; Hanna, B.N.; Waddington, G.M.; Sabourin, G.; Girard, R.

2005-01-01

, controls, receives boundary conditions from CATHENA, calls ELOCA-IST subroutines for computation and sends feedback to CATHENA through PVM calls. The benefit of this dynamic link is that CATHENA's GENeralized Heat Transfer Package (GENHTP) is replaced with a specialized detailed model for CANDU fuel elements. The stand-alone plant conTROL Gentilly-2 (TROLG2) program, developed jointly by AECL and Hydro-Quebec, simulates the control system of the Gentilly-2 generating station operated by Hydro Quebec. The dynamic link with a CATHENA plant idealization couples the thermalhydraulic reactor behavior to reactor control system behavior of the Gentilly-2 generating station plant during transient conditions. CATHENA can perform simulations of CANDU channels by dynamically linking with one or more ELOCA driver programs. Each link to an independent instance of the ELOCA driver program is associated with one fuel element having up to 20 axial nodes (current ELOCA-IST limit) and one circumferential segment. Figure 1 in the full paper shows graphically the data transfers involved in the connection between the CATHENA and ELOCA driver through the PVM interface. Variables transferred from CATHENA to ELOCA-IST at each time step are: number of axial segments; number of circumferential segments (currently one only); coolant pressure; coolant temperature; sheath-to-coolant heat transfer coefficient; thermal radiation heat flux; and, power fraction. Variables that are returned for each axial segment from ELOCA-IST are: fuel sheath temperature; fuel element outer diameter; and, fuel length. CATHENA linked with ELOCA through PVM allows independent development of separate codes and achieves direct coupling during execution ensuring convergence between the codes. This coupling also eliminates the preparation and conversion of data transfer necessary between the codes by an analyst. This coupling process saves analyst time while reducing the possibility of inadvertent errors and additionally

Control de higiene bucal en pacientes geriátricos portadores de sobredentaduras

Directory of Open Access Journals (Sweden)

Gema Lauzardo García del Prado

2002-12-01

Full Text Available Debido a la importancia de establecer medidas preventivas de higiene bucal que beneficien a los pacientes de la tercera edad, nos propusimos como objetivo en nuestro trabajo determinar la influencia de la higiene bucal controlada en pacientes geriátricos portadores de sobredentaduras. Nuestro universo estuvo constituido por 20 pacientes de ambos sexos mayores de 60 años, portadores de prótesis parcial removible desde hace 1 año, que acudieron a nuestro servicio para recibir tratamientos rehabilitadores debidamente avalados por historias clínicas que constan en el archivo de la Facultad de Estomatología de ISCM de La Habana. Dichos pacientes estaban en plenas facultades mentales y físicas en correspondencia con su edad.Due to the importance of taking oral hygiene preventive measures to benefit the elderly, we proposed ourselves as an objective to determine the influence of controlled oral hygiene in geriatric patients wearing overdentures. Our universe was composed of 20 patients aged 60 of both sexes, who had been wearing removable partial denture for a year and received rehabilitating treatment in our service, endorsed by their medical histories, which are in the archive of the Dental Faculty of the Higher Institute of Medical Sciences of Havana City. These patients were in full mental and physical capacity according to their age.

THYDE-B1/MOD1: a computer code for analysis of small-break loss-of-coolant accident of boiling water reactors

International Nuclear Information System (INIS)

Muramatsu, Ken; Akimoto, Masayuki

1982-08-01

THYDE-B1/MOD1 is a computer code to analyze thermo-hydraulic transients of the reactor cooling system of a BWR, mainly during a small-break loss-of-coolant accidnet (SB-LOCA) with a special emphasis on the behavior of pressure and mixture level in the pressure vessel. The coolant behavior is simulated with a volume-and-junction method based on assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions, i.e., subcooled liquid, saturated mixture and saturated steam regions are allowed to exist. The regions are separated by moving boundaries, tracked by mass and energy balances for each region. The interior of the pressure vessel is represented by two volumes with three regions: one for inside of the shroud and the other for outside, while other portions of the system are treated with homogeneous model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SB-LOCAs in which the hydraulic transient is relatively slow and the cooling of the core strongly depends on the mixture level behavior in the vessel. In order to simulate the system behavior, THYDE-B1 is provided with analytical models for reactor kinetics, heat generation and conduction in fuel rods and structures, heat transfer between coolant and solid surfaces, coolant injection systems, breaks and discharge systems, jet pumps, recirculation pumps, and so on. The verification of the code has been conducted. A good predictability of the code has been indicated through the comparison of calculated results with experimental data provided by ROSA-III small-break tests. This report presents the analytical models, solution method, and input data requirements of the THYDE-B1/MOD1 code. (author)

Sensitivity analysis of FRAPCON-1 computer code to some parameters

International Nuclear Information System (INIS)

Chia, C.T.; Silva, C.F. da.

1987-05-01

A sensibility study of the code FRAPCON-1 was done for the following inout data: number of axial nodes, number of time steps and the axial power shape. Their influence in the code response concerning to the fuel center line temperature, stored energy, internal gas pressure, clad hoop strain and gap width were analyzed. The number of axial nodes has little influence, but care must be taken in the choice of the power axial profile and the time step length. (Author) [pt

Current algorithms used in reactor safety codes and the impact of future computer development on these algorithms

International Nuclear Information System (INIS)

Mahaffy, J.H.; Liles, D.R.; Woodruff, S.B.

1985-01-01

Computational methods and solution procedures used in the US Nuclear Regulatory Commission's reactor safety systems codes, Transient Reactor Analysis Code (TRAC) and Reactor Leak and Power Safety Excursion Code (RELAP), are reviewed. Methods used in TRAC-PF1/MOD1, including the stability-enhancing two-step (SETS) technique, which permits fast computations by allowing time steps larger than the material Courant stability limit, are described in detail, and the differences from RELAP5/MOD2 are noted. Developments in computing, including parallel and vector processing, and their applicability to nuclear reactor safety codes are described. These developments, coupled with appropriate numerical methods, make detailed faster-than-real-time reactor safety analysis a realistic near-term possibility

Interface between computational fluid dynamics (CFD) and plant analysis computer codes

International Nuclear Information System (INIS)

Coffield, R.D.; Dunckhorst, F.F.; Tomlinson, E.T.; Welch, J.W.

1993-01-01

Computational fluid dynamics (CFD) can provide valuable input to the development of advanced plant analysis computer codes. The types of interfacing discussed in this paper will directly contribute to modeling and accuracy improvements throughout the plant system and should result in significant reduction of design conservatisms that have been applied to such analyses in the past

Development of a Computer Code for the Estimation of Fuel Rod Failure

Energy Technology Data Exchange (ETDEWEB)

Rhee, I.H.; Ahn, H.J. [Korea Electric Power Research Institute, Daejeon (Korea, Republic of)

1997-12-31

Much research has already been performed to obtain the information on the degree of failed fuel rods from the primary coolant activities of operating PWRs in the last few decades. The computer codes that are currently in use for domestic nuclear power plants, such as CADE code and ABB-CE codes developed by Westinghouse and ABB-CE, respectively, still give significant overall errors in estimating the failed fuel rods. In addition, with the CADE code, it is difficult to predict the degree of fuel rod failures during the transient period of nuclear reactor operation, where as the ABB-CE codes are relatively more difficult to use for end-users. In particular, the rapid progresses made recently in the area of the computer hardware and software systems that their computer programs be more versatile and user-friendly. While the MS windows system that is centered on the graphic user interface and multitasking is now in widespread use, the computer codes currently employed at the nuclear power plants, such as CADE and ABB-CE codes, can only be run on the DOS system. Moreover, it is desirable to have a computer code for the fuel rod failure estimation that can directly use the radioactivity data obtained from the on-line monitoring system of the primary coolant activity. The main purpose of this study is, therefore, to develop a Windows computer code that can predict the location, the number of failed fuel rods,and the degree of failures using the radioactivity data obtained from the primary coolant activity for PWRs. Another objective is to combine this computer code with the on-line monitoring system of the primary coolant radioactivity at Kori 3 and 4 operating nuclear power plants and enable their combined use for on-line evaluation of the number and degree of fuel rod failures. (author). 49 refs., 85 figs., 30 tabs.

Efficient Proximity Computation Techniques Using ZIP Code Data for Smart Cities †.

Science.gov (United States)

Murdani, Muhammad Harist; Kwon, Joonho; Choi, Yoon-Ho; Hong, Bonghee

2018-03-24

In this paper, we are interested in computing ZIP code proximity from two perspectives, proximity between two ZIP codes ( Ad-Hoc ) and neighborhood proximity ( Top-K ). Such a computation can be used for ZIP code-based target marketing as one of the smart city applications. A naïve approach to this computation is the usage of the distance between ZIP codes. We redefine a distance metric combining the centroid distance with the intersecting road network between ZIP codes by using a weighted sum method. Furthermore, we prove that the results of our combined approach conform to the characteristics of distance measurement. We have proposed a general and heuristic approach for computing Ad-Hoc proximity, while for computing Top-K proximity, we have proposed a general approach only. Our experimental results indicate that our approaches are verifiable and effective in reducing the execution time and search space.

Efficient Proximity Computation Techniques Using ZIP Code Data for Smart Cities †

Directory of Open Access Journals (Sweden)

Muhammad Harist Murdani

2018-03-01

Full Text Available In this paper, we are interested in computing ZIP code proximity from two perspectives, proximity between two ZIP codes (Ad-Hoc and neighborhood proximity (Top-K. Such a computation can be used for ZIP code-based target marketing as one of the smart city applications. A naïve approach to this computation is the usage of the distance between ZIP codes. We redefine a distance metric combining the centroid distance with the intersecting road network between ZIP codes by using a weighted sum method. Furthermore, we prove that the results of our combined approach conform to the characteristics of distance measurement. We have proposed a general and heuristic approach for computing Ad-Hoc proximity, while for computing Top-K proximity, we have proposed a general approach only. Our experimental results indicate that our approaches are verifiable and effective in reducing the execution time and search space.

Saúde bucal no EpiFloripa: estudo prospectivo das condições de saúde de adultos de Florianópolis, Sul do Brasil

Directory of Open Access Journals (Sweden)

Marco Aurelio Peres

2014-06-01

Full Text Available Objetivo: Descrever a metodologia e desafios de estudos de saúde bucal, inseridos em uma coorte prospectiva de adultos. Métodos: Foi obtida uma amostra de 2.016 adultos residentes em Florianópolis em 2009. Visitas domiciliares foram realizadas para a aplicação de um questionário sobre condições socioeconômicas e demográficas, de saúde geral, uso de serviços e de medicamentos, doação de sangue, violência doméstica e uma seção relativa à saúde da mulher. Informações sobre saúde bucal incluíram autoavaliação de seu estado, número de dentes, uso de serviços, percepção de necessidade de tratamento, ocorrência, intensidade e impacto nas atividades diárias da dor dentária, sintomas de xerostomia e dificuldade de alimentação em virtude de problemas bucais. Adicionalmente, aferiram-se a pressão arterial e medidas antropométricas. Em 2012, ocorreu a segunda onda do estudo, na qual foi aplicado um questionário sobre questões socioeconômicas, qualidade de vida, experiências discriminatórias, recordatório alimentar de 24 horas e de saúde bucal. Além disso, foi aferida a pressão arterial, medidas antropométricas, e foram realizados exames bucais (cárie, perdas dentárias e condições periodontais. Resultados: A taxa de participação foi de 85,3% (n = 1.720 em 2009 e, destes, 1.222 (71,1% foram investigados em 2012. Conclusões: A continuidade do estudo poderá contribuir para a elucidação da causalidade de associações entre condições de saude bucal e agravos e doencas cronicas.

Once-through CANDU reactor models for the ORIGEN2 computer code

International Nuclear Information System (INIS)

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

1980-11-01

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

CASKETSS-2: a computer code system for thermal and structural analysis of nuclear fuel shipping casks (version 2)

International Nuclear Information System (INIS)

Ikushima, Takeshi

1991-08-01

A computer program CASKETSS-2 has been developed for the purpose of thermal and structural analysis of nuclear fuel shipping casks. CASKETSS-2 means a modular code system for CASK Evaluation code system Thermal and Structural Safety (Version 2). Main features of CASKETSS-2 are as follow; (1) Thermal and structural analysis computer programs for one-, two-, three-dimensional geometries are contained in the code system. (2) There are simplified computer programs and a detailed one in the structural analysis part in the code system. (3) Input data generator is provided in the code system. (4) Graphic computer program is provided in the code system. In the paper, brief illustration of calculation method, input data and sample calculations are presented. (author)

Case studies in Gaussian process modelling of computer codes

International Nuclear Information System (INIS)

Kennedy, Marc C.; Anderson, Clive W.; Conti, Stefano; O'Hagan, Anthony

2006-01-01

In this paper we present a number of recent applications in which an emulator of a computer code is created using a Gaussian process model. Tools are then applied to the emulator to perform sensitivity analysis and uncertainty analysis. Sensitivity analysis is used both as an aid to model improvement and as a guide to how much the output uncertainty might be reduced by learning about specific inputs. Uncertainty analysis allows us to reflect output uncertainty due to unknown input parameters, when the finished code is used for prediction. The computer codes themselves are currently being developed within the UK Centre for Terrestrial Carbon Dynamics

Computer codes for beam dynamics analysis of cyclotronlike accelerators

Science.gov (United States)

Smirnov, V.

2017-12-01

Computer codes suitable for the study of beam dynamics in cyclotronlike (classical and isochronous cyclotrons, synchrocyclotrons, and fixed field alternating gradient) accelerators are reviewed. Computer modeling of cyclotron segments, such as the central zone, acceleration region, and extraction system is considered. The author does not claim to give a full and detailed description of the methods and algorithms used in the codes. Special attention is paid to the codes already proven and confirmed at the existing accelerating facilities. The description of the programs prepared in the worldwide known accelerator centers is provided. The basic features of the programs available to users and limitations of their applicability are described.

Independent verification and validation testing of the FLASH computer code, Versiion 3.0

International Nuclear Information System (INIS)

Martian, P.; Chung, J.N.

1992-06-01

Independent testing of the FLASH computer code, Version 3.0, was conducted to determine if the code is ready for use in hydrological and environmental studies at various Department of Energy sites. This report describes the technical basis, approach, and results of this testing. Verification tests, and validation tests, were used to determine the operational status of the FLASH computer code. These tests were specifically designed to test: correctness of the FORTRAN coding, computational accuracy, and suitability to simulating actual hydrologic conditions. This testing was performed using a structured evaluation protocol which consisted of: blind testing, independent applications, and graduated difficulty of test cases. Both quantitative and qualitative testing was performed through evaluating relative root mean square values and graphical comparisons of the numerical, analytical, and experimental data. Four verification test were used to check the computational accuracy and correctness of the FORTRAN coding, and three validation tests were used to check the suitability to simulating actual conditions. These tests cases ranged in complexity from simple 1-D saturated flow to 2-D variably saturated problems. The verification tests showed excellent quantitative agreement between the FLASH results and analytical solutions. The validation tests showed good qualitative agreement with the experimental data. Based on the results of this testing, it was concluded that the FLASH code is a versatile and powerful two-dimensional analysis tool for fluid flow. In conclusion, all aspects of the code that were tested, except for the unit gradient bottom boundary condition, were found to be fully operational and ready for use in hydrological and environmental studies

Compendium of computer codes for the safety analysis of fast breeder reactors

International Nuclear Information System (INIS)

1977-10-01

The objective of the compendium is to provide the reader with a guide which briefly describes many of the computer codes used for liquid metal fast breeder reactor safety analyses, since it is for this system that most of the codes have been developed. The compendium is designed to address the following frequently asked questions from individuals in licensing and research and development activities: (1) What does the code do. (2) To what safety problems has it been applied. (3) What are the code's limitations. (4) What is being done to remove these limitations. (5) How does the code compare with experimental observations and other code predictions. (6) What reference documents are available

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

LATTICE: an interactive lattice computer code

International Nuclear Information System (INIS)

Staples, J.

1976-10-01

LATTICE is a computer code which enables an interactive user to calculate the functions of a synchrotron lattice. This program satisfies the requirements at LBL for a simple interactive lattice program by borrowing ideas from both TRANSPORT and SYNCH. A fitting routine is included

Liquen plano bucal. Presentación de un caso

OpenAIRE

Sánchez Gay, Juana María; Artze Caballero, Maritza; Artze Caballero, Guillermo

2016-01-01

El liquen plano es una enfermedad inflamatoria, eruptiva de la piel, pruriginosa, de marcha crónica o subaguda que puede involucrar las mucosas, sobre todo la bucal. Su etiología es desconocida, se relaciona con estímulos subjetivos (estados nerviosos, depresivos). Se mencionan también como posibles causas: las infecciones, los trastornos metabólicos y endocrinos, recientemente se ha considerado que la enfermedad puede presentar una reacción de hipersensibilidad retardada. El caso clínico del...

User's manual for computer code RIBD-II, a fission product inventory code

International Nuclear Information System (INIS)

Marr, D.R.

1975-01-01

The computer code RIBD-II is used to calculate inventories, activities, decay powers, and energy releases for the fission products generated in a fuel irradiation. Changes from the earlier RIBD code are: the expansion to include up to 850 fission product isotopes, input in the user-oriented NAMELIST format, and run-time choice of fuels from an extensively enlarged library of nuclear data. The library that is included in the code package contains yield data for 818 fission product isotopes for each of fourteen different fissionable isotopes, together with fission product transmutation cross sections for fast and thermal systems. Calculational algorithms are little changed from those in RIBD. (U.S.)

Hábitos de higiene bucal e índice de higiene oral de escolares do ensino público

Directory of Open Access Journals (Sweden)

Adriano Pivotto

2013-12-01

Full Text Available Objetivo: Verificar os hábitos de higiene bucal e o índice de higiene oral de escolares do ensino fundamental de escolas públicas do município de Itajaí-SC. Métodos: Investigação descritiva transversal. A amostra constou de escolares do primeiro ano do ensino fundamental de escolas públicas da rede municipal de Itajaí-SC matriculados em 2011. A coleta de dados foi realizada através de registro do Índice de Higiene Oral Simplificado (IHOS das crianças e da aplicação de um questionário aos pais/responsáveis sobre a caracterização da higiene oral dos escolares. Resultados: Avaliaram-se 202 escolares. Quanto à escovação dental diária, 121 (59,9% relataram que um adulto é o responsável pela realização desse procedimento na criança e 81 (40,1% informaram que a própria criança executa a escovação. O número de escovações em 128 (63,4% crianças foi de três vezes ao dia e o fio dental não era utilizado por 137 (68%. Encontrou-se em 114 (56,4% escolares um IHOS classificado como higiene razoável – de 1,3 a 2. Com relação a como proceder com a higiene bucal da criança, 140 (69% pais responderam já ter recebido essa informação e a fonte citada por 118 (58,4% foi o cirurgião-dentista. Conclusão: Os escolares apresentaram hábitos de higiene bucal com deficiência na remoção da placa bacteriana e no uso do fio dental, resultando em um IHOS razoável.

MARG1D: One dimensional outer region matching data code

International Nuclear Information System (INIS)

Tokuda, Shinji; Watanabe, Tomoko.

1995-08-01

A code MARG1D has been developed which computes outer region matching data of the one dimensional Newcomb equation. Matching data play an important role in the resistive (and non ideal) Magneto-hydrodynamic (MHD) stability analysis in a tokamak plasma. The MARG1D code computes matching data by using the boundary value method or by the eigenvalue method. Variational principles are derived for the problems to be solved and a finite element method is applied. Except for the case of marginal stability, the eigenvalue method is equivalent to the boundary value method. However, the eigenvalue method has the several advantages: it is a new method of ideal MHD stability analysis for which the marginally stable state can be identified, and it guarantees numerical stability in computing matching data close to marginal stability. We perform detailed numerical experiments for a model equation with analytical solutions and for the Newcomb equation in the m=1 mode theory. Numerical experiments show that MARG1D code gives the matching data with numerical stability and high accuracy. (author)

War of ontology worlds: mathematics, computer code, or Esperanto?

Science.gov (United States)

Rzhetsky, Andrey; Evans, James A

2011-09-01

The use of structured knowledge representations-ontologies and terminologies-has become standard in biomedicine. Definitions of ontologies vary widely, as do the values and philosophies that underlie them. In seeking to make these views explicit, we conducted and summarized interviews with a dozen leading ontologists. Their views clustered into three broad perspectives that we summarize as mathematics, computer code, and Esperanto. Ontology as mathematics puts the ultimate premium on rigor and logic, symmetry and consistency of representation across scientific subfields, and the inclusion of only established, non-contradictory knowledge. Ontology as computer code focuses on utility and cultivates diversity, fitting ontologies to their purpose. Like computer languages C++, Prolog, and HTML, the code perspective holds that diverse applications warrant custom designed ontologies. Ontology as Esperanto focuses on facilitating cross-disciplinary communication, knowledge cross-referencing, and computation across datasets from diverse communities. We show how these views align with classical divides in science and suggest how a synthesis of their concerns could strengthen the next generation of biomedical ontologies.

Pautas orientadoras para la promoción de la salud bucal en la primera infancia para profesionales de salud

OpenAIRE

Gloria Esperanza González C.

2012-01-01

La salud bucal es parte integral de la salud general del individuo. Lasafecciones bucales más prevalentes en niños son las alteraciones delcrecimiento y desarrollo bucodental, y la caries. Las primeras, generalmente están relacionadas con hábitos orales nocivos, patronesalimentarios inadecuados y la adquisición tardía de funciones comola masticación que generan maloclusiones. La caries, enfermedadcrónica más frecuente en la infancia, causa graves consecuencias enla salud del niño como dolor, ...

Situación de salud bucal de la población cubana: Estudio comparativo según provincias, 1998

Directory of Open Access Journals (Sweden)

Grisel Zacca González

2001-08-01

Full Text Available Se realizó un estudio comparativo del estado de salud bucal de las 15 provincias y una muestra representativa del país. Para el análisis se utilizaron los indicadores de salud bucal propuestos por la Federación Dental Internacional. Esta investigación permitió evaluar el comportamiento de las principales enfermedades bucales y las necesidades de tratamiento para establecer estrategias de trabajo con el objetivo de mejorar la salud bucal de nuestra población. Se comprobó que el comportamiento de las enfermedades bucales en la muestra del país resultó similar al de las provincias. La provincia Habana fue la más afectada en cuanto a las condiciones extraorales, de la mucosa bucal y el estado de las articulaciones temporomandibulares, mientras que Guantánamo presentó el mayor porcentaje de afectados por maloclusión y La Isla de la Juventud por enfermedad periodontal. Asimismo, Pinar del Río tuvo el mayor índice COP y presentó problemas con la conservación de dientes en boca. La población de Granma es la que más necesidad de prótesis presentó. Además, se evaluó el cumplimiento de las metas de salud bucal para el año 2000, que no fueron cumplidas por la mayoría de las provincias y se establecieron nuevas metas para el año 2005, teniendo en cuenta la situación actual de cada territorio.A comparative study on the oral health status of the 15 provinces was conducted and a representative sample of the country was taken. To make this analysis the oral health indicators proposed by the International Dental Federation were used. This research allowed to evaluate the behavior of the different oral diseases and the needs of treatment to establish working strategies aimed at improving the oral health of our population. It was proved that the behavior of oral diseases in the sample of the country was similar to that of the provinces. The province of Havana was the most affected as to extra-oral conditions of the oral mucosa and the

Compendium of computer codes for the safety analysis of LMFBR's

International Nuclear Information System (INIS)

1975-06-01

A high level of mathematical sophistication is required in the safety analysis of LMFBR's to adequately meet the demands for realism and confidence in all areas of accident consequence evaluation. The numerical solution procedures associated with these analyses are generally so complex and time consuming as to necessitate their programming into computer codes. These computer codes have become extremely powerful tools for safety analysis, combining unique advantages in accuracy, speed and cost. The number, diversity and complexity of LMFBR safety codes in the U. S. has grown rapidly in recent years. It is estimated that over 100 such codes exist in various stages of development throughout the country. It is inevitable that such a large assortment of codes will require rigorous cataloguing and abstracting to aid individuals in identifying what is available. It is the purpose of this compendium to provide such a service through the compilation of code summaries which describe and clarify the status of domestic LMFBR safety codes. (U.S.)

Conhecimento de alunos concluintes de Pedagogia sobre saúde bucal

Directory of Open Access Journals (Sweden)

Jainara Maria Soares Ferreira

2005-08-01

Full Text Available O objetivo desta pesquisa foi avaliar o conhecimento sobre saúde bucal de concluintes do curso de Pedagogia da Universidade Federal da Paraíba. Para tanto, alunos em sala de aula responderam um questionário contendo quesitos objetivos relativos ao tema. Os dados foram analisados por meio de estatística descritiva e os resultados indicam que 83% dos cem participantes tiveram acesso a informações de odontologia preventiva, 64% pelo cirurgião-dentista. Os acadêmicos conhecem pouco sobre placa bacteriana (31%, ao contrário da etiologia da cárie dentária (55%. Embora 92% dos concluintes afirmem ser a chupeta prejudicial ao desenvolvimento facial da criança, apenas 9% identificaram a idade limite de desuso. Adicionalmente, 20% acertaram o momento ideal do primeiro contato entre criança e dentista. Concluiu-se que os estudantes apresentam conhecimento razoável em relação à saúde bucal, sugerindo a instituição de programas educativos dentro do currículo acadêmico, uma vez que esses futuros profissionais contribuirão para a formação da criança, estabelecendo práticas diárias capazes de gerar saúde.

Conhecimento de alunos concluintes de Pedagogia sobre saúde bucal

Directory of Open Access Journals (Sweden)

Jainara Maria Soares Ferreira

Full Text Available O objetivo desta pesquisa foi avaliar o conhecimento sobre saúde bucal de concluintes do curso de Pedagogia da Universidade Federal da Paraíba. Para tanto, alunos em sala de aula responderam um questionário contendo quesitos objetivos relativos ao tema. Os dados foram analisados por meio de estatística descritiva e os resultados indicam que 83% dos cem participantes tiveram acesso a informações de odontologia preventiva, 64% pelo cirurgião-dentista. Os acadêmicos conhecem pouco sobre placa bacteriana (31%, ao contrário da etiologia da cárie dentária (55%. Embora 92% dos concluintes afirmem ser a chupeta prejudicial ao desenvolvimento facial da criança, apenas 9% identificaram a idade limite de desuso. Adicionalmente, 20% acertaram o momento ideal do primeiro contato entre criança e dentista. Concluiu-se que os estudantes apresentam conhecimento razoável em relação à saúde bucal, sugerindo a instituição de programas educativos dentro do currículo acadêmico, uma vez que esses futuros profissionais contribuirão para a formação da criança, estabelecendo práticas diárias capazes de gerar saúde.

Gender codes why women are leaving computing

CERN Document Server

Misa, Thomas J

2010-01-01

The computing profession is facing a serious gender crisis. Women are abandoning the computing field at an alarming rate. Fewer are entering the profession than anytime in the past twenty-five years, while too many are leaving the field in mid-career. With a maximum of insight and a minimum of jargon, Gender Codes explains the complex social and cultural processes at work in gender and computing today. Edited by Thomas Misa and featuring a Foreword by Linda Shafer, Chair of the IEEE Computer Society Press, this insightful collection of essays explores the persisting gender imbalance in computing and presents a clear course of action for turning things around.

Statistical screening of input variables in a complex computer code

International Nuclear Information System (INIS)

Krieger, T.J.

1982-01-01

A method is presented for ''statistical screening'' of input variables in a complex computer code. The object is to determine the ''effective'' or important input variables by estimating the relative magnitudes of their associated sensitivity coefficients. This is accomplished by performing a numerical experiment consisting of a relatively small number of computer runs with the code followed by a statistical analysis of the results. A formula for estimating the sensitivity coefficients is derived. Reference is made to an earlier work in which the method was applied to a complex reactor code with good results

Atribuições dos Técnicos em Saúde Bucal na Estratégia Saúde da Família em Minas Gerais, Brasil

Directory of Open Access Journals (Sweden)

Carla Aparecida Sanglard-Oliveira

2013-08-01

Full Text Available O objetivo deste artigo é analisar o autorrelato de funções executadas pelos Técnicos em Saúde Bucal no Estado de Minas Gerais. Estudo transversal e descritivo, realizado por meio de entrevista telefônica, com amostra representativa de 231 trabalhadores. A análise descritiva envolveu cálculo de proporções. Observou-se que 71,6% (IC 95%, 64,4-77,5 realizavam polimento coronário, 63,2% (IC 95%, 56,1-69,7 faziam raspagem de cálculo e 14,7% (IC 95%, 10,3-20,4 condensavam e inseriam materiais restauradores. Em relação às ações preventivas/coletivas, 100% (IC 95%, 97,6-100,0 participavam de ações educativas, 99,0% (IC 95%, 96,1-99,8 demonstravam técnicas de higiene bucal, 96,6% (IC 95%, 92,7-98,4 realizavam a aplicação tópica de flúor, 77,9% (IC 95%, 71,5-83,3 realizavam visitas domiciliares, e 96,6% (IC 95%, 92,7-98,4 realizavam ações coletivas, principalmente em escolas. Os Técnicos em Saúde Bucal têm desprendido seu tempo mais em atividades preventivas/coletivas do que em atividades assistenciais.

O Direito humano ao sorriso: uma análise do arcabouço legislativo sobre a saúde bucal

Directory of Open Access Journals (Sweden)

Yêda Maria Parro

2016-05-01

Full Text Available A saúde bucal da população tem reflexo na saúde integral e na qualidade de vida de toda a sociedade. As mudanças nos padrões das doenças guardam estreita relação com as alterações nos estilos de vida, que incluem dietas ricas em açúcares, uso de tabaco e álcool, sedentarismo e estresse crônico. Assim, a investigação do tema é um importante instrumento no planejamento de programas de prevenção e tratamento. Foi verificada a presença do tema saúde bucal no arcabouço legislativo federal no período de 1986 a 2014. Tratou-se de pesquisa exploratória de base descritiva-analítica, que utilizou a pesquisa documental. Foram levantados nos sítios das duas casas do Congresso Nacional e do Ministério da Saúde a legislação produzida nesse período. Os resultados encontrados demonstraram que o tema saúde bucal está no grupo de normas infralegais e o tema está presente na agenda governamental. A evolução legislativa no Brasil para o alcance do direito humano ao sorriso está ascendendo, mas faltam concretizações das ações. A saúde bucal ainda permanece à margem da saúde geral.

A restructuring of CF package for MIDAS computer code

International Nuclear Information System (INIS)

Park, S. H.; Kim, K. R.; Kim, D. H.; Cho, S. W.

2004-01-01

CF package, which evaluates user-specified 'control functions' and applies them to define or control various aspects of computation, has been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and modernized data structure. To do this, data transferring methods of current MELCOR code are modified and adopted into the CF package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of meaning of the variables as well as waste of memory, difficulty is more over because its data is location information of other package's data due to characteristics of CF package. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of the CF package addressed in this paper includes module development, subroutine modification, and treats MELGEN, which generates data file, as well as MELCOR, which is processing a calculation. The verification has been done by comparing the results of the modified code with those from the existing code. As the trends are similar to each other, it hints that the same approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models

A study on the nuclear computer codes installation and management system

International Nuclear Information System (INIS)

Kim, Yeon Seung; Huh, Young Hwan; Kim, Hee Kyung; Kang, Byung Heon; Kim, Ko Ryeo; Suh, Soong Hyok; Choi, Young Gil; Lee, Jong Bok

1990-12-01

From 1987 a number of technical transfer related to nuclear power plant had been performed from C-E for YGN 3 and 4 construction. Among them, installation and management of the computer codes for YGN 3 and 4 fuel and nuclear steam supply system was one of the most important project. Main objectives of this project are to establish the nuclear computer code management system, to develop QA procedure for nuclear codes, to secure the nuclear code reliability and to extend techanical applicabilities including the user-oriented utility programs for nuclear codes. Contents of performing the project in this year was to produce 215 transmittal packages of nuclear codes installation including making backup magnetic tape and microfiche for software quality assurance. Lastly, for easy reference about the nuclear codes information we presented list of code names and information on the codes which were introduced from C-E. (Author)

Citham-2 computer code-User manual

International Nuclear Information System (INIS)

Batista, J.L.

1984-01-01

The procedures and the input data for the Citham-2 computer code are described. It is a subroutine that modifies the nuclide concentration taking in account its burn and prepares cross sections library in 2,3 or 4 energy groups, to the used for Citation program. (E.G.) [pt

Citham a computer code for calculating fuel depletion-description, tests, modifications and evaluation

International Nuclear Information System (INIS)

Alvarenga, M.A.B.

1984-12-01

The CITHAN computer code was developed at IPEN (Instituto de Pesquisas Energeticas e Nucleares) to link the HAMMER computer code with a fuel depletion routine and to provide neutron cross sections to be read with the appropriate format of the CITATION code. The problem arised due to the efforts to addapt the new version denomined HAMMER-TECHION with the routine refered. The HAMMER-TECHION computer code was elaborated by Haifa Institute, Israel within a project with EPRI. This version is at CNEN to be used in multigroup constant generation for neutron diffusion calculation in the scope of the new methodology to be adopted by CNEN. The theoretical formulation of CITHAM computer code, tests and modificatins are described. (Author) [pt

Lesiones bucales relacionadas con las enfermedades digestivas

Directory of Open Access Journals (Sweden)

José A. Pacho Saavedra

2006-09-01

Full Text Available Muchas de las lesiones de la mucosa en la cavidad bucal están relacionadas con trastornos anatómicos y funcionales de los órganos del aparato digestivo; algunas forman parte del cuadro clínico de la entidad y otras aparecen como complicaciones de estas. Generalmente son de orígenes inmunológicos, nutricionales o carenciales. Estas lesiones son difíciles de tratar, por lo que es importante conocer las características clínicas que faciliten una adecuada interpretación y al mismo tiempo ofrecer una conducta terapéutica correcta. Se presenta una revisión actualizada de las características semiológicas de las lesiones bucales que forman parte del cuadro clínico de diversas enfermedades digestivas, con el fin de que los médicos generales, clínicos, estomatólogos y gastroenterólogos puedan diagnosticarlas y brindar mejor orientación y tratamiento a los pacientes.Many of the lesions of the mucosa in the oral cavity are related to anatomical and functional disorders of the organs of the digestive system. Some of them are part of the clinical picture of the entity and others appear as complications of them. Generally, they have an immunological, nutritional, or deficiency origin. These lesions are difficult to be treated and that's why it is important to know the clinical characteristics making easy an adequate interpretation, and to follow a suitable therapeutic conduct at the same time. An updated review of the semiological features of the oral lesions corresponding to the clinical picture of diverse digestive diseases is presented, so that the general physicians, clinicians, stomatologists and gastroenterologists be able to diagnose and give a better guidance and treatment to the patients.

Integrated computer codes for nuclear power plant severe accident analysis

Energy Technology Data Exchange (ETDEWEB)

Jordanov, I; Khristov, Y [Bylgarska Akademiya na Naukite, Sofia (Bulgaria). Inst. za Yadrena Izsledvaniya i Yadrena Energetika

1996-12-31

This overview contains a description of the Modular Accident Analysis Program (MAAP), ICARE computer code and Source Term Code Package (STCP). STCP is used to model TMLB sample problems for Zion Unit 1 and WWER-440/V-213 reactors. Comparison is made of STCP implementation on VAX and IBM systems. In order to improve accuracy, a double precision version of MARCH-3 component of STCP is created and the overall thermal hydraulics is modelled. Results of modelling the containment pressure, debris temperature, hydrogen mass are presented. 5 refs., 10 figs., 2 tabs.

Integrated computer codes for nuclear power plant severe accident analysis

International Nuclear Information System (INIS)

Jordanov, I.; Khristov, Y.

1995-01-01

This overview contains a description of the Modular Accident Analysis Program (MAAP), ICARE computer code and Source Term Code Package (STCP). STCP is used to model TMLB sample problems for Zion Unit 1 and WWER-440/V-213 reactors. Comparison is made of STCP implementation on VAX and IBM systems. In order to improve accuracy, a double precision version of MARCH-3 component of STCP is created and the overall thermal hydraulics is modelled. Results of modelling the containment pressure, debris temperature, hydrogen mass are presented. 5 refs., 10 figs., 2 tabs

Computing Challenges in Coded Mask Imaging

Science.gov (United States)

Skinner, Gerald

2009-01-01

This slide presaentation reviews the complications and challenges in developing computer systems for Coded Mask Imaging telescopes. The coded mask technique is used when there is no other way to create the telescope, (i.e., when there are wide fields of view, high energies for focusing or low energies for the Compton/Tracker Techniques and very good angular resolution.) The coded mask telescope is described, and the mask is reviewed. The coded Masks for the INTErnational Gamma-Ray Astrophysics Laboratory (INTEGRAL) instruments are shown, and a chart showing the types of position sensitive detectors used for the coded mask telescopes is also reviewed. Slides describe the mechanism of recovering an image from the masked pattern. The correlation with the mask pattern is described. The Matrix approach is reviewed, and other approaches to image reconstruction are described. Included in the presentation is a review of the Energetic X-ray Imaging Survey Telescope (EXIST) / High Energy Telescope (HET), with information about the mission, the operation of the telescope, comparison of the EXIST/HET with the SWIFT/BAT and details of the design of the EXIST/HET.

Computer code for quantitative ALARA evaluations

International Nuclear Information System (INIS)

Voilleque, P.G.

1984-01-01

A FORTRAN computer code has been developed to simplify the determination of whether dose reduction actions meet the as low as is reasonably achievable (ALARA) criterion. The calculations are based on the methodology developed for the Atomic Industrial Forum. The code is used for analyses of eight types of dose reduction actions, characterized as follows: reduce dose rate, reduce job frequency, reduce productive working time, reduce crew size, increase administrative dose limit for the task, and increase the workers' time utilization and dose utilization through (a) improved working conditions, (b) basic skill training, or (c) refresher training for special skills. For each type of action, two analysis modes are available. The first is a generic analysis in which the program computes potential benefits (in dollars) for a range of possible improvements, e.g., for a range of lower dose rates. Generic analyses are most useful in the planning stage and for evaluating the general feasibility of alternative approaches. The second is a specific analysis in which the potential annual benefits of a specific level of improvement and the annual implementation cost are compared. The potential benefits reflect savings in operational and societal costs that can be realized if occupational radiation doses are reduced. Because the potential benefits depend upon many variables which characterize the job, the workplace, and the workers, there is no unique relationship between the potential dollar savings and the dose savings. The computer code permits rapid quantitative analyses of alternatives and is a tool that supplements the health physicist's professional judgment. The program output provides a rational basis for decision-making and a record of the assumptions employed

Estado de salud bucal de la población cubana, 1995

Directory of Open Access Journals (Sweden)

Luis Delgado Méndez

1999-12-01

Full Text Available Se realizó una investigación epidemiológica nacional en el año 1995 con el objetivo de analizar el estado de la salud bucal de la población cubana. Se analizó una muestra de 3 805 personas de 16 áreas de salud, correspondientes a 11 provincias; se utilizó el modelo recomendado por la OMS para este tipo de estudio; se capacitaron y calibraron a 6 estomatólogos y sus respectivas asistentes. Los datos se procesaron en computadora mediante el programa EPINFO. Los resultados se confrontaron con las metas propuestas por la OMS para el año 2000. Se observó que las metas número 1, 2, 3 y 4 se cumplen según lo previsto, no así la meta 5.In 1995, an epidemiological research at national level was performed in order to analyse buccal health status of Cuban population. We studied a sample of 3 805 persons from 16 health areas, corresponding to 11 provinces. Model recommended by World Health Organization (WHO for this type of study was used. 6 stomatologists were trained and sized up as well as their respective assistants. Data were processed in a computer by EPINFO program. Results were compared with planned aims by WHO for 2000 year. Aims 1, 2, 3, and 4 are fulfilled according planning, except for number 5.

Computer-aided software understanding systems to enhance confidence of scientific codes

International Nuclear Information System (INIS)

Sheng, G.; Oeren, T.I.

1991-01-01

A unique characteristic of nuclear waste disposal is the very long time span over which the combined engineered and natural containment system must remain effective: hundreds of thousands of years. Since there is no precedent in human history for such an endeavour, simulation with the use of computers is the only means we have of forecasting possible future outcomes quantitatively. The need for reliable models and software to make such forecasts so far into the future is obvious. One of the critical elements necessary to ensure reliability is the degree of reviewability of the computer program. Among others, there are two very important reasons for this. Firstly, if there is to be any chance at all of validating the conceptual models as implemented by the computer code, peer reviewers must be able to see and understand what the program is doing. It is all but impossible to achieve this understanding by just looking at the code due to possible unfamiliarity with the language and often due as well to the length and complexity of the code. Secondly, a thorough understanding of the code is also necessary to carry out code maintenance activities which include among others, error detection, error correction and code modification for purposes of enhancing its performance, functionality or to adapt it to a changed environment. The emerging concepts of computer-aided software understanding and reverse engineering can answer precisely these needs. This paper will discuss the role they can play in enhancing the confidence one has on computer codes and several examples will be provided. Finally a brief discussion of combining state-of-art forward engineering systems with reverse engineering systems will show how powerfully they can contribute to the overall quality assurance of a computer program. (13 refs., 7 figs.)

Adaptation of Toodee-2 computer code for reflood analysis in Angra-1 reactor

International Nuclear Information System (INIS)

Praes, J.G.L.; Onusic Junior, J.

1981-01-01

A method of calculation the heat transfer coefficient used in Toodee-2 computer code for core reflood analysis in a loss of coolant accident, is presented. Preliminary results are presented with the use of heat transfer correlations based on FLECHT experiments adequate to a geometric arrangement such as 16 x 16 (Angra I). Optional calculations are suggested for the heat transfer coefficients when the cooling of fuel cladding by steam is used. (Author) [pt

GAM-HEAT -- a computer code to compute heat transfer in complex enclosures

International Nuclear Information System (INIS)

Cooper, R.E.; Taylor, J.R.; Kielpinski, A.L.; Steimke, J.L.

1991-02-01

The GAM-HEAT code was developed for heat transfer analyses associated with postulated Double Ended Guillotine Break Loss Of Coolant Accidents (DEGB LOCA) resulting in a drained reactor vessel. In these analyses the gamma radiation resulting from fission product decay constitutes the primary source of energy as a function of time. This energy is deposited into the various reactor components and is re- radiated as thermal energy. The code accounts for all radiant heat exchanges within and leaving the reactor enclosure. The SRS reactors constitute complex radiant exchange enclosures since there are many assemblies of various types within the primary enclosure and most of the assemblies themselves constitute enclosures. GAM-HEAT accounts for this complexity by processing externally generated view factors and connectivity matrices, and also accounts for convective, conductive, and advective heat exchanges. The code is applicable for many situations involving heat exchange between surfaces within a radiatively passive medium. The GAM-HEAT code has been exercised extensively for computing transient temperatures in SRS reactors with specific charges and control components. Results from these computations have been used to establish the need for and to evaluate hardware modifications designed to mitigate results of postulated accident scenarios, and to assist in the specification of safe reactor operating power limits. The code utilizes temperature dependence on material properties. The efficiency of the code has been enhanced by the use of an iterative equation solver. Verification of the code to date consists of comparisons with parallel efforts at Los Alamos National Laboratory and with similar efforts at Westinghouse Science and Technology Center in Pittsburgh, PA, and benchmarked using problems with known analytical or iterated solutions. All comparisons and tests yield results that indicate the GAM-HEAT code performs as intended

Compilation of the abstracts of nuclear computer codes available at CPD/IPEN

International Nuclear Information System (INIS)

Granzotto, A.; Gouveia, A.S. de; Lourencao, E.M.

1981-06-01

A compilation of all computer codes available at IPEN in S.Paulo are presented. These computer codes are classified according to Argonne National Laboratory - and Energy Nuclear Agency schedule. (E.G.) [pt

Validation of containment thermal hydraulic computer codes for VVER reactor

Energy Technology Data Exchange (ETDEWEB)

Jiri Macek; Lubomir Denk [Nuclear Research Institute Rez plc Thermal-Hydraulic Analyses Department CZ 250 68 Husinec-Rez (Czech Republic)

2005-07-01

Full text of publication follows: The Czech Republic operates 4 VVER-440 units, two VVER-1000 units are being finalized (one of them is undergoing commissioning). Thermal-hydraulics Department of the Nuclear Research Institute Rez performs accident analyses for these plants using a number of computer codes. To model the primary and secondary circuits behaviour the system codes ATHLET, CATHARE, RELAP, TRAC are applied. Containment and pressure-suppression system are modelled with COCOSYS and MELCOR codes, the reactor power calculations (point and space-neutron kinetics) are made with DYN3D, NESTLE and CDF codes (FLUENT, TRIO) are used for some specific problems.An integral part of the current Czech project 'New Energy Sources' is selection of a new nuclear source. Within this and the preceding projects financed by the Czech Ministry of Industry and Trade and the EU PHARE, the Department carries and has carried out the systematic validation of thermal-hydraulic and reactor physics computer codes applying data obtained on several experimental facilities as well as the real operational data. One of the important components of the VVER 440/213 NPP is its containment with pressure suppression system (bubble condenser). For safety analyses of this system, computer codes of the type MELCOR and COCOSYS are used in the Czech Republic. These codes were developed for containments of classic PWRs or BWRs. In order to apply these codes for VVER 440 systems, their validation on experimental facilities must be performed.The paper provides concise information on these activities of the NRI and its Thermal-hydraulics Department. The containment system of the VVER 440/213, its functions and approaches to solution of its safety is described with definition of acceptance criteria. A detailed example of the containment code validation on EREC Test facility (LOCA and MSLB) and the consequent utilisation of the results for a real NPP purposes is included. An approach to

Analysis of the AD sequence in Zion plant using the March 1.1 code

International Nuclear Information System (INIS)

Oriolo, F.; Paci, S.

1985-01-01

The analyses of the AD sequences for the Zion power plant, made at the Pisa University, in the framework of the participation in the Source Tern Working Group. After a short description of the plant and the sequence under analysis, the model used for the reference computation and the results obtained using the March 1.1 code are shown. Together with the reference computation a series of parametric tests have been also made, concerning some input code variables, in order to ascertain their influence on the transient trend. The results of these analyses are shown in Appendix

Additional extensions to the NASCAP computer code, volume 3

Science.gov (United States)

Mandell, M. J.; Cooke, D. L.

1981-01-01

The ION computer code is designed to calculate charge exchange ion densities, electric potentials, plasma temperatures, and current densities external to a neutralized ion engine in R-Z geometry. The present version assumes the beam ion current and density to be known and specified, and the neutralizing electrons to originate from a hot-wire ring surrounding the beam orifice. The plasma is treated as being resistive, with an electron relaxation time comparable to the plasma frequency. Together with the thermal and electrical boundary conditions described below and other straightforward engine parameters, these assumptions suffice to determine the required quantities. The ION code, written in ASCII FORTRAN for UNIVAC 1100 series computers, is designed to be run interactively, although it can also be run in batch mode. The input is free-format, and the output is mainly graphical, using the machine-independent graphics developed for the NASCAP code. The executive routine calls the code's major subroutines in user-specified order, and the code allows great latitude for restart and parameter change.

Verification study of the FORE-2M nuclear/thermal-hydraulilc analysis computer code

International Nuclear Information System (INIS)

Coffield, R.D.; Tang, Y.S.; Markley, R.A.

1982-01-01

The verification of the LMFBR core transient performance code, FORE-2M, was performed in two steps. Different components of the computation (individual models) were verified by comparing with analytical solutions and with results obtained from other conventionally accepted computer codes (e.g., TRUMP, LIFE, etc.). For verification of the integral computation method of the code, experimental data in TREAT, SEFOR and natural circulation experiments in EBR-II were compared with the code calculations. Good agreement was obtained for both of these steps. Confirmation of the code verification for undercooling transients is provided by comparisons with the recent FFTF natural circulation experiments. (orig.)

Two-phase wall friction model for the trace computer code

International Nuclear Information System (INIS)

Wang Weidong

2005-01-01

The wall drag model in the TRAC/RELAP5 Advanced Computational Engine computer code (TRACE) has certain known deficiencies. For example, in an annular flow regime, the code predicts an unphysical high liquid velocity compared to the experimental data. To address those deficiencies, a new wall frictional drag package has been developed and implemented in the TRACE code to model the wall drag for two-phase flow system code. The modeled flow regimes are (1) annular/mist, (2) bubbly/slug, and (3) bubbly/slug with wall nucleation. The new models use void fraction (instead of flow quality) as the correlating variable to minimize the calculation oscillation. In addition, the models allow for transitions between the three regimes. The annular/mist regime is subdivided into three separate regimes for pure annular flow, annular flow with entrainment, and film breakdown. For adiabatic two-phase bubbly/slug flows, the vapor phase primarily exists outside of the boundary layer, and the wall shear uses single-phase liquid velocity for friction calculation. The vapor phase wall friction drag is set to zero for bubbly/slug flows. For bubbly/slug flows with wall nucleation, the bubbles are presented within the hydrodynamic boundary layer, and the two-phase wall friction drag is significantly higher with a pronounced mass flux effect. An empirical correlation has been studied and applied to account for nucleate boiling. Verification and validation tests have been performed, and the test results showed a significant code improvement. (authors)

R5FORCE: a program to compute fluid induced forces using hydrodynamic output from the RELAP5 code

International Nuclear Information System (INIS)

Watkins, J.C.

1983-01-01

This paper describes the computer code R5FORCE, a postprocessor to the RELAP5/MOD1 thermal-hydraulics code. R5FORCE computes piping hydraulic force/time histories that can be input into various structural analysis computer codes. R5FORCE solves the momentum conservation equation using the pressure and wall shear force terms rather than the pressure and fluid acceleration terms; eliminating potential instabilities associated with computing the time derivative in the fluid acceleration term. The updates to REALP5 required to generate the input data to R5FORCE are also discussed

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Functional modules F1-F8

International Nuclear Information System (INIS)

1997-03-01

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U.S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This volume consists of the section of the manual dealing with eight of the functional modules in the code. Those are: BONAMI - resonance self-shielding by the Bondarenko method; NITAWL-II - SCALE system module for performing resonance shielding and working library production; XSDRNPM - a one-dimensional discrete-ordinates code for transport analysis; XSDOSE - a module for calculating fluxes and dose rates at points outside a shield; KENO IV/S - an improved monte carlo criticality program; COUPLE; ORIGEN-S - SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms; ICE

SCALE: A modular code system for performing standardized computer analyses for licensing evaluation: Functional modules F1-F8

Energy Technology Data Exchange (ETDEWEB)

NONE

1997-03-01

This Manual represents Revision 5 of the user documentation for the modular code system referred to as SCALE. The history of the SCALE code system dates back to 1969 when the current Computational Physics and Engineering Division at Oak Ridge National Laboratory (ORNL) began providing the transportation package certification staff at the U.S. Atomic Energy Commission with computational support in the use of the new KENO code for performing criticality safety assessments with the statistical Monte Carlo method. From 1969 to 1976 the certification staff relied on the ORNL staff to assist them in the correct use of codes and data for criticality, shielding, and heat transfer analyses of transportation packages. However, the certification staff learned that, with only occasional use of the codes, it was difficult to become proficient in performing the calculations often needed for an independent safety review. Thus, shortly after the move of the certification staff to the U.S. Nuclear Regulatory Commission (NRC), the NRC staff proposed the development of an easy-to-use analysis system that provided the technical capabilities of the individual modules with which they were familiar. With this proposal, the concept of the Standardized Computer Analyses for Licensing Evaluation (SCALE) code system was born. This volume consists of the section of the manual dealing with eight of the functional modules in the code. Those are: BONAMI - resonance self-shielding by the Bondarenko method; NITAWL-II - SCALE system module for performing resonance shielding and working library production; XSDRNPM - a one-dimensional discrete-ordinates code for transport analysis; XSDOSE - a module for calculating fluxes and dose rates at points outside a shield; KENO IV/S - an improved monte carlo criticality program; COUPLE; ORIGEN-S - SCALE system module to calculate fuel depletion, actinide transmutation, fission product buildup and decay, and associated radiation source terms; ICE.

Computer code TOBUNRAD for PWR fuel bundle heat-up calculations

International Nuclear Information System (INIS)

Shimooke, Takanori; Yoshida, Kazuo

1979-05-01

The computer code TOBUNRAD developed is for analysis of ''fuel-bundle'' heat-up phenomena in a loss-of-coolant accident of PWR. The fuel bundle consists of fuel pins in square lattice; its behavior is different from that of individual pins during heat-up. The code is based on the existing TOODEE2 code which analyzes heat-up phenomena of single fuel pins, so that the basic models of heat conduction and transfer and coolant flow are the same as the TOODEE2's. In addition to the TOODEE2 features, unheated rods are modeled and radiation heat loss is considered between fuel pins, a fuel pin and other heat sinks. The TOBUNRAD code is developed by a new FORTRAN technique which makes it possible to interrupt a flow of program controls wherever desired, thereby attaching several subprograms to the main code. Users' manual for TOBUNRAD is presented: The basic program-structure by interruption method, physical and computational model in each sub-code, usage of the code and sample problems. (author)

GASFLOW computer code (physical models and input data)

International Nuclear Information System (INIS)

Muehlbauer, Petr

2007-11-01

The GASFLOW computer code was developed jointly by the Los Alamos National Laboratory, USA, and Forschungszentrum Karlsruhe, Germany. The code is primarily intended for calculations of the transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and in other facilities. The physical models and the input data are described, and a commented simple calculation is presented

A zero-dimensional EXTRAP computer code

International Nuclear Information System (INIS)

Karlsson, P.

1982-10-01

A zero-dimensional computer code has been designed for the EXTRAP experiment to predict the density and the temperature and their dependence upon paramenters such as the plasma current and the filling pressure of neutral gas. EXTRAP is a Z-pinch immersed in a vacuum octupole field and could be either linear or toroidal. In this code the density and temperature are assumed to be constant from the axis up to a breaking point from where they decrease linearly in the radial direction out to the plasma radius. All quantities, however, are averaged over the plasma volume thus giving the zero-dimensional character of the code. The particle, momentum and energy one-fluid equations are solved including the effects of the surrounding neutral gas and oxygen impurities. The code shows that the temperature and density are very sensitive to the shape of the plasma, flatter profiles giving higher temperatures and densities. The temperature, however, is not strongly affected for oxygen concentration less than 2% and is well above the radiation barrier even for higher concentrations. (Author)

The computer code system for reactor radiation shielding in design of nuclear power plant

International Nuclear Information System (INIS)

Li Chunhuai; Fu Shouxin; Liu Guilian

1995-01-01

The computer code system used in reactor radiation shielding design of nuclear power plant includes the source term codes, discrete ordinate transport codes, Monte Carlo and Albedo Monte Carlo codes, kernel integration codes, optimization code, temperature field code, skyshine code, coupling calculation codes and some processing codes for data libraries. This computer code system has more satisfactory variety of codes and complete sets of data library. It is widely used in reactor radiation shielding design and safety analysis of nuclear power plant and other nuclear facilities

Interface code between WIMS-AECL and RFSP-IST for coupling computing

International Nuclear Information System (INIS)

Xu Liangwang; Liu Yu; Jia Baoshan

2007-01-01

A code based on the protocols of Telnet and FTP is developed with C++ for coupling computing between WIMS-AECL and RFSP-IST. the input document of WIMS-AECL and RFSP-ISP cna be generated automatically and be submitted to server, the output document will be downloaded by the end of computing. the function of analyzing standard output document is also included in this code. After simple updating, this code can meet the requirement of other code using input document, e.g. CATHENA. A pilot study of the relation between void fraction and reactivity in TACR, some valuable conclusions has been achieved. (authors)

Relación entre enfermedades crónicas y salud-enfermedad bucal en adultos brasileros de bajo nivel socioeconómico

Directory of Open Access Journals (Sweden)

Márcia Cançado Figueiredo

Full Text Available El presente trabajo representó un estudio de prevalencia, transversal, de observación analítica, realizado en el barrio Figueirinha, en el municipio de Xangri-Lá, localizado en el litoral norte del Estado de Río Grande do Sul, Brasil. Objetivo del mismo fue realizar un relevamiento de las condiciones de salud bucal de los habitantes adultos registrados en el programa Salud de la Familia Figueirinha, portadores de diabetes mellitus, hipertensión arterial o ambas patologías y verificar la existencia de alguna correlación con la salud-enfermedad bucal. Material y Método. Se recogieron datos de 218 habitantes adultos, de los cuales 35 estaban registrados en el Programa Hiperdía (Estrategia Salud de la Familia Figueirinha como portadores de las patologías sistémicas citadas anteriormente. Para la valoración del estado de salud bucal, se evaluó: presencia de placa bacteriana, sangrado gingival y el índice CPOD (dientes cariados, perdidos y obturados. Resultados: de los 218 habitantes adultos, el 11.5% eran pacientes hipertensos, el 2.3% portadores de diabetes mellitus y el 2.3% portaban ambas enfermedades. Del examen bucal resultó que el 67,9% presentaba placa bacteriana y el 58,7% sangrado gingival. Se verificó una correlación positiva entre el número de pérdidas dentarias, la hipertensión arterial y diabetes mellitus con un resultado estadísticamente significante (p≥0,015. Conclusiones: Es de suma importancia que las personas portadoras de enfermedades sistémicas como la diabetes mellitus y la hipertensión arterial estén integradas a un programa de promoción de salud que tenga en cuenta sus necesidades específicas para el mantenimiento de la salud bucal

Independent assessment of the TRAC-BD1/MOD1 computer code at the Idaho National Engineering Laboratory

International Nuclear Information System (INIS)

Wilson, G.E.; Charboneau, B.L.; Dallman, R.J.; Kullberg, C.M.; Wagner, K.C.; Wheatley, P.D.

1984-01-01

Under auspices of the United States Nuclear Regulatory Commission, their primary boiling water reactor safety analysis code (TRAC-BWR) is being assessed with simulations of a wide range of experimental data. The FY-1984 assessment activities were associated with the latest version (TRAC-BD1/MOD1) of this code. Typical results of the assessment studies are given. Conclusions formulated from these results are presented. These calculations relate to the overall applicability of the current code to safety analysis, and to future work which would further enhance the code's quality and ease of use

Tipos de tabaquismo como factor de riesgo asociado a cáncer bucal. Reporte de dos casos

Directory of Open Access Journals (Sweden)

Martha Rebolledo Cobos

2012-01-01

Full Text Available El tabaquismo corresponde a uno de los hábitos más comunes en la población mundial, tanto en hombres como en mujeres, siendo un factor de riesgo para el desarrollo de lesiones neoplásicas malignas y premalignas en la cavidad bucal. Las diferentes formas de utilización de este hábito, como fumar cigarrillo de manera convencional, tabaquismo invertido y pasivo, presentan variables en cuanto a la incidencia y prevalencia de aparición de tumores, así como el tipo, cantidad y la intensidad de tabaco consumido. Las células epiteliales que recubren la mucosa bucal reaccionan como mecanismos de defensa ante el estímulo del humo y la combustión, al igual que frente a los sustancias químico- tóxicas que de ellos provienen; manifestándose como lesiones que varían entre leucoedemas, hiperqueratosis nicotínicas, fibrosis epiteliales, lesiones precancerosas, carcinomas in situ, hasta el desarrollo de verdaderas neoplasias malignas. El estomatólogo juega un rol fundamental en el diagnóstico oportuno y la prevención de estas afecciones, puesto que está entrenado para detectar cualquier lesión en estado incipiente, y así simplificar su tratamiento, mejorando la calidad de vida del paciente; pero mucho más importante que detectar la lesión es prevenir que aparezca, orientando, población y combatiendo los factores de riesgo. Se presentan dos casos de pacientes fumadoras activas que acudieron al servicio de Estomatología y Cirugía Oral de la Fundación Universitaria San Martín, sede Puerto Colombia, por presentar lesiones tumorales en cavidad bucal semejantes clínicamente a carcinomas bucales; a quienes se les realizaron biopsias que confirmaron diagnósticos de carcinoma escamocelular.

TPASS: a gamma-ray spectrum analysis and isotope identification computer code

International Nuclear Information System (INIS)

Dickens, J.K.

1981-03-01

The gamma-ray spectral data-reduction and analysis computer code TPASS is described. This computer code is used to analyze complex Ge(Li) gamma-ray spectra to obtain peak areas corrected for detector efficiencies, from which are determined gamma-ray yields. These yields are compared with an isotope gamma-ray data file to determine the contributions to the observed spectrum from decay of specific radionuclides. A complete FORTRAN listing of the code and a complex test case are given

Development of the computer code system for the analyses of PWR core

International Nuclear Information System (INIS)

Tsujimoto, Iwao; Naito, Yoshitaka.

1992-11-01

This report is one of the materials for the work titled 'Development of the computer code system for the analyses of PWR core phenomena', which is performed under contracts between Shikoku Electric Power Company and JAERI. In this report, the numerical method adopted in our computer code system are described, that is, 'The basic course and the summary of the analysing method', 'Numerical method for solving the Boltzmann equation', 'Numerical method for solving the thermo-hydraulic equations' and 'Description on the computer code system'. (author)

Sandia reactor kinetics codes: SAK and PK1D

International Nuclear Information System (INIS)

Pickard, P.S.; Odom, J.P.

1978-01-01

The Sandia Kinetics code (SAK) is a one-dimensional coupled thermal-neutronics transient analysis code for use in simulation of reactor transients. The time-dependent cross section routines allow arbitrary time-dependent changes in material properties. The one-dimensional heat transfer routines are for cylindrical geometry and allow arbitrary mesh structure, temperature-dependent thermal properties, radiation treatment, and coolant flow and heat-transfer properties at the surface of a fuel element. The Point Kinetics 1 Dimensional Heat Transfer Code (PK1D) solves the point kinetics equations and has essentially the same heat-transfer treatment as SAK. PK1D can address extended reactor transients with minimal computer execution time

Code system to compute radiation dose in human phantoms

International Nuclear Information System (INIS)

Ryman, J.C.; Cristy, M.; Eckerman, K.F.; Davis, J.L.; Tang, J.S.; Kerr, G.D.

1986-01-01

Monte Carlo photon transport code and a code using Monte Carlo integration of a point kernel have been revised to incorporate human phantom models for an adult female, juveniles of various ages, and a pregnant female at the end of the first trimester of pregnancy, in addition to the adult male used earlier. An analysis code has been developed for deriving recommended values of specific absorbed fractions of photon energy. The computer code system and calculational method are described, emphasizing recent improvements in methods

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)

H0 precessor computer code

International Nuclear Information System (INIS)

van Dyck, O.B.; Floyd, R.A.

1981-05-01

A spin precessor using H - to H 0 stripping, followed by small precession magnets, has been developed for the LAMPF 800-MeV polarized H - beam. The performance of the system was studied with the computer code documented in this report. The report starts from the fundamental physics of a system of spins with hyperfine coupling in a magnetic field and contains many examples of beam behavior as calculated by the program

Energy-1: a computer code for thermohydraulic analysis of a LMBFR rod bundles, in a mixed convection regime

International Nuclear Information System (INIS)

Braz Filho, F.A.

1987-01-01

A code was set up in which velocity, temperature and pressure distributions are calculated, using the porous body model, for a rod bundle where mixed convection regime plays an important role. Results show satisfactory agreement with experimental data, as well as a reduction in computational time when compared to ENERGY-III code. (author) [pt

A three-dimensional magnetostatics computer code for insertion devices

International Nuclear Information System (INIS)

Chubar, O.; Elleaume, P.; Chavanne, J.

1998-01-01

RADIA is a three-dimensional magnetostatics computer code optimized for the design of undulators and wigglers. It solves boundary magnetostatics problems with magnetized and current-carrying volumes using the boundary integral approach. The magnetized volumes can be arbitrary polyhedrons with non-linear (iron) or linear anisotropic (permanent magnet) characteristics. The current-carrying elements can be straight or curved blocks with rectangular cross sections. Boundary conditions are simulated by the technique of mirroring. Analytical formulae used for the computation of the field produced by a magnetized volume of a polyhedron shape are detailed. The RADIA code is written in object-oriented C++ and interfaced to Mathematica (Mathematica is a registered trademark of Wolfram Research, Inc.). The code outperforms currently available finite-element packages with respect to the CPU time of the solver and accuracy of the field integral estimations. An application of the code to the case of a wedge-pole undulator is presented

Influência do ambiente familiar sobre a saúde bucal de crianças: uma revisão sistemática Influence of family environment on children's oral health: a systematic review

Directory of Open Access Journals (Sweden)

Aline Rogéria Freire de Castilho

2013-04-01

Full Text Available OBJETIVO: Envolver modelos atuais e comprovações científicas sobre a influência de comportamentos de saúde bucal dos pais na cárie dentária de suas crianças. FONTES: Artigos do MEDLINE publicados entre 1980 e junho de 2012. Foram analisados artigos de pesquisa originais tratando do comportamento dos pais quanto à saúde bucal. Um total de 218 citações foi analisado e 13 artigos foram incluídos na análise. Os estudos foram considerados elegíveis para análise se atendessem aos seguintes critérios de inclusão: (1 avaliassem uma possível associação entre cáries dentárias e o comportamento dos pais relacionado à saúde bucal; e (2 se a metodologia do estudo incluísse exame clínico bucal. Os principais termos de pesquisa foram "saúde bucal", "atitudes dos pais", "conhecimento dos pais" e "cáries dentárias". RESUMO DOS ACHADOS: Ao todo, 13 estudos experimentais contribuíram com dados para a síntese. Também foram considerados trabalhos, revisões e capítulos originais em livros didáticos. CONCLUSÃO: Os hábitos de saúde dental dos pais influenciam a saúde bucal de seus filhos. São necessários programas de educação em saúde bucal com ações preventivas para proporcionar não apenas saúde bucal adequada às crianças, mas também uma melhor qualidade de vida. Deve ser dada atenção especial a toda a família, com relação a seu estilo de vida e hábitos relacionados à saúde bucal.OBJECTIVE: To review current models and scientific evidence on the influence of parents' oral health behaviors on their children's dental caries. SOURCES: MEDLINE articles published between 1980 and June, 2012. Original research articles on parents' oral health behavior were reviewed. A total of 218 citations were retrieved, and 13 articles were included in the analysis. The studies were eligible for review if they matched the following inclusion criteria: (1 they evaluated a possible association between dental caries and parents

Probabilistic evaluations for CANTUP computer code analysis improvement

International Nuclear Information System (INIS)

Florea, S.; Pavelescu, M.

2004-01-01

Structural analysis with finite element method is today an usual way to evaluate and predict the behavior of structural assemblies subject to hard conditions in order to ensure their safety and reliability during their operation. A CANDU 600 fuel channel is an example of an assembly working in hard conditions, in which, except the corrosive and thermal aggression, long time irradiation, with implicit consequences on material properties evolution, interferes. That leads inevitably to material time-dependent properties scattering, their dynamic evolution being subject to a great degree of uncertainness. These are the reasons for developing, in association with deterministic evaluations with computer codes, the probabilistic and statistical methods in order to predict the structural component response. This work initiates the possibility to extend the deterministic thermomechanical evaluation on fuel channel components to probabilistic structural mechanics approach starting with deterministic analysis performed with CANTUP computer code which is a code developed to predict the long term mechanical behavior of the pressure tube - calandria tube assembly. To this purpose the structure of deterministic calculus CANTUP computer code has been reviewed. The code has been adapted from LAHEY 77 platform to Microsoft Developer Studio - Fortran Power Station platform. In order to perform probabilistic evaluations, it was added a part to the deterministic code which, using a subroutine from IMSL library from Microsoft Developer Studio - Fortran Power Station platform, generates pseudo-random values of a specified value. It was simulated a normal distribution around the deterministic value and 5% standard deviation for Young modulus material property in order to verify the statistical calculus of the creep behavior. The tube deflection and effective stresses were the properties subject to probabilistic evaluation. All the values of these properties obtained for all the values for

Parameters that affect parallel processing for computational electromagnetic simulation codes on high performance computing clusters

Science.gov (United States)

Moon, Hongsik

What is the impact of multicore and associated advanced technologies on computational software for science? Most researchers and students have multicore laptops or desktops for their research and they need computing power to run computational software packages. Computing power was initially derived from Central Processing Unit (CPU) clock speed. That changed when increases in clock speed became constrained by power requirements. Chip manufacturers turned to multicore CPU architectures and associated technological advancements to create the CPUs for the future. Most software applications benefited by the increased computing power the same way that increases in clock speed helped applications run faster. However, for Computational ElectroMagnetics (CEM) software developers, this change was not an obvious benefit - it appeared to be a detriment. Developers were challenged to find a way to correctly utilize the advancements in hardware so that their codes could benefit. The solution was parallelization and this dissertation details the investigation to address these challenges. Prior to multicore CPUs, advanced computer technologies were compared with the performance using benchmark software and the metric was FLoting-point Operations Per Seconds (FLOPS) which indicates system performance for scientific applications that make heavy use of floating-point calculations. Is FLOPS an effective metric for parallelized CEM simulation tools on new multicore system? Parallel CEM software needs to be benchmarked not only by FLOPS but also by the performance of other parameters related to type and utilization of the hardware, such as CPU, Random Access Memory (RAM), hard disk, network, etc. The codes need to be optimized for more than just FLOPs and new parameters must be included in benchmarking. In this dissertation, the parallel CEM software named High Order Basis Based Integral Equation Solver (HOBBIES) is introduced. This code was developed to address the needs of the

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong

International Nuclear Information System (INIS)

Syahrir

1996-01-01

Selection of Computer Codes for Shallow Land Waste Disposal in PPTA Serpong. Models and computer codes have been selected for safety assessment of near surface waste disposal facility. This paper provides a summary and overview of the methodology and codes selected. The methodology allows analyses of dose to individuals from offsite releases under normal conditions as well as on-site doses to inadvertent intruders. A demonstration in the case of shallow land waste disposal in Nuclear Research Establishment are in Serpong has been given for normal release scenario. The assessment includes infiltration of rainfall, source-term, ground water (well) and surface water transport, food-chain and dosimetry. The results show dose history of maximally exposed individuals. The codes used are VS2DT, PAGAN and GENII. The application of 1 m silt loam as a moisture barrier cover decreases flow in the disposal unit by a factor of 27. The selected radionuclides show variety of dose histories according to their chemical and physical characteristics and behavior in the environment

Hábitos bucales deformantes en un consultorio del médico de la familia en Camagüey, Cuba

OpenAIRE

Lima Álvarez, Magda; Romero Zaldívar, Esperanza; Pérez Cederrón, Ricardo Alberto

2004-01-01

Se realizó un estudio de intervención en la población de 5 a 18 años del Consultorio 18 del área Oeste de Camagüey desde noviembre de 1998 hasta enero de 2001, con el objetivo de evaluar la disminución de los hábitos bucales deformantes, determinar el tipo de oclusión según grupos de edades, identificar los hábitos bucales deformantes presentes y relacionar los mismos con el tipo de oclusión. El universo estuvo formado por 96 pacientes, de los cuales 84 fueron encuestados, interconsultados y ...

Avaliação das condições de saúde bucal de Portadores de Necessidades Especiais

Directory of Open Access Journals (Sweden)

Faldryene de Sousa Queiroz

Full Text Available Objetivo: O objetivo deste trabalho foi avaliar as condições de saúde bucal de Portadores de Necessidades Especiais (PNE de uma Escola Especial da cidade de Patos-PB, bem como identificar as dificuldades apontadas por seus responsáveis para a manutenção da saúde bucal dos mesmos. Metodologia: A população-alvo deste estudo foi composta por 74 alunos, de ambos os sexos, regularmente matriculados, que preencheram os critérios de inclusão previamente estabelecidos e por seus responsáveis. O estudo foi conduzido em duas etapas: a primeira consistiu na aplicação de um formulário aos responsáveis pelos PNE, e a segunda, na realização de um exame clínico intrabucal, realizado por um examinador e anotador previamente calibrados, em que se avaliaram as condições de saúde bucal dos alunos por meio do Índice de Cárie Dentária (CPO-D, do Índice de Higiene Oral Simplificado (IHOS e da presença de Trauma Dentário. Resultado: Observou-se que 75,4% dos alunos já haviam recebido algum tipo de tratamento odontológico; destes, 50,9% afirmaram ter sido na Unidade Básica de Saúde. O CPO-D médio foi de 12,6 (±8,4, 52% apresentaram higiene oral deficiente e o trauma dental foi observado em 19,3% dos alunos analisados. Com relação ao parto, 51% das mães relataram ter tido uma gestação normal e 54,4% nunca haviam sido orientadas com relação aos cuidados com a saúde bucal do filho. Entre as dificuldades relatadas pelos responsáveis para manter a saúde bucal do PNE, 33,3% afirmaram ser encontrar um Dentista que o atenda e 33,3% apontaram o custo do tratamento. Conclusão: Os altos índices revelados pelo CPO-D, bem como a higiene oral deficiente, somados às dificuldades relatadas em se realizar o acompanhamento odontológico desses indivíduos, mostram a necessidade da implementação de políticas públicas mais voltadas à atenção a esses pacientes.

Multitasking the code ARC3D. [for computational fluid dynamics

Science.gov (United States)

Barton, John T.; Hsiung, Christopher C.

1986-01-01

The CRAY multitasking system was developed in order to utilize all four processors and sharply reduce the wall clock run time. This paper describes the techniques used to modify the computational fluid dynamics code ARC3D for this run and analyzes the achieved speedup. The ARC3D code solves either the Euler or thin-layer N-S equations using an implicit approximate factorization scheme. Results indicate that multitask processing can be used to achieve wall clock speedup factors of over three times, depending on the nature of the program code being used. Multitasking appears to be particularly advantageous for large-memory problems running on multiple CPU computers.

La sugestión en una etapa del sueño para el tratamiento de hábitos bucales deformantes

Directory of Open Access Journals (Sweden)

Arlene Liset Corrales León

2014-12-01

Full Text Available Introducción: en su labor diaria el estomatólogo atiende a los niños con hábitos bucales deformantes y debe tratar sus causas. Por tanto, requiere conocimientos sobre la psicología infantil y de aspectos relacionados con hábitos. Objetivo: aplicar la sugestión en la fase de sueño con movimientos oculares rápidos como técnica sugestiva por parte de la familia, para controlar estos hábitos bucales deformantes en edades tempranas, teniendo en cuenta la prevalencia de hábitos bucales deformantes en la muestra, su distribución según el sexo y la edad, la relación entre la influencia familiar y la eliminación de hábitos bucales deformantes. Material y método: se realizó un estudio longitudinal y prospectivo en la población de 2 a 18 años de los consultorios 15 y 16 del policlínico universitario "Luis Augusto Turcios Lima" de Pinar del Río, desde septiembre de 2011 a febrero de 2012. El universo estuvo integrado por 33 pacientes, de ellos, se seleccionaron 20 los que practicaban hábitos deformantes. Para el análisis de la información, se aplicó el método estadístico descriptivo y porcentual. El procesamiento de los datos se realizó mediante el sistema estadístico SPSS/PC. Resultados: el hábito deformante más frecuente fue el empuje lingual. El grupo de edades entre 5-9 años fue el más afectado. Se comprobó un cambio favorable en el estado de salud de los niños al disminuir la práctica de hábitos bucales deformantes. Conclusiones: la aplicabilidad de la terapia aplicada fue buena en más de la mitad de la muestra.

Investigation of the efficiency and qualification of computer codes for PSA

International Nuclear Information System (INIS)

Andernacht, M.; Dinsmore, S.

1992-01-01

An international selection of computer codes for the quantification of level 1 PSA models was evaluated due to the consistence of results of different Benchmark exercises. The exercises in this project are based on those developed during the first benchmark project (Phase I). Due to several large differences in the results during Phase I of the Benchmark, the exercises in Phase II were more precisely defined. Due to the improved definition of the benchmark exercises, the results delivered from the different computer codes for Phase II are much more consistent. In general, the results of Benchmark II show, that the exercises were defined well enough to allow consistant results to be generated. Thus, the exercises can also be used to support the evaluation of additional PSA programs. (orig.) [de

Analysis of parallel computing performance of the code MCNP

International Nuclear Information System (INIS)

Wang Lei; Wang Kan; Yu Ganglin

2006-01-01

Parallel computing can reduce the running time of the code MCNP effectively. With the MPI message transmitting software, MCNP5 can achieve its parallel computing on PC cluster with Windows operating system. Parallel computing performance of MCNP is influenced by factors such as the type, the complexity level and the parameter configuration of the computing problem. This paper analyzes the parallel computing performance of MCNP regarding with these factors and gives measures to improve the MCNP parallel computing performance. (authors)

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

Computer codes for evaluation of control room habitability (HABIT)

International Nuclear Information System (INIS)

Stage, S.A.

1996-06-01

This report describes the Computer Codes for Evaluation of Control Room Habitability (HABIT). HABIT is a package of computer codes designed to be used for the evaluation of control room habitability in the event of an accidental release of toxic chemicals or radioactive materials. Given information about the design of a nuclear power plant, a scenario for the release of toxic chemicals or radionuclides, and information about the air flows and protection systems of the control room, HABIT can be used to estimate the chemical exposure or radiological dose to control room personnel. HABIT is an integrated package of several programs that previously needed to be run separately and required considerable user intervention. This report discusses the theoretical basis and physical assumptions made by each of the modules in HABIT and gives detailed information about the data entry windows. Sample runs are given for each of the modules. A brief section of programming notes is included. A set of computer disks will accompany this report if the report is ordered from the Energy Science and Technology Software Center. The disks contain the files needed to run HABIT on a personal computer running DOS. Source codes for the various HABIT routines are on the disks. Also included are input and output files for three demonstration runs

High-performance computational fluid dynamics: a custom-code approach

International Nuclear Information System (INIS)

Fannon, James; Náraigh, Lennon Ó; Loiseau, Jean-Christophe; Valluri, Prashant; Bethune, Iain

2016-01-01

We introduce a modified and simplified version of the pre-existing fully parallelized three-dimensional Navier–Stokes flow solver known as TPLS. We demonstrate how the simplified version can be used as a pedagogical tool for the study of computational fluid dynamics (CFDs) and parallel computing. TPLS is at its heart a two-phase flow solver, and uses calls to a range of external libraries to accelerate its performance. However, in the present context we narrow the focus of the study to basic hydrodynamics and parallel computing techniques, and the code is therefore simplified and modified to simulate pressure-driven single-phase flow in a channel, using only relatively simple Fortran 90 code with MPI parallelization, but no calls to any other external libraries. The modified code is analysed in order to both validate its accuracy and investigate its scalability up to 1000 CPU cores. Simulations are performed for several benchmark cases in pressure-driven channel flow, including a turbulent simulation, wherein the turbulence is incorporated via the large-eddy simulation technique. The work may be of use to advanced undergraduate and graduate students as an introductory study in CFDs, while also providing insight for those interested in more general aspects of high-performance computing. (paper)

High-performance computational fluid dynamics: a custom-code approach

Science.gov (United States)

Fannon, James; Loiseau, Jean-Christophe; Valluri, Prashant; Bethune, Iain; Náraigh, Lennon Ó.

2016-07-01

We introduce a modified and simplified version of the pre-existing fully parallelized three-dimensional Navier-Stokes flow solver known as TPLS. We demonstrate how the simplified version can be used as a pedagogical tool for the study of computational fluid dynamics (CFDs) and parallel computing. TPLS is at its heart a two-phase flow solver, and uses calls to a range of external libraries to accelerate its performance. However, in the present context we narrow the focus of the study to basic hydrodynamics and parallel computing techniques, and the code is therefore simplified and modified to simulate pressure-driven single-phase flow in a channel, using only relatively simple Fortran 90 code with MPI parallelization, but no calls to any other external libraries. The modified code is analysed in order to both validate its accuracy and investigate its scalability up to 1000 CPU cores. Simulations are performed for several benchmark cases in pressure-driven channel flow, including a turbulent simulation, wherein the turbulence is incorporated via the large-eddy simulation technique. The work may be of use to advanced undergraduate and graduate students as an introductory study in CFDs, while also providing insight for those interested in more general aspects of high-performance computing.

Evaluating computer program performance on the CRAY-1

International Nuclear Information System (INIS)

Rudsinski, L.; Pieper, G.W.

1979-01-01

The Advanced Scientific Computers Project of Argonne's Applied Mathematics Division has two objectives: to evaluate supercomputers and to determine their effect on Argonne's computing workload. Initial efforts have focused on the CRAY-1, which is the only advanced computer currently available. Users from seven Argonne divisions executed test programs on the CRAY and made performance comparisons with the IBM 370/195 at Argonne. This report describes these experiences and discusses various techniques for improving run times on the CRAY. Direct translations of code from scalar to vector processor reduced running times as much as two-fold, and this reduction will become more pronounced as the CRAY compiler is developed. Further improvement (two- to ten-fold) was realized by making minor code changes to facilitate compiler recognition of the parallel and vector structure within the programs. Finally, extensive rewriting of the FORTRAN code structure reduced execution times dramatically, in three cases by a factor of more than 20; and even greater reduction should be possible by changing algorithms within a production code. It is condluded that the CRAY-1 would be of great benefit to Argonne researchers. Existing codes could be modified with relative ease to run significantly faster than on the 370/195. More important, the CRAY would permit scientists to investigate complex problems currently deemed infeasibile on traditional scalar machines. Finally, an interface between the CRAY-1 and IBM computers such as the 370/195, scheduled by Cray Research for the first quarter of 1979, would considerably facilitate the task of integrating the CRAY into Argonne's Central Computing Facility. 13 tables

Available computer codes and data for radiation transport analysis

International Nuclear Information System (INIS)

Trubey, D.K.; Maskewitz, B.F.; Roussin, R.W.

1975-01-01

The Radiation Shielding Information Center (RSIC), sponsored and supported by the Energy Research and Development Administration (ERDA) and the Defense Nuclear Agency (DNA), is a technical institute serving the radiation transport and shielding community. It acquires, selects, stores, retrieves, evaluates, analyzes, synthesizes, and disseminates information on shielding and ionizing radiation transport. The major activities include: (1) operating a computer-based information system and answering inquiries on radiation analysis, (2) collecting, checking out, packaging, and distributing large computer codes, and evaluated and processed data libraries. The data packages include multigroup coupled neutron-gamma-ray cross sections and kerma coefficients, other nuclear data, and radiation transport benchmark problem results

New coding technique for computer generated holograms.

Science.gov (United States)

Haskell, R. E.; Culver, B. C.

1972-01-01

A coding technique is developed for recording computer generated holograms on a computer controlled CRT in which each resolution cell contains two beam spots of equal size and equal intensity. This provides a binary hologram in which only the position of the two dots is varied from cell to cell. The amplitude associated with each resolution cell is controlled by selectively diffracting unwanted light into a higher diffraction order. The recording of the holograms is fast and simple.

WSRC approach to validation of criticality safety computer codes

International Nuclear Information System (INIS)

Finch, D.R.; Mincey, J.F.

1991-01-01

Recent hardware and operating system changes at Westinghouse Savannah River Site (WSRC) have necessitated review of the validation for JOSHUA criticality safety computer codes. As part of the planning for this effort, a policy for validation of JOSHUA and other criticality safety codes has been developed. This policy will be illustrated with the steps being taken at WSRC. The objective in validating a specific computational method is to reliably correlate its calculated neutron multiplication factor (K eff ) with known values over a well-defined set of neutronic conditions. Said another way, such correlations should be: (1) repeatable; (2) demonstrated with defined confidence; and (3) identify the range of neutronic conditions (area of applicability) for which the correlations are valid. The general approach to validation of computational methods at WSRC must encompass a large number of diverse types of fissile material processes in different operations. Special problems are presented in validating computational methods when very few experiments are available (such as for enriched uranium systems with principal second isotope 236 U). To cover all process conditions at WSRC, a broad validation approach has been used. Broad validation is based upon calculation of many experiments to span all possible ranges of reflection, nuclide concentrations, moderation ratios, etc. Narrow validation, in comparison, relies on calculations of a few experiments very near anticipated worst-case process conditions. The methods and problems of broad validation are discussed

Accident and safety analyses for the HTR-modul. Partial project 1: Computer codes for system behaviour calculation. Final report. Pt. 2

International Nuclear Information System (INIS)

Lohnert, G.; Becker, D.; Dilcher, L.; Doerner, G.; Feltes, W.; Gysler, G.; Haque, H.; Kindt, T.; Kohtz, N.; Lange, L.; Ragoss, H.

1993-08-01

The project encompasses the following project tasks and problems: (1) Studies relating to complete failure of the main heat transfer system; (2) Pebble flow; (3) Development of computer codes for detailed calculation of hypothetical accidents; (a) the THERMIX/RZKRIT temperature buildup code (covering a.o. a variation to include exothermal heat sources); (b) the REACT/THERMIX corrosion code (variation taking into account extremely severe air ingress into the primary loop); (c) the GRECO corrosion code (variation for treating extremely severe water ingress into the primary loop); (d) the KIND transients code (for treating extremely fast transients during reactivity incidents. (4) Limiting devices for safety-relevant quantities. (5) Analyses relating to hypothetical accidents. (a) hypothetical air ingress; (b) effects on the fuel particles induced by fast transients. The problems of the various tasks are defined in detail and the main results obtained are explained. The contributions reporting the various project tasks and activities have been prepared for separate retrieval from the database. (orig./HP) [de

Hauser*5, a computer code to calculate nuclear cross sections

International Nuclear Information System (INIS)

Mann, F.M.

1979-07-01

HAUSER*5 is a computer code that uses the statistical (Hauser-Feshbach) model, the pre-equilibrium model, and a statistical model of direct reactions to predict nuclear cross sections. The code is unrestricted as to particle type, includes fission and capture, makes width-fluctuation corrections, and performs three-body calculations - all in minimum computer time. Transmission coefficients can be generated internally or supplied externally. This report describes equations used, necessary input, and resulting output. 2 figures, 4 tables

NADAC and MERGE: computer codes for processing neutron activation analysis data

International Nuclear Information System (INIS)

Heft, R.E.; Martin, W.E.

1977-01-01

Absolute disintegration rates of specific radioactive products induced by neutron irradition of a sample are determined by spectrometric analysis of gamma-ray emissions. Nuclide identification and quantification is carried out by a complex computer code GAMANAL (described elsewhere). The output of GAMANAL is processed by NADAC, a computer code that converts the data on observed distintegration rates to data on the elemental composition of the original sample. Computations by NADAC are on an absolute basis in that stored nuclear parameters are used rather than the difference between the observed disintegration rate and the rate obtained by concurrent irradiation of elemental standards. The NADAC code provides for the computation of complex cases including those involving interrupted irradiations, parent and daughter decay situations where the daughter may also be produced independently, nuclides with very short half-lives compared to counting interval, and those involving interference by competing neutron-induced reactions. The NADAC output consists of a printed report, which summarizes analytical results, and a card-image file, which can be used as input to another computer code MERGE. The purpose of MERGE is to combine the results of multiple analyses and produce a single final answer, based on all available information, for each element found

Survey of computer codes applicable to waste facility performance evaluations

International Nuclear Information System (INIS)

Alsharif, M.; Pung, D.L.; Rivera, A.L.; Dole, L.R.

1988-01-01

This study is an effort to review existing information that is useful to develop an integrated model for predicting the performance of a radioactive waste facility. A summary description of 162 computer codes is given. The identified computer programs address the performance of waste packages, waste transport and equilibrium geochemistry, hydrological processes in unsaturated and saturated zones, and general waste facility performance assessment. Some programs also deal with thermal analysis, structural analysis, and special purposes. A number of these computer programs are being used by the US Department of Energy, the US Nuclear Regulatory Commission, and their contractors to analyze various aspects of waste package performance. Fifty-five of these codes were identified as being potentially useful on the analysis of low-level radioactive waste facilities located above the water table. The code summaries include authors, identification data, model types, and pertinent references. 14 refs., 5 tabs

CAT: a computer code for the automated construction of fault trees

International Nuclear Information System (INIS)

Apostolakis, G.E.; Salem, S.L.; Wu, J.S.

1978-03-01

A computer code, CAT (Computer Automated Tree, is presented which applies decision table methods to model the behavior of components for systematic construction of fault trees. The decision tables for some commonly encountered mechanical and electrical components are developed; two nuclear subsystems, a Containment Spray Recirculation System and a Consequence Limiting Control System, are analyzed to demonstrate the applications of CAT code

Gastos privados com saúde bucal no Brasil: análise dos dados da Pesquisa de Orçamentos Familiares, 2008-2009

Directory of Open Access Journals (Sweden)

Andreia Morales Cascaes

Full Text Available Resumo: O objetivo foi analisar os gastos privados com assistência odontológica e produtos de higiene bucal dos brasileiros. Foram analisados dados de 55.970 domicílios pesquisados na Pesquisa de Orçamentos Familiares de 2008-2009. Os gastos foram descritos segundo macrorregiões, estados e capitais do Brasil e de acordo com características socioeconômicas e demográficas dos domicílios (sexo, idade, cor da pele e escolaridade do chefe, renda domiciliar per capita e presença de idoso no domicílio. Os brasileiros gastaram em média no ano R$ 42,19 com serviços de assistência odontológica e R$ 10,27 com produtos de higiene bucal. Desigualdades sociais na distribuição desses gastos segundo as características dos moradores dos domicílios e segundo as diferentes macrorregiões, estados e capitais do país foram encontradas. O presente estudo evidenciou com detalhes quanto e com o que gastam os brasileiros com assistência odontológica e com produtos de higiene bucal. O monitoramento e avaliação desses gastos são condições fundamentais para avaliação e orientação de políticas públicas em saúde bucal.

Description of computer code PRINS, Program for Interpreting Gamma Spectra, developed at ENEA

Energy Technology Data Exchange (ETDEWEB)

Borsari, R. [ENEA, Centro Ricerche `E. Clementel`, Bologna (Italy). Dip. Energia

1995-11-01

The computer code PRINS, program for interpreting gamma Spectra, has been developed in collaboration with CENG/SECC (Centre Etude Nucleaire Grenoble / Service Etude Comportement du Combustible). Later it has been updated and improved at ENEA. Properties of the PRINS code are: (1) A powerful algorithm to locate the peaks; (2) An accurate evaluation of the errors; (3) Possibility of an automatic channels-energy calibration.

Verification of the network flow and transport/distributed velocity (NWFT/DVM) computer code

International Nuclear Information System (INIS)

Duda, L.E.

1984-05-01

The Network Flow and Transport/Distributed Velocity Method (NWFT/DVM) computer code was developed primarily to fulfill a need for a computationally efficient ground-water flow and contaminant transport capability for use in risk analyses where, quite frequently, large numbers of calculations are required. It is a semi-analytic, quasi-two-dimensional network code that simulates ground-water flow and the transport of dissolved species (radionuclides) in a saturated porous medium. The development of this code was carried out under a program funded by the US Nuclear Regulatory Commission (NRC) to develop a methodology for assessing the risk from disposal of radioactive wastes in deep geologic formations (FIN: A-1192 and A-1266). In support to the methodology development program, the NRC has funded a separate Maintenance of Computer Programs Project (FIN: A-1166) to ensure that the codes developed under A-1192 or A-1266 remain consistent with current operating systems, are as error-free as possible, and have up-to-date documentations for reference by the NRC staff. Part of this effort would include verification and validation tests to assure that a code correctly performs the operations specified and/or is representing the processes or system for which it is intended. This document contains four verification problems for the NWFT/DVM computer code. Two of these problems are analytical verifications of NWFT/DVM where results are compared to analytical solutions. The other two are code-to-code verifications where results from NWFT/DVM are compared to those of another computer code. In all cases NWFT/DVM showed good agreement with both the analytical solutions and the results from the other code

Indicadores de saúde bucal e qualidade de vida

OpenAIRE

Henriques, Cristiane [UNESP

2007-01-01

O objetivo deste estudo foi avaliar a autopercepção e as condições de saúde bucal de pacientes maiores de 50 anos, residentes em Araraquara-SP, verificando o grau de reprodutibilidade dos indicadores empregados.O planejamento estatístico incluiu estimativa de prevalência, por ponto e por intervalo de 95% de confiança (IC95%), estimativa de concordância pela estatística kappa e testes de associação com nível de significância de 5%. Inicialmente, foi verificado, entre idosos, nível ruim de auto...

Gingivitis crónica y la higiene bucal en adolescentes de la secundaria básica "Raúl González Diego"

OpenAIRE

Mayán Reina, Grissel; de Beche Riambau, Elisa; Sosa Rodríguez, Iria; Parejo Maden, Dayanira; Morales Morán, Liset

2012-01-01

Introducción: las afecciones bucales constituyen un importante problema de salud por su alta prevalencia y demanda pública. Dentro de ellas encontramos la gingivitis crónica, cuyas manifestaciones clínicas aparecen desde edades tempranas, confirmándose que durante la adolescencia existe un incremento de la misma, asociado con una deficiente higiene bucal. Objetivo: por ello nos motivamos a realizar esta investigación cuyo objetivo fue determinar el comportamiento epidemiológico de la gingivit...

Benchmarking Severe Accident Computer Codes for Heavy Water Reactor Applications

International Nuclear Information System (INIS)

2013-12-01

Requests for severe accident investigations and assurance of mitigation measures have increased for operating nuclear power plants and the design of advanced nuclear power plants. Severe accident analysis investigations necessitate the analysis of the very complex physical phenomena that occur sequentially during various stages of accident progression. Computer codes are essential tools for understanding how the reactor and its containment might respond under severe accident conditions. The IAEA organizes coordinated research projects (CRPs) to facilitate technology development through international collaboration among Member States. The CRP on Benchmarking Severe Accident Computer Codes for HWR Applications was planned on the advice and with the support of the IAEA Nuclear Energy Department's Technical Working Group on Advanced Technologies for HWRs (the TWG-HWR). This publication summarizes the results from the CRP participants. The CRP promoted international collaboration among Member States to improve the phenomenological understanding of severe core damage accidents and the capability to analyse them. The CRP scope included the identification and selection of a severe accident sequence, selection of appropriate geometrical and boundary conditions, conduct of benchmark analyses, comparison of the results of all code outputs, evaluation of the capabilities of computer codes to predict important severe accident phenomena, and the proposal of necessary code improvements and/or new experiments to reduce uncertainties. Seven institutes from five countries with HWRs participated in this CRP

Concatenated codes for fault tolerant quantum computing

Energy Technology Data Exchange (ETDEWEB)

Knill, E.; Laflamme, R.; Zurek, W.

1995-05-01

The application of concatenated codes to fault tolerant quantum computing is discussed. We have previously shown that for quantum memories and quantum communication, a state can be transmitted with error {epsilon} provided each gate has error at most c{epsilon}. We show how this can be used with Shor`s fault tolerant operations to reduce the accuracy requirements when maintaining states not currently participating in the computation. Viewing Shor`s fault tolerant operations as a method for reducing the error of operations, we give a concatenated implementation which promises to propagate the reduction hierarchically. This has the potential of reducing the accuracy requirements in long computations.

Avaliação da saúde bucal das gestantes atendidas no PSF Adirbal Corralo na cidade Passo Fundo-RS

OpenAIRE

Carlos Alberto Rech; Patrícia Manfio

2016-01-01

O presente trabalho tem por objetivo analisar as condições e percepções de saúde bucal das gestantes que freqüentam o grupo de gestantes do PSF Adirbal Corralo na cidade de Passo Fundo-RS. Trata-se de um estudo quantitativo com abordagem descritiva. Para a coleta de dados foram utilizados questionários acerca da saúde bucal das gestantes, procurando observar quantas vezes e como é feita a escovação, o atendimento odontológico, as orientações odontológicas pré-natais e também exame clínico ver...

Autopercepção da saúde bucal entre idosos brasileiros Autopercepción de la salud bucal entre ancianos brasileños Self-perceived oral health among Brazilian elderly individuals

Directory of Open Access Journals (Sweden)

Andréa Maria Eleutério de Barros Lima Martins

2010-10-01

Full Text Available OBJETIVO: Identificar os fatores associados à autopercepção da saúde bucal entre idosos brasileiros. MÉTODOS: Utilizaram-se dados do Projeto SB Brasil, realizado em 20022003. Foi examinada e entrevistada amostra probabilística de 5.349 idosos de 65 a 74 anos agrupados em dentados e edentados. A variável dependente foi autopercepção da condição de saúde bucal e as independentes foram: local de moradia, características individuais, comportamentos relacionados à saúde, condições objetivas de saúde e condições subjetivas relacionadas à saúde. Foram conduzidas análises descritivas e análises de regressão linear múltipla hierárquica. RESULTADOS: Nos dois grupos a autopercepção da saúde bucal foi considerada positiva, apesar das precárias condições de saúde bucal entre os idosos. No modelo final, o local de moradia e as características individuais pouco contribuíram para explicar a variabilidade da autopercepção. Entre dentados, o uso de serviços odontológicos esteve associado ao desfecho, e as condições objetivas e subjetivas se mostraram associadas nos dois grupos. Entre dentados e edentados, o R² para o ambiente externo foi de 0,00; com o acréscimo das características individuais, respectivamente, 0,05 e 0,02; incluindo o comportamento relacionado à saúde, 0,06 e 0,03; acrescentando as condições objetivas de saúde, 0,11 e 0,04; adicionando as condições subjetivas relacionadas à saúde foram 0,50 e 0,43. Foi possível explicar 50% da variabilidade da autopercepção entre dentados e 43% entre edentados. CONCLUSÕES: Os principais fatores associados à autopercepção da saúde bucal como positiva nos dois grupos foram a autopercepção da aparência como ótima seguida pela autopercepção da mastigação como positiva. O terceiro fator associado, entre dentados, foi o relato de nenhuma necessidade de tratamento odontológico e, entre edentados, a autopercepção da fala.OBJETIVO: Identificar los

GASFLOW-MPI. A scalable computational fluid dynamics code for gases, aerosols and combustion. Vol. 2. Users' manual (Revision 1.0)

Energy Technology Data Exchange (ETDEWEB)

Xiao, Jianjun; Travis, Jack; Royl, Peter; Necker, Gottfried; Svishchev, Anatoly; Jordan, Thomas

2016-07-01

Karlsruhe Institute of Technology (KIT) is developing the parallel computational fluid dynamics code GASFLOW-MPI as a best-estimate tool for predicting transport, mixing, and combustion of hydrogen and other gases in nuclear reactor containments and other facility buildings. GASFLOW-MPI is a finite-volume code based on proven computational fluid dynamics methodology that solves the compressible Navier-Stokes equations for three-dimensional volumes in Cartesian or cylindrical coordinates.

Quantitative software-reliability analysis of computer codes relevant to nuclear safety

International Nuclear Information System (INIS)

Mueller, C.J.

1981-12-01

This report presents the results of the first year of an ongoing research program to determine the probability of failure characteristics of computer codes relevant to nuclear safety. An introduction to both qualitative and quantitative aspects of nuclear software is given. A mathematical framework is presented which will enable the a priori prediction of the probability of failure characteristics of a code given the proper specification of its properties. The framework consists of four parts: (1) a classification system for software errors and code failures; (2) probabilistic modeling for selected reliability characteristics; (3) multivariate regression analyses to establish predictive relationships among reliability characteristics and generic code property and development parameters; and (4) the associated information base. Preliminary data of the type needed to support the modeling and the predictions of this program are described. Illustrations of the use of the modeling are given but the results so obtained, as well as all results of code failure probabilities presented herein, are based on data which at this point are preliminary, incomplete, and possibly non-representative of codes relevant to nuclear safety

Integral transport computation of gamma detector response with the CPM2 code

International Nuclear Information System (INIS)

Jones, D.B.

1989-12-01

CPM-2 Version 3 is an enhanced version of the CPM-2 lattice physics computer code which supports the capabilities to (1) perform a two-dimensional gamma flux calculation and (2) perform Restart/Data file maintenance operations. The Gamma Calculation Module implemented in CPM-2 was first developed for EPRI in the CASMO-1 computer code by Studsvik Energiteknik under EPRI Agreement RP2352-01. The gamma transport calculation uses the CPM-HET code module to calculate the transport of gamma rays in two dimensions in a mixed cylindrical-rectangular geometry, where the basic fuel assembly and component regions are maintained in a rectangular geometry, but the fuel pins are represented as cylinders within a square pin cell mesh. Such a capability is needed to represent gamma transport in an essentially transparent medium containing spatially distributed ''black'' cylindrical pins. Under a subcontract to RP2352-01, RPI developed the gamma production and gamma interaction library used for gamma calculation. The CPM-2 gamma calculation was verified against reference results generated by Studsvik using the CASMO-1 program. The CPM-2 Restart/Data file maintenance capabilities provide the user with options to copy files between Restart/Data tapes and to purge files from the Restart/Data tapes

Problemas de salud bucal relacionados al uso de medicamentos por vía inhalatoria en trastornos respiratorios

Directory of Open Access Journals (Sweden)

Rosemarie Huartamendia

Full Text Available En el Uruguay la prevalencia de niños con problemas respiratorios no infecciosos es alta. El tratamiento medicamentoso de esas afecciones puede tener un impacto negativo en la salud bucal. El objetivo del presente estudio fue profundizar en los conocimientos sobre el asma en niños y adolescentes, de los fámacos y dispositivos terapéuticos utilizados y relacionarlos con los eventos adversos observados a nivel bucal. La revisión bibliográfica realizada demuestra que el uso de medicació por vía inhalatoria para las afecciones respiratorias no infecciosas se relaciona con reacciones adversas como la erosión, caries dental, gingivitis, halitosis, candidiasis y xerostomía. El relevamiento realizado en pacientes del Centro Hospitalario Pereira Rossell (2009-2010 mostró una correlación positiva entre los datos de la bibliografía revisada y lo observado en la clínica. Teniendo en cuenta estos antecedentes, es de importancia que el equipo de salud reconozca a la población que utiliza inhaladores como de alto riesgo potencial para el desarrollo de patologías bucales, enfatizando la necesidad de contar con programas educativo-preventivos específicos. La atención para la salud de los pacientes portadores de afecciones respiratorias requiere de un abordaje multidisciplinario

Prodeto, a computer code for probabilistic fatigue design

Energy Technology Data Exchange (ETDEWEB)

Braam, H [ECN-Solar and Wind Energy, Petten (Netherlands); Christensen, C J; Thoegersen, M L [Risoe National Lab., Roskilde (Denmark); Ronold, K O [Det Norske Veritas, Hoevik (Norway)

1999-03-01

A computer code for structural relibility analyses of wind turbine rotor blades subjected to fatigue loading is presented. With pre-processors that can transform measured and theoretically predicted load series to load range distributions by rain-flow counting and with a family of generic distribution models for parametric representation of these distribution this computer program is available for carying through probabilistic fatigue analyses of rotor blades. (au)

Relación histopatológica de la displasia epitelial con la oncoproteína p53 en la leucoplasia bucal

Directory of Open Access Journals (Sweden)

Zenia Batista Castro

2012-03-01

Full Text Available La leucoplasia bucal es una lesión precancerosa bien conocida debido a su asociación con la presencia de displasia epitelial y su tendencia a la transformación maligna. Con el fin de eliminar la subjetividad en la determinación de los grados de la displasia epitelial se han utilizado marcadores biológicos, entre ellos, el AcM anti p53. Por ello se propuso evaluar la expresión del AcM anti p53 en los diferentes grados de displasia epitelial en la leucoplasia bucal. Se emplearon las biopsias de 46 pacientes con diagnóstico de leucoplasia bucal, procedentes del Departamento de Patología Bucal de la Facultad de Estomatología de La Habana. Las muestras fueron procesadas por la técnica de inclusión en parafina y coloreadas con la técnica inmunohistoquímica del complejo avidina-biotina-peroxidasa para el AcM p53. Se estudió la correlación entre el patrón de inmunoensayo para p53 y el grado de displasia epitelial. Se evidenció que existe una asociación significativa entre la inmunocoloración de las células basales y suprabasales del epitelio con la oncoproteína p53, en los distintos grados de severidad de la displasia epitelial, lo que pudiera estar relacionado con el incremento progresivo de atipia celular observada. Se concluyó que en las muestras estudiadas existió una relación coincidente del aumento del grado de severidad de la displasia epitelial, con el marcaje de la oncoproteína p53. Estas evidencias sugirieron que el análisis inmunohistoquímico de p53 en conjunto con los parámetros histológicos, principalmente relacionados con el grado de severidad de la displasia epitelial, pudiera ser utilizado para lograr un diagnóstico más certero y contribuir a la prevención del cáncer bucal.

Development of a graphical interface computer code for reactor fuel reloading optimization

International Nuclear Information System (INIS)

Do Quang Binh; Nguyen Phuoc Lan; Bui Xuan Huy

2007-01-01

This report represents the results of the project performed in 2007. The aim of this project is to develop a graphical interface computer code that allows refueling engineers to design fuel reloading patterns for research reactor using simulated graphical model of reactor core. Besides, this code can perform refueling optimization calculations based on genetic algorithms as well as simulated annealing. The computer code was verified based on a sample problem, which relies on operational and experimental data of Dalat research reactor. This code can play a significant role in in-core fuel management practice at nuclear research reactor centers and in training. (author)

Pretest aerosol code comparisons for LWR aerosol containment tests LA1 and LA2

International Nuclear Information System (INIS)

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

1986-01-01

The Light-Water-Reactor (LWR) Aerosol Containment Experiments (LACE) are being performed in Richland, Washington, at the Hanford Engineering Development Laboratory (HEDL) 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 are being coordinated at the Oak Ridge National Laboratory. For each of the six LACE tests, ''pretest'' calculations (for code-to-code comparisons) and ''posttest'' calculations (for code-to-test data comparisons) are being performed. The overall goals of the comparison effort are (1) to provide code users with experience in applying their codes to LWR accident-sequence conditions and (2) to evaluate and improve the code models

Protector bucal por laminado a presión en paciente deportista

OpenAIRE

Corral, Camila; Mercado, Montserrat; Latapiat, André; Veliz, Andrea; Garrido, Mauricio; de Oliveira Jr, Osmir Batista

2017-01-01

RESUMEN: El traumatismo dentoalveolar incluye un conjunto de lesiones que afectan a los dientes y/o estructuras de soporte a consecuencia de un impacto violento directo o indirecto. Debido a que por lo general comprometen el sector anterior generan cambios físicos, fonéticos, psicológicos y dietarios, que pueden afectar significativamente la calidad de vida de pacientes afectados por este traumatismo. Los protectores bucales son considerados la principal medida para minimizar y/o evitar estos...

Algunos factores de riesgo y fenómenos psicológicos relacionados con el estado de salud bucal Risk factors and psychological phenomena related to the dentistry

Directory of Open Access Journals (Sweden)

Magda Lima Álvarez

2007-12-01

Full Text Available Se realizó un estudio descriptivo a 67 sujetos mayores de 15 años pertenecientes al consultorio No. 28 del Policlínico Comunitario Previsora en el período de Abril-noviembre del 2006, para determinar algunos factores de riesgo y fenómenos psicológicos relacionados con el estado de salud bucal. Se obtuvo predominio en las edades de 30 a 44 años con 33 pacientes (49.2 % y el estado de salud bucal medianamente favorable y desfavorable representó un 32.8 % y 41.8 % . El factor de riesgo que más influyó en el estado de salud bucal fue el biológico (77.6%. Al relacionar el diagnóstico estomatológico con la percepción de riesgo de enfermedad bucal la mayoría de los pacientes percibían éste pero no eran capaces de acudir al odontólogo para recibir tratamiento. El 61.2% de los pacientes tenían miedo y el 29,9% correspondió al estado de salud bucal desfavorable. La percepción de riesgo a enfermar se comportó en el 76.1% de los pacientesA descriptive study was carried out to 67 fellows older than 15 years assisted by the neighbourhood clinic No. 28 from the Previsora Community Policlinic in the period of April-November in 2006, to determine risk factors and psychological phenomena related to the state of mouth health problems. Prevalence was obtained with 33 patients (49.2% within the ages 30 to 44 years and the state of fairly favorable and unfavorable dentistry problems represented 37,3%. The risk factor that influenced the most in the state of mouth health problems was the biological one (77.6%. When relating the dentistry diagnostic with the perception of risk of that illness, most of the patients perceived it, but they were not able to go to the orthodontist to receive treatment. 61.2% of the patients were afraid and 50,8% corresponded to the state of fairly favorable and unfavorable mouth health problems. The perception of risk to get sick involved 76.1% of the patients

The failure mechanisms of HTR coated particle fuel and computer code

International Nuclear Information System (INIS)

Yang Lin; Liu Bing; Shao Youlin; Liang Tongxiang; Tang Chunhe

2010-01-01

The basic constituent unit of fuel element in HTR is ceramic coated particle fuel. And the performance of coated particle fuel determines the safety of HTR. In addition to the traditional detection of radiation experiments, establishing computer code is of great significance to the research. This paper mainly introduces the structure and the failure mechanism of TRISO-coated particle fuel, as well as a few basic assumptions,principles and characteristics of some existed main overseas codes. Meanwhile, this paper has proposed direction of future research by comparing the advantages and disadvantages of several computer codes. (authors)

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

Computer simulation of variform fuel assemblies using Dragon code

International Nuclear Information System (INIS)

Ju Haitao; Wu Hongchun; Yao Dong

2005-01-01

The DRAGON is a cell code that developed for the CANDU reactor by the Ecole Polytechnique de Montreal of CANADA. Although, the DRAGON is mainly used to simulate the CANDU super-cell fuel assembly, it has an ability to simulate other geometries of the fuel assembly. However, only NEACRP benchmark problem of the BWR lattice cell was analyzed until now except for the CANDU reactor. We also need to develop the code to simulate the variform fuel assemblies, especially, for design of the advanced reactor. We validated that the cell code DRAGON is useful for simulating various kinds of the fuel assembly by analyzing the rod-shape fuel assembly of the PWR and the MTR plate-shape fuel assembly. Some other kinds of geometry of geometry were computed. Computational results show that the DRAGON is able to analyze variform fuel assembly problems and the precision is high. (authors)

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

International Nuclear Information System (INIS)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E.; Tills, J.

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions

Code manual for CONTAIN 2.0: A computer code for nuclear reactor containment analysis

Energy Technology Data Exchange (ETDEWEB)

Murata, K.K.; Williams, D.C.; Griffith, R.O.; Gido, R.G.; Tadios, E.L.; Davis, F.J.; Martinez, G.M.; Washington, K.E. [Sandia National Labs., Albuquerque, NM (United States); Tills, J. [J. Tills and Associates, Inc., Sandia Park, NM (United States)

1997-12-01

The CONTAIN 2.0 computer code is an integrated analysis tool used for predicting the physical conditions, chemical compositions, and distributions of radiological materials inside a containment building following the release of material from the primary system in a light-water reactor accident. It can also predict the source term to the environment. CONTAIN 2.0 is intended to replace the earlier CONTAIN 1.12, which was released in 1991. The purpose of this Code Manual is to provide full documentation of the features and models in CONTAIN 2.0. Besides complete descriptions of the models, this Code Manual provides a complete description of the input and output from the code. CONTAIN 2.0 is a highly flexible and modular code that can run problems that are either quite simple or highly complex. An important aspect of CONTAIN is that the interactions among thermal-hydraulic phenomena, aerosol behavior, and fission product behavior are taken into account. The code includes atmospheric models for steam/air thermodynamics, intercell flows, condensation/evaporation on structures and aerosols, aerosol behavior, and gas combustion. It also includes models for reactor cavity phenomena such as core-concrete interactions and coolant pool boiling. Heat conduction in structures, fission product decay and transport, radioactive decay heating, and the thermal-hydraulic and fission product decontamination effects of engineered safety features are also modeled. To the extent possible, the best available models for severe accident phenomena have been incorporated into CONTAIN, but it is intrinsic to the nature of accident analysis that significant uncertainty exists regarding numerous phenomena. In those cases, sensitivity studies can be performed with CONTAIN by means of user-specified input parameters. Thus, the code can be viewed as a tool designed to assist the knowledge reactor safety analyst in evaluating the consequences of specific modeling assumptions.

COMPETÊNCIAS DE AUXILIARES E TÉCNICOS DE SAÚDE BUCAL E O VÍNCULO COM O SISTEMA ÚNICO DE SAÚDE

Directory of Open Access Journals (Sweden)

Cristine Maria Warmling

2016-01-01

Full Text Available Resumo O estudo teve por objetivo descrever o perfil sociodemográfico, de trabalho e formação de auxiliares e técnicos em saúde bucal com atuação no estado do Rio Grande do Sul. Foram analisadas as informações relatadas por 255 auxiliares e técnicos de saúde bucal que participaram do Congresso Rio-Grandense de Odontologia realizado em 2010 e 2012. A pesquisa utilizou-se de um questionário escrito, estruturado e autoaplicável, organizado em três blocos temáticos com as seguintes categorias: identificação (sexo, idade, estado civil, estado/cidade, renda, habilitação, vínculo e inscrição conselho/sindicato, formação (estabelecimento, duração, incentivo/dificuldades de atualização/formação e processo de trabalho (competências e atribuições profissionais. Os resultados encontrados demonstraram que diferenças no processo de trabalho entre os auxiliares e técnicos de saúde bucal determinadas pelo vínculo de trabalho com o Sistema Único de Saúde estavam concentradas nas atribuições das competências de promoção e prevenção de saúde. Também se verificou que as atribuições das competências de organização do ambiente de trabalho e de atendimento clínico de saúde bucal conferem maior identidade ao trabalho desses profissionais, independentemente do vínculo. O estudo alerta para a sobreposição das competências e atribuições realizadas pelos auxiliares e técnicos de saúde bucal.

Implantation of TRAC-PF1 computer code of VAX-11/750

International Nuclear Information System (INIS)

Madeira, A.A.; Souza Gouvea, L. de; Galetti, M.R.S.

1988-01-01

The implantation of TRAC-PF1 code, IBM version, in VAX-11/750 is described. This work provides Reator Department with an advanced best-estimate tool to perform loss-of-coolant accident analysis. (Author) [pt

SACRD: a data base for fast reactor safety computer codes, contents and glossary of Version 1 of the system

International Nuclear Information System (INIS)

Greene, N.M.; Forsberg, V.M.; Raiford, G.B.; Arwood, J.W.; Flanagan, G.F.

1979-01-01

SACRD is a data base of material properties and other handbook data needed in computer codes used for fast reactor safety studies. This document lists the contents of Version 1 and also serves as a glossary of terminology used in the data base. Data are available in the thermodynamics, heat transfer, fluid mechanics, structural mechanics, aerosol transport, meteorology, neutronics and dosimetry areas. Tabular, graphical and parameterized data are provided in many cases

COMPBRN III: a computer code for modeling compartment fires

International Nuclear Information System (INIS)

Ho, V.; Siu, N.; Apostolakis, G.; Flanagan, G.F.

1986-07-01

The computer code COMPBRN III deterministically models the behavior of compartment fires. This code is an improvement of the original COMPBRN codes. It employs a different air entrainment model and numerical scheme to estimate properties of the ceiling hot gas layer model. Moreover, COMPBRN III incorporates a number of improvements in shape factor calculations and error checking, which distinguish it from the COMPBRN II code. This report presents the ceiling hot gas layer model employed by COMPBRN III as well as several other modifications. Information necessary to run COMPBRN III, including descriptions of required input and resulting output, are also presented. Simulation of experiments and a sample problem are included to demonstrate the usage of the code. 37 figs., 46 refs

Representações sociais de gestantes sobre saúde bucal

OpenAIRE

Finkler, Mirelle

2003-01-01

Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro de Ciências da Saúde. Programa de Pós-Graduação em Odontologia. Partindo do pressuposto de que é necessário melhor entender para melhor agir, este estudo investigou os saberes de gestantes sobre saúde bucal, tendo como objetivo a compreensão das representações sociais (RS) que influenciam suas práticas, à luz da Teoria das Representações Sociais, proposta por Moscovici, em 1961. Os sujeitos desta pesquisa qualitativa f...

ABINIT: a computer code for matter; Abinit: un code au service de la matiere

Energy Technology Data Exchange (ETDEWEB)

Amadon, B.; Bottin, F.; Bouchet, J.; Dewaele, A.; Jollet, F.; Jomard, G.; Loubeyre, P.; Mazevet, S.; Recoules, V.; Torrent, M.; Zerah, G. [CEA Bruyeres-le-Chatel, 91 (France)

2008-07-01

The PAW (Projector Augmented Wave) method has been implemented in the ABINIT Code that computes electronic structures in atoms. This method relies on the simultaneous use of a set of auxiliary functions (in plane waves) and a sphere around each atom. This method allows the computation of systems including many atoms and gives the expression of energy, forces, stress... in terms of the auxiliary function only. We have generated atomic data for iron at very high pressure (over 200 GPa). We get a bcc-hcp transition around 10 GPa and the magnetic order disappears around 50 GPa. This method has been validated on a series of metals. The development of the PAW method has required a great effort for the massive parallelization of the ABINIT code. (A.C.)

Procedure and code for calculating black control rods taking into account epithermal absorption, code CAS-1; Postupak i program za proracun crnih kontrolnih sipki, uzimajuci u obzir i epitermalnu apsorpciju, CAS-1

Energy Technology Data Exchange (ETDEWEB)

Martinc, R; Trivunac, N; Zivkovic, Z [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1964-12-15

This report describes the computer code CAS-1, calculation method and procedure applied for calculating the black control rods taking into account the epithermal neutron absorption. Results obtained for supercell method applied for regular lattice reflected in the multiplication medium is part of this report in addition to the computer code manual.

DISP1 code

International Nuclear Information System (INIS)

Vokac, P.

1999-12-01

DISP1 code is a simple tool for assessment of the dispersion of the fission product cloud escaping from a nuclear power plant after an accident. The code makes it possible to tentatively check the feasibility of calculations by more complex PSA3 codes and/or codes for real-time dispersion calculations. The number of input parameters is reasonably low and the user interface is simple enough to allow a rapid processing of sensitivity analyses. All input data entered through the user interface are stored in the text format. Implementation of dispersion model corrections taken from the ARCON96 code enables the DISP1 code to be employed for assessment of the radiation hazard within the NPP area, in the control room for instance. (P.A.)

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

International Nuclear Information System (INIS)

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

1983-02-01

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

Saúde bucal do idoso: por uma política inclusiva

Directory of Open Access Journals (Sweden)

Ana Lúcia Schaefer Ferreira de Mello

2008-01-01

Full Text Available El presente artículo forma parte de una investigación sobre el cuidado a la salud bucodental, realizada en residencias geriátricas. Su objetivo es relacionar el significado del cuidado a la salud bucodental del anciano, institucionalizando los asuntos referentes a las políticas públicas, en el actual contexto nacional de implementación de políticas de salud/salud bucal. Se trata de un estudio cualitativo basado en la Grounded Theory. Participaron del estudio tres ancianos, cuatro cuidadores, dos enfermeros y tres administradores (primer grupo del muestreo; y, tres dentistas, tres gestores públicos y un administrador (segundo grupo del muestreo. Después de la relectura de los datos de las entrevistas y del análisis comparativo, la categoría: Insertando el cuidado a la salud bucodental del anciano en la dimensión político-organizacional incluyó las políticas públicas de salud/salud bucal. A pesar de las garantías legales, del crecimiento de los recursos y de la expansión de los servicios, la implementación de políticas públicas que incluyan al anciano en las acciones de salud bucodental es incipiente para garantizar el compromiso público-estadual y gubernamental que transforme la realidad epidemiológica.

Simulation of accident and restrained transients in PWR nuclear power plant with RELAP 5/MOD 1 computer code

International Nuclear Information System (INIS)

Silva Filho, E.

1986-01-01

The computer code RELAP5/MOD1 has been utilized to investigate the thermal-hydraulic behaviour of a standard 1300 Mwe pressurized water reactor plant of the KWU design during a station blackout and during a loss-of-coolant accident involving 2% break in the cross-sectional area the cold leg in one of the four loops and located between the pump and the reactor pressure vessel. During the simulations the reactor scram system and the emergency coolant system were considered inactive. (Author) [pt

Theory of the space-dependent fuel management computer code ''UAFCC''

International Nuclear Information System (INIS)

El-Meshad, Y.; Morsy, S.; El-Osery, I.A.

1981-01-01

This report displays the theory of the spatial burnup computer code ''UAFCC'' which has been constructed as a part of an integrated reactor calculation scheme proposed at the Reactors Department of the ARE Atomic Energy Authority. The ''UAFCC'' is a single energy-one-dimensional diffusion burnup FORTRAN computer code for well moderated, multiregion, cylindrical thermal reactors. The effect of reactivity variation with burnup is introduced in the steady state diffusion equation by a fictitious neutron source. The infinite multiplication factor, the total migration area, and the power density per unit thermal flux are calculated from the point model burnup code ''UABUC'' fitted to polynomials of suitable degree in the flux-time, and then used as an input data to the ''UAFCC'' code. The proposed burnup spatial model has been used to study the different stratogemes of the incore fuel management schemes. The conclusions of this study will be presented in a future publication. (author)

Three computer codes for safety and stability of large superconducting magnets

International Nuclear Information System (INIS)

Turner, L.R.

1985-01-01

For analyzing the safety and stability of large superconducting magnets, three computer codes TASS, SHORTURN, and SSICC have been developed, applicable to bath-cooled magnets, bath-cooled magnets with shorted turns, and magnets with internally cooled conductors respectively. The TASS code is described, and the use of the three codes is reviewed

Computation of thermodynamic equilibria of nuclear materials in multi-physics codes

International Nuclear Information System (INIS)

Piro, M.H.; Lewis, B.J.; Thompson, W.T.; Simunovic, S.; Besmann, T.M.

2011-01-01

A new equilibrium thermodynamic solver is being developed with the primary impetus of direct integration into nuclear fuel performance and safety codes to provide improved predictions of fuel behavior. This solver is intended to provide boundary conditions and material properties for continuum transport calculations. There are several legitimate concerns with the use of existing commercial thermodynamic codes: 1) licensing entanglements associated with code distribution, 2) computational performance, and 3) limited capabilities of handling large multi-component systems of interest to the nuclear industry. The development of this solver is specifically aimed at addressing these concerns. In support of this goal, a new numerical algorithm for computing chemical equilibria is presented which is not based on the traditional steepest descent method or 'Gibbs energy minimization' technique. This new approach exploits fundamental principles of equilibrium thermodynamics, which simplifies the optimization equations. The chemical potentials of all species and phases in the system are constrained by the system chemical potentials, and the objective is to minimize the residuals of the mass balance equations. Several numerical advantages are achieved through this simplification, as described in this paper. (author)

CRACKEL: a computer code for CFR fuel management calculations

International Nuclear Information System (INIS)

Burstall, R.F.; Ball, M.A.; Thornton, D.E.J.

1975-12-01

The CRACKLE computer code is designed to perform rapid fuel management surveys of CFR systems. The code calculates overall features such as reactivity, power distributions and breeding gain, and also calculates for each sub-assembly plutonium content and power output. A number of alternative options are built into the code, in order to permit different fuel management strategies to be calculated, and to perform more detailed calculations when necessary. A brief description is given of the methods of calculation, and the input facilities of CRACKLE, with examples. (author)

Qualification of FEAST 3.0 and FEAT 4.0 computer codes

International Nuclear Information System (INIS)

Xu, Z.; Lai, L.; Sim, K.-S.; Huang, F.; Wong, B.

2005-01-01

FEAST (Finite Element Analysis for Stresses) is an AECL computer code used to assess the structural integrity of the CANDU fuel element. FEAST models the thermo-elastic, thermo-elasto-plastic and creep deformations in CANDU fuel. FEAT (Finite Element Analysis for Temperature) is another AECL computer code and is used to assess the thermal integrity of fuel elements. FEAT models the steady-state and transient heat flows in CANDU fuel, under conditions such as flux depression, end flux peaking, temperature-dependent thermal conductivity, and non-uniform time-dependent boundary conditions. Both computer programs are used in design and qualification analyses of CANDU fuel. Formal qualifications (including coding verification and validation) of both codes were performed, in accordance with AECL software quality assurance (SQA) manual and procedures that are consistent with CSA N286.7-99. Validation of FEAST 3.0 shows very good agreement with independent analytical solutions or measurements. Validation of FEAT 4.0 also shows very good agreement with independent WIMS-AECL calculations, analytical solutions, ANSYS calculations and measurement. (author)

Qualification of FEAST 3.0 and FEAT 4.0 computer codes

Energy Technology Data Exchange (ETDEWEB)

Xu, Z.; Lai, L.; Sim, K.-S.; Huang, F.; Wong, B. [Atomic Energy of Canada Limited, Mississauga, Ontario (Canada)

2005-07-01

FEAST (Finite Element Analysis for Stresses) is an AECL computer code used to assess the structural integrity of the CANDU fuel element. FEAST models the thermo-elastic, thermo-elasto-plastic and creep deformations in CANDU fuel. FEAT (Finite Element Analysis for Temperature) is another AECL computer code and is used to assess the thermal integrity of fuel elements. FEAT models the steady-state and transient heat flows in CANDU fuel, under conditions such as flux depression, end flux peaking, temperature-dependent thermal conductivity, and non-uniform time-dependent boundary conditions. Both computer programs are used in design and qualification analyses of CANDU fuel. Formal qualifications (including coding verification and validation) of both codes were performed, in accordance with AECL software quality assurance (SQA) manual and procedures that are consistent with CSA N286.7-99. Validation of FEAST 3.0 shows very good agreement with independent analytical solutions or measurements. Validation of FEAT 4.0 also shows very good agreement with independent WIMS-AECL calculations, analytical solutions, ANSYS calculations and measurement. (author)

Description of the TREBIL, CRESSEX and STREUSL computer programs, that belongs to RALLY computer code pack for the analysis of reliability systems

International Nuclear Information System (INIS)

Fernandes Filho, T.L.

1982-11-01

The RALLY computer code pack (RALLY pack) is a set of computer codes destinate to the reliability of complex systems, aiming to a risk analysis. Three of the six codes, are commented, presenting their purpose, input description, calculation methods and results obtained with each one of those computer codes. The computer codes are: TREBIL, to obtain the fault tree logical equivalent; CRESSEX, to obtain the minimal cut and the punctual values of the non-reliability and non-availability of the system; and STREUSL, for the dispersion calculation of those values around the media. In spite of the CRESSEX, in its version available at CNEN, uses a little long method to obtain the minimal cut in an HB-CNEN system, the three computer programs show good results, mainly the STREUSL, which permits the simulation of various components. (E.G.) [pt

Reducing Computational Overhead of Network Coding with Intrinsic Information Conveying

DEFF Research Database (Denmark)

Heide, Janus; Zhang, Qi; Pedersen, Morten V.

is RLNC (Random Linear Network Coding) and the goal is to reduce the amount of coding operations both at the coding and decoding node, and at the same time remove the need for dedicated signaling messages. In a traditional RLNC system, coding operation takes up significant computational resources and adds...... the coding operations must be performed in a particular way, which we introduce. Finally we evaluate the suggested system and find that the amount of coding can be significantly reduced both at nodes that recode and decode.......This paper investigated the possibility of intrinsic information conveying in network coding systems. The information is embedded into the coding vector by constructing the vector based on a set of predefined rules. This information can subsequently be retrieved by any receiver. The starting point...

Computer codes for the study of the loss of coolant accident of PWR reactors

International Nuclear Information System (INIS)

Gomolinski, M.; Menessier, D.; Tellier, N.

1975-01-01

The CEA has undertaken a large programme to study the consequence on the core of the LOCA of a PWR. In the programme, simultaneously carried out experiments and the development of the calculations means are described. Several experiments such as OMEGA, ERSEC and PHEBUS tests, which provide data to check the computer codes are outlined briefly in the paper. For analysis of the LOCA of a PWR, a series of computer codes, which are at present in use or under development, are linked with each other. The codes are DANAIDES for blowdown, CERES for refill and reflood, THETA-1B and FLIRA for heat up calculation during the blow-down and the reflooding period respectively. FLIRA-PASTEL, a combination of FLIRA and PASTEL which calculate the stress and deformations of material using the finite element method, will be used in place of FLIRA. The basic models and flowcharts of the above codes are described in the paper

Sodium fast reactor gaps analysis of computer codes and models for accident analysis and reactor safety.

Energy Technology Data Exchange (ETDEWEB)

Carbajo, Juan (Oak Ridge National Laboratory, Oak Ridge, TN); Jeong, Hae-Yong (Korea Atomic Energy Research Institute, Daejeon, Korea); Wigeland, Roald (Idaho National Laboratory, Idaho Falls, ID); Corradini, Michael (University of Wisconsin, Madison, WI); Schmidt, Rodney Cannon; Thomas, Justin (Argonne National Laboratory, Argonne, IL); Wei, Tom (Argonne National Laboratory, Argonne, IL); Sofu, Tanju (Argonne National Laboratory, Argonne, IL); Ludewig, Hans (Brookhaven National Laboratory, Upton, NY); Tobita, Yoshiharu (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Ohshima, Hiroyuki (Japan Atomic Energy Agency, Ibaraki-ken, Japan); Serre, Frederic (Centre d' %C3%94etudes nucl%C3%94eaires de Cadarache %3CU%2B2013%3E CEA, France)

2011-06-01

This report summarizes the results of an expert-opinion elicitation activity designed to qualitatively assess the status and capabilities of currently available computer codes and models for accident analysis and reactor safety calculations of advanced sodium fast reactors, and identify important gaps. The twelve-member panel consisted of representatives from five U.S. National Laboratories (SNL, ANL, INL, ORNL, and BNL), the University of Wisconsin, the KAERI, the JAEA, and the CEA. The major portion of this elicitation activity occurred during a two-day meeting held on Aug. 10-11, 2010 at Argonne National Laboratory. There were two primary objectives of this work: (1) Identify computer codes currently available for SFR accident analysis and reactor safety calculations; and (2) Assess the status and capability of current US computer codes to adequately model the required accident scenarios and associated phenomena, and identify important gaps. During the review, panel members identified over 60 computer codes that are currently available in the international community to perform different aspects of SFR safety analysis for various event scenarios and accident categories. A brief description of each of these codes together with references (when available) is provided. An adaptation of the Predictive Capability Maturity Model (PCMM) for computational modeling and simulation is described for use in this work. The panel's assessment of the available US codes is presented in the form of nine tables, organized into groups of three for each of three risk categories considered: anticipated operational occurrences (AOOs), design basis accidents (DBA), and beyond design basis accidents (BDBA). A set of summary conclusions are drawn from the results obtained. At the highest level, the panel judged that current US code capabilities are adequate for licensing given reasonable margins, but expressed concern that US code development activities had stagnated and that the

Development and validation of GWHEAD, a three-dimensional groundwater head computer code

International Nuclear Information System (INIS)

Beckmeyer, R.R.; Root, R.W.; Routt, K.R.

1980-03-01

A computer code has been developed to solve the groundwater flow equation in three dimensions. The code has finite-difference approximations solved by the strongly implicit solution procedure. Input parameters to the code include hydraulic conductivity, specific storage, porosity, accretion (recharge), and initial hydralic head. These parameters may be input as varying spatially. The hydraulic conductivity may be input as isotropic or anisotropic. The boundaries either may permit flow across them or may be impermeable. The code has been used to model leaky confined groundwater conditions and spherical flow to a continuous point sink, both of which have exact analytical solutions. The results generated by the computer code compare well with those of the analytical solutions. The code was designed to be used to model groundwater flow beneath fuel reprocessing and waste storage areas at the Savannah River Plant

Hábitos de higiene bucal de adultos porto-alegrenses

Directory of Open Access Journals (Sweden)

Abegg Claídes

1997-01-01

Full Text Available OBJETIVOS: Avaliar alguns hábitos de higiene bucal (escovação dentária, uso do palito e uso do fio dental em um grupo de adultos, em relação a fatores sociodemográficos, e investigar o nível de placa bacteriana e sangramento gengival. METODOLOGIA: A amostra foi constituída por 234 mulheres e 237 homens de duas categorias socioeconômicas, com idade entre 24 e 44 anos. Os dados foram coletados através de entrevistas estruturadas e exames clínicos. RESULTADOS: A freqüência de escovação encontrada foi alta: (mediana e moda de três vezes ao dia e apresentou associação com sexo e categoria socioeconômica. A maioria dos entrevistados (67,5% declarou usar fio dental, estando seu uso associado com sexo e categoria socioeconômica. Usar palito foi descrito como um hábito comum para a maioria das pessoas entrevistadas:(54,6% o usam. O uso do palito apresentou associação com sexo, idade e categoria socioeconômica . O nível de placa bacteriana foi moderado para a maioria das pessoas (62,6%, e estava associado com a categoria socioeconômica. Um quarto dos participantes do estudo não apresentou sangramento gengival, e este estava associado com a idade e a categoria socioeconômica. CONCLUSÃO: Os hábitos de higiene bucal foram considerados bons para a maioria dos indivíduos que participaram do estudo, havendo necessidade de melhoria para os homens e pessoas de categoria socioeconômica inferior.

Phenomenological optical potentials and optical model computer codes

International Nuclear Information System (INIS)

Prince, A.

1980-01-01

An introduction to the Optical Model is presented. Starting with the purpose and nature of the physical problems to be analyzed, a general formulation and the various phenomenological methods of solution are discussed. This includes the calculation of observables based on assumed potentials such as local and non-local and their forms, e.g. Woods-Saxon, folded model etc. Also discussed are the various calculational methods and model codes employed to describe nuclear reactions in the spherical and deformed regions (e.g. coupled-channel analysis). An examination of the numerical solutions and minimization techniques associated with the various codes, is briefly touched upon. Several computer programs are described for carrying out the calculations. The preparation of input, (formats and options), determination of model parameters and analysis of output are described. The class is given a series of problems to carry out using the available computer. Interpretation and evaluation of the samples includes the effect of varying parameters, and comparison of calculations with the experimental data. Also included is an intercomparison of the results from the various model codes, along with their advantages and limitations. (author)

RADTRAN II: revised computer code to analyze transportation of radioactive material

International Nuclear Information System (INIS)

Taylor, J.M.; Daniel, S.L.

1982-10-01

A revised and updated version of the RADTRAN computer code is presented. This code has the capability to predict the radiological impacts associated with specific schemes of radioactive material shipments and mode specific transport variables

The PLTEMP V2.1 code

International Nuclear Information System (INIS)

Olson, A.P.

2003-01-01

Recent improvements to the computer code PLTEMP/ANL V2.1 are described. A new iterative, error-minimization solution technique is used to obtain the thermal distribution both within each fuel plate, and along the axial length of each coolant channel. A new, radial geometry solution is available for tube-type fuel assemblies. Software comparisons of these and other new models are described. Applications to Russian-designed IRT-type research reactors are described. (author)

FIRAC: a computer code to predict fire-accident effects in nuclear facilities

International Nuclear Information System (INIS)

Bolstad, J.W.; Krause, F.R.; Tang, P.K.; Andrae, R.W.; Martin, R.A.; Gregory, W.S.

1983-01-01

FIRAC is a medium-sized computer code designed to predict fire-induced flows, temperatures, and material transport within the ventilating systems and other airflow pathways in nuclear-related facilities. The code is designed to analyze the behavior of interconnected networks of rooms and typical ventilation system components. This code is one in a family of computer codes that is designed to provide improved methods of safety analysis for the nuclear industry. The structure of this code closely follows that of the previously developed TVENT and EVENT codes. Because a lumped-parameter formulation is used, this code is particularly suitable for calculating the effects of fires in the far field (that is, in regions removed from the fire compartment), where the fire may be represented parametrically. However, a fire compartment model to simulate conditions in the enclosure is included. This model provides transport source terms to the ventilation system that can affect its operation and in turn affect the fire

Computer codes for simulating atomic-displacement cascades in solids subject to irradiation

International Nuclear Information System (INIS)

Asaoka, Takumi; Taji, Yukichi; Tsutsui, Tsuneo; Nakagawa, Masayuki; Nishida, Takahiko

1979-03-01

In order to study atomic displacement cascades originating from primary knock-on atoms in solids subject to incident radiation, the simulation code CASCADE/CLUSTER is adapted for use on FACOM/230-75 computer system. In addition, the code is modified so as to plot the defect patterns in crystalline solids. As other simulation code of the cascade process, MARLOWE is also available for use on the FACOM system. To deal with the thermal annealing of point defects produced in the cascade process, the code DAIQUIRI developed originally for body-centered cubic crystals is modified to be applicable also for face-centered cubic lattices. By combining CASCADE/CLUSTER and DAIQUIRI, we then prepared a computer code system CASCSRB to deal with heavy irradiation or saturation damage state of solids at normal temperature. Furthermore, a code system for the simulation of heavy irradiations CASCMARL is available, in which MARLOWE code is substituted for CASCADE in the CASCSRB system. (author)

Comparison of computer codes related to the sodium oxide aerosol behavior in a containment building

International Nuclear Information System (INIS)

Fermandjian, J.

1984-09-01

In order to ensure that the problems of describing the physical behavior of sodium aerosols, during hypothetical fast reactor accidents, were adequately understood, a comparison of the computer codes (ABC/INTG, PNC, Japan; AEROSIM, UKAEA/SRD, United Kingdom; PARDISEKO IIIb, KfK, Germany; AEROSOLS/A2 and AEROSOLS/B1, CEA France) was undertaken in the frame of the CEC: exercise in which code users have run their own codes with a prearranged input

Theoretical calculation possibilities of the computer code HAMMER

International Nuclear Information System (INIS)

Onusic Junior, J.

1978-06-01

With the aim to know the theoretical calculation possibilities of the computer code HAMMER, developed at Savanah River Laboratory, a analysis of the crytical cells assembly of the kind utilized in PWR reactors is made. (L.F.S.) [pt

THYDE-B1/MOD2: a computer code for analysis of small-break loss-of-coolant accidents of boiling water reactors

International Nuclear Information System (INIS)

Nakamura, Hideo; Muramatsu, Ken; Kukita, Yutaka; Tasaka, Kanji

1988-04-01

THYDE-B1/MOD2 is a fast-running best estimate (BE) computer code to analyze thermal-hydraulic behaviors of the reactor cooling system of a boiling water reactor (BWR), mainly, during a small-break loss-of-coolant accident (SBLOCA) with a special emphasis on the behavior of pressure and mixture level in the pressure vessel. The coolant behavior is simulated with a volume-and-junction method based on assumptions of thermal equilibrium and homogeneous conditions for two-phase flow. A characteristic feature of this code is a three-region representation of the state of the coolant in a control volume, in which three regions consist of subcooled liquid, saturated mixture and saturated steam regions from the volume bottom. The regions are separated by two horizontal moving boundaries which are tracked by mass and energy balances for each region. With this three region node model, the interior of the pressure vessel can be represented by only two volumes: one for inside of the shroud and the other for outside, while other portions of the system are treated with homogeneous node model. This method, although it seems to be very simple, has been verified to be adequate for cases of BWR SBLOCAs in which the thermal-hydraulic behavior is relatively slow and gravity controlled. The code has been improved and modified from the last version of the code, THYDE-B1/MOD1, especially in the phase separation model which is used in the mixture level calculation in the three region node model. Then, a good predictability of the code has been indicated through the comparison of calculated results with various SBLOCA test data including ROSA-III of JAERI and FIST of the General Electric Co. This report presents the code modifications and input data requirements of the THYDE-B1/MOD2 code. (author)

Development of a tracer transport option for the NAPSAC fracture network computer code

International Nuclear Information System (INIS)

Herbert, A.W.

1990-06-01

The Napsac computer code predicts groundwater flow through fractured rock using a direct fracture network approach. This paper describes the development of a tracer transport algorithm for the NAPSAC code. A very efficient particle-following approach is used enabling tracer transport to be predicted through large fracture networks. The new algorithm is tested against three test examples. These demonstrations confirm the accuracy of the code for simple networks, where there is an analytical solution to the transport problem, and illustrates the use of the computer code on a more realistic problem. (author)

Avaliação do conhecimento popular e práticas cotidianas em saúde bucal

Directory of Open Access Journals (Sweden)

Beatriz Unfer

2000-04-01

Full Text Available OBJETIVO: Avaliar o conhecimento popular e as práticas cotidianas em saúde bucal de usuários de serviços públicos de saúde. MÉTODOS: A população estudada foi selecionada a partir de uma amostra estratificada de usuários que procuraram atendimento nas unidades sanitárias da zona urbana de Santa Maria, RS. Os dados foram coletados por meio de entrevista semi-estruturada e organizados em conjuntos de categorias descritivas, permitindo sua distribuição em tabela de freqüência. RESULTADOS: Verificou-se que predominam usuários entre 21 e 40 anos de idade, do sexo feminino e com padrão socioeconômico baixo. A busca pela saúde e o controle das doenças bucais são atribuídos à responsabilidade individual de realizar a higiene bucal e procurar tratamento dentário. A presença e os benefícios do flúor no creme dental e na água de beber não foram reconhecidos pela população estudada. CONCLUSÕES: Os programas de saúde devem considerar os aspectos relativos ao conhecimento e as práticas em saúde bucal, para viabilizar o processo de capacitação da população e promover a responsabilização coletiva da promoção da saúde em todos os níveis da sociedade.

A restructuring of the MELCOR fission product packages for the MIDAS computer code

International Nuclear Information System (INIS)

Park, S.H.; Kim, K.R.; Kim, D.H.

2004-01-01

The RN1/RN2 packages, which are the fission product-related packages in MELCOR, have been restructured for the MIDAS computer code. MIDAS is being developed as an integrated severe accident analysis code with a user-friendly graphical user interface and a modernized data structure. To do this, the data transferring methods of the current MELCOR code are modified and adopted into the RN1/RN2 package. The data structure of the current MELCOR code using FORTRAN77 has a difficulty in grasping the meaning of the variables as well as waste of memory. New features of FORTRAN90 make it possible to allocate the storage dynamically and to user-defined data type, which leads to an efficient memory treatment and an easy understanding of the code. Restructuring of the RN1/RN2 package addressed in this paper includes a module development, subroutine modification, and the treatment of MELGEN, which generates the data file, as well as MELCOR, which is processing the calculation. The verification has been done by comparing the results of the modified code with those of the existing code. As the trends are similar to each other, it implies that the same approach could be extended to the entire code package. It is expected that the code restructuring will accelerate the code domestication thanks to a direct understanding of each variable and an easy implementation of the modified or newly developed models. (author)

Speed up of MCACE, a Monte Carlo code for evaluation of shielding safety, by parallel computer, (3)

International Nuclear Information System (INIS)

Takano, Makoto; Masukawa, Fumihiro; Naito, Yoshitaka; Onodera, Emi; Imawaka, Tsuneyuki; Yoda, Yoshihisa.

1993-07-01

The parallel computing of the MCACE code has been studied on two platforms; 1) Shared Memory Type Vector-Parallel Computer Monte-4 and 2) Networked Several Workstations. On the Monte-4, a disk-file has been allocated to collect all results computed by 4 CPUs in parallel, executing the copy of the MCACE code on each CPU. On the workstations under network environment, two parallel models have been evaluated; 1) a host-node model and 2) the model used on the Monte-4 where no software for parallelization has been employed but only standard FORTRAN language. The measurement of computing times has showed that speed up of about 3 times has been achieved by using 4 CPUs of the Monte-4. Further, connecting 4 workstations by network, the computing speed by parallelization has achieved faster than our scalar main frame computer, FACOM M-780. (author)

Tele-educação e monitoria ativa no ensino da saúde bucal a estudantes de medicina

Directory of Open Access Journals (Sweden)

Ednalva de Sousa Eskenazi

Full Text Available OBJETIVOS: Verificar o nível de conhecimento basal de alunos do quinto ano de Medicina sobre saúde bucal e mensurar os ganhos em conhecimento e a habilidade de aconselhamento após treinamento. MÉTODOS: Cento e quarenta e oito alunos, divididos em quatro turmas - 2007-A (grupo controle, 2007-B, 2008-A e 2008-B - receberam intervenções progressivas de ensino, presenciais (em 2007 e a distância (em 2008. A turma 2008-B recebeu também contatos ativos com especialista em saúde bucal. O ganho em conhecimento foi medido por provas escritas aplicadas antes e depois da respectiva intervenção, e a habilidade em aconselhar foi avaliada por meio do exame clínico objetivo estruturado por estações (Osce. RESULTADOS: Noventa e um por cento dos alunos acharam inadequado o seu nível basal de conhecimento em promoção da saúde bucal. O ganho de conhecimento das turmas 2008-A e 2008-B foi progressivo e estatisticamente superior ao do grupo controle, assim como ocorreu com a habilidade de aconselhamento da turma 2008-B. CONCLUSÃO: As informações obtidas no presente estudo podem ser úteis para o desenvolvimento de estratégias de ensino interdisciplinar em áreas complementares da formação médica.

Radiation Shielding Information Center: a source of computer codes and data for fusion neutronics studies

International Nuclear Information System (INIS)

McGill, B.L.; Roussin, R.W.; Trubey, D.K.; Maskewitz, B.F.

1980-01-01

The Radiation Shielding Information Center (RSIC), established in 1962 to collect, package, analyze, and disseminate information, computer codes, and data in the area of radiation transport related to fission, is now being utilized to support fusion neutronics technology. The major activities include: (1) answering technical inquiries on radiation transport problems, (2) collecting, packaging, testing, and disseminating computing technology and data libraries, and (3) reviewing literature and operating a computer-based information retrieval system containing material pertinent to radiation transport analysis. The computer codes emphasize methods for solving the Boltzmann equation such as the discrete ordinates and Monte Carlo techniques, both of which are widely used in fusion neutronics. The data packages include multigroup coupled neutron-gamma-ray cross sections and kerma coefficients, other nuclear data, and radiation transport benchmark problem results

NEWSPEC: A computer code to unfold neutron spectra from Bonner sphere data

International Nuclear Information System (INIS)

Lemley, E.C.; West, L.

1996-01-01

A new computer code, NEWSPEC, is in development at the University of Arkansas. The NEWSPEC code allows a user to unfold, fold, rebin, display, and manipulate neutron spectra as applied to Bonner sphere measurements. The SPUNIT unfolding algorithm, a new rebinning algorithm, and the graphical capabilities of Microsoft (MS) Windows and MS Excel are utilized to perform these operations. The computer platform for NEWSPEC is a personal computer (PC) running MS Windows 3.x or Win95, while the code is written in MS Visual Basic (VB) and MS VB for Applications (VBA) under Excel. One of the most useful attributes of the NEWSPEC software is the link to Excel allowing additional manipulation of program output or creation of program input

Efficient preparation of large-block-code ancilla states for fault-tolerant quantum computation

Science.gov (United States)

Zheng, Yi-Cong; Lai, Ching-Yi; Brun, Todd A.

2018-03-01

Fault-tolerant quantum computation (FTQC) schemes that use multiqubit large block codes can potentially reduce the resource overhead to a great extent. A major obstacle is the requirement for a large number of clean ancilla states of different types without correlated errors inside each block. These ancilla states are usually logical stabilizer states of the data-code blocks, which are generally difficult to prepare if the code size is large. Previously, we have proposed an ancilla distillation protocol for Calderbank-Shor-Steane (CSS) codes by classical error-correcting codes. It was assumed that the quantum gates in the distillation circuit were perfect; however, in reality, noisy quantum gates may introduce correlated errors that are not treatable by the protocol. In this paper, we show that additional postselection by another classical error-detecting code can be applied to remove almost all correlated errors. Consequently, the revised protocol is fully fault tolerant and capable of preparing a large set of stabilizer states sufficient for FTQC using large block codes. At the same time, the yield rate can be boosted from O (t-2) to O (1 ) in practice for an [[n ,k ,d =2 t +1

KC-A Kinectic computer code for investigation of parametric plasma instabilities

International Nuclear Information System (INIS)

Olshansky, V.

1995-07-01

In the frame of a joint research program of the Institute of Plasma Physics of the NationaI Science Center 'Kharkov Institute of Physics and Technology' (Kh IPT), Ukraine, and the plasma physics group of the Austrian Research Center Seibersdorf (FZS) a kinetic computer code with the acronym KC for investigation of paramarametric plasma instabilities has been implemented at the computer facilities of FZS as a starting point for further research in this field. This code based on a macroparticle technique is appropriate for studying the evolution of instabilities in a turbulent plasma including saturation. The results can be of interest for heating of tokamaks of the next generation, i.g. ITER. The present report describes the underlying physical models and numerical methods as well as the code structure and how to use the code as a reference of forthcoming joint papers. (author)

PORST: a computer code to analyze the performance of retrofitted steam turbines

Energy Technology Data Exchange (ETDEWEB)

Lee, C.; Hwang, I.T.

1980-09-01

The computer code PORST was developed to analyze the performance of a retrofitted steam turbine that is converted from a single generating to a cogenerating unit for purposes of district heating. Two retrofit schemes are considered: one converts a condensing turbine to a backpressure unit; the other allows the crossover extraction of steam between turbine cylinders. The code can analyze the performance of a turbine operating at: (1) valve-wide-open condition before retrofit, (2) partial load before retrofit, (3) valve-wide-open after retrofit, and (4) partial load after retrofit.

Sample test cases using the environmental computer code NECTAR

International Nuclear Information System (INIS)

Ponting, A.C.

1984-06-01

This note demonstrates a few of the many different ways in which the environmental computer code NECTAR may be used. Four sample test cases are presented and described to show how NECTAR input data are structured. Edited output is also presented to illustrate the format of the results. Two test cases demonstrate how NECTAR may be used to study radio-isotopes not explicitly included in the code. (U.K.)

Standardization of computer programs - basis of the Czechoslovak library of nuclear codes

International Nuclear Information System (INIS)

Gregor, M.

1987-01-01

A standardized form of computer code documentation has been established in the CSSR in the field of reactor safety. Structure and content of the documentation are described and codes already subject to this process are mentioned. The formation of a Czechoslovak nuclear code library and facilitated discussion of safety reports containing results of standardized codes are aimed at

Quality assurance aspects of the computer code CODAR2

International Nuclear Information System (INIS)

Maul, P.R.

1986-03-01

The computer code CODAR2 was developed originally for use in connection with the Sizewell Public Inquiry to evaluate the radiological impact of routine discharges to the sea from the proposed PWR. It has subsequently bee used to evaluate discharges from Heysham 2. The code was frozen in September 1983, and this note gives details of its verification, validation and evaluation. Areas where either improved modelling methods or more up-to-date information relevant to CODAR2 data bases have subsequently become available are indicated; these will be incorporated in any future versions of the code. (author)

A restructuring of TF package for MIDAS computer code

International Nuclear Information System (INIS)

Park, S. H.; Song, Y. M.; Kim, D. H.

2002-01-01

TF package which defines some interpolation and extrapolation condition through user defined table has been restructured in MIDAS computer code. To do this, data transferring methods of current MELCOR code are modified and adopted into TF package. The data structure of the current MELCOR code using FORTRAN77 causes a difficult grasping of the meaning of the variables as well as waste of memory. New features of FORTRAN90 make it possible to allocate the storage dynamically and to use the user-defined data type, which lead to an efficient memory treatment and an easy understanding of the code. Restructuring of TF package addressed in this paper does module development and subroutine modification, and treats MELGEN which is making restart file as well as MELCOR which is processing calculation. The validation has been done by comparing the results of the modified code with those from the existing code, and it is confirmed that the results are the same. It hints that the similar approach could be extended to the entire code package. It is expected that code restructuring will accelerate the code domestication thanks to direct understanding of each variable and easy implementation of modified or newly developed models

Geometrical-optics code for computing the optical properties of large dielectric spheres.

Science.gov (United States)

Zhou, Xiaobing; Li, Shusun; Stamnes, Knut

2003-07-20

Absorption of electromagnetic radiation by absorptive dielectric spheres such as snow grains in the near-infrared part of the solar spectrum cannot be neglected when radiative properties of snow are computed. Thus a new, to our knowledge, geometrical-optics code is developed to compute scattering and absorption cross sections of large dielectric particles of arbitrary complex refractive index. The number of internal reflections and transmissions are truncated on the basis of the ratio of the irradiance incident at the nth interface to the irradiance incident at the first interface for a specific optical ray. Thus the truncation number is a function of the angle of incidence. Phase functions for both near- and far-field absorption and scattering of electromagnetic radiation are calculated directly at any desired scattering angle by using a hybrid algorithm based on the bisection and Newton-Raphson methods. With these methods a large sphere's absorption and scattering properties of light can be calculated for any wavelength from the ultraviolet to the microwave regions. Assuming that large snow meltclusters (1-cm order), observed ubiquitously in the snow cover during summer, can be characterized as spheres, one may compute absorption and scattering efficiencies and the scattering phase function on the basis of this geometrical-optics method. A geometrical-optics method for sphere (GOMsphere) code is developed and tested against Wiscombe's Mie scattering code (MIE0) and a Monte Carlo code for a range of size parameters. GOMsphere can be combined with MIE0 to calculate the single-scattering properties of dielectric spheres of any size.

PASC-1, Petten AMPX-II/SCALE-3 Code System for Reactor Neutronics Calculation

International Nuclear Information System (INIS)

Yaoqing, W.; Oppe, J.; Haas, J.B.M. de; Gruppelaar, H.; Slobben, J.

1995-01-01

1 - Description of program or function: The Petten AMPX-II/SCALE-3 Code System PASC-1 is a reactor neutronics calculation programme system consisting of well known IBM-oriented codes, that have been translated into FORTRAN-77, for calculations on a CDC-CYBER computer. Thus, the portability of these codes has been increased. In this system, some AMPX-II and SCALE-3 modules, the one-dimensional transport code ANISN and the 1 to 3-dimensional diffusion code CITATION are linked together on the CDC-CYBER/855 computer. The new cell code XSDRNPM-S and the old XSDRN code are included in the system. Starting from an AMPX fine group library up to CITATION, calculations can be performed for each individual module. Existing AMPX master interface format libraries, such as CSRL-IV, JEF-1, IRI and SCALE-45, and the old XSDRN-formatted libraries such as the COBB library can be used for the calculations. The code system contains the following modules and codes at present: AIM, AJAX, MALOCS, NITAWL-S, REVERT-I, ICE-2, CONVERT, JUAN, OCTAGN, XSDRNPM-S, XSDRN, ANISN and CITATION. The system will be extended with other SCALE modules and transport codes. 2 - Method of solution: The PASC-1 system is based on AMPX-II/SCALE-3 modules. Except for some SCALE-3 modules taken from the SCALIAS package, the original AMPX-II modules were IBM versions written in FORTRAN IV. These modules have been translated into CDC FORTRAN V. In order to test these modules and link them with some codes, some of the sample problem calculations have been performed for the whole PASC-1 system. During these calculations, some FORTRAN-77 errors were found in MALOCS, REVERT, CONVERT and some subroutines of SUBLIB (FORTRAN-77 subroutine library). These errors have been corrected. Because many corrections were made for the REVERT module, it is renamed as REVERT-I (improved version of REVERT). After these corrections, the whole system is running on a CDC-CYBER Computer (NOS-BE operating system). 3 - Restrictions on the

Atmospheric dispersion of radioactive releases: Computer code DIASPORA

International Nuclear Information System (INIS)

Synodinou, B.M.; Bartzis, J.M.

1982-05-01

The computer code DIASPORA is presented. Air and ground concentrations of an airborne radioactive material released from an elevated continuous point source are calculated using Gaussian plume models. Dry and wet deposition as well as plume rise effects are taken into consideration. (author)

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

Músicos de viento: afecciones bucales asociadas a instrumentos musicales de viento

OpenAIRE

Mendes, Claudia Andrea; Fernández, Rocío; Gamino, Adriana; Quevedo, José; Dorati, Pablo Javier; De Vicente, Cecilia; Felipe, Pablo; Barilaro, Hilda Liliana; Canale, Luis; Sirimarco, Karina; González, Stella; Rimoldi, Marta Lidia

2017-01-01

Los instrumentos de viento son un elemento extraño en la boca que pueden producir a corto o largo plazo alteraciones orofaciales: apiñamiento, desgastes incisales, hipertonía muscular, maloclusión dental, problemas periodontales, entre otras. El objetivo de este proyecto, surge, en la necesidad de realizar estudios clínicos que nos permitan obtener evidencias de la naturaleza de la relación entre los instrumentos de viento y la cavidad bucal para posteriormente poder optimizar los posibles tr...

Validation and uncertainty analysis of the Athlet thermal-hydraulic computer code

International Nuclear Information System (INIS)