Real time determination of dose radiation through artificial intelligence and virtual reality

International Nuclear Information System (INIS)

Freitas, Victor Goncalves Gloria

2009-01-01

In the last years, a virtual environment of Argonauta research reactor, sited in the Instituto de Engenharia Nuclear (Brazil), has been developed. Such environment, called here Argonauta Virtual (AV), is a 3D model of the reactor hall, in which virtual people (avatar) can navigate. In AV, simulations of nuclear sources and doses are possible. In a recent work, a real time monitoring system (RTMS) was developed to provide (by means of Ethernet TCP/I P) the information of area detectors situated in the reactor hall. Extending the scope of AV, this work is intended to provide a continuous determination of gamma radiation dose in the reactor hall, based in several monitored parameters. To accomplish that a module based in artificial neural network (ANN) was developed. The ANN module is able to predict gamma radiation doses using as inputs: the avatar position (from virtual environment), the reactor power (from RTMS) and information of fixed area detectors (from RTMS). The ANN training data has been obtained by measurements of gamma radiation doses in a mesh of points, with previously defined positions, for different power levels. Through the use of ANN it is possible to estimate, in real time, the dose received by a person at any position in Argonauta reactor hall. Such approach allows tasks simulations and training of people inside the AV system, without exposing them to radiation effects. (author)

Measurement of the epithermal neutron flux of the Argonauta reactor by the Sandwich method

International Nuclear Information System (INIS)

Nascimento, H.M.

1973-01-01

A common method of obtaining information about the neutron spectrum in the energy range of 1 eV to a few keV is by using resonance sandwich detectors. A sandwich detector is usually made up of three foils placed one on top of the other, each having the same thickness and being made of the same material which has a pronounced absorption resonance. To make an adequate evaluation, the sandwich method was compared with one using an isolated detector. The results obtained from approximate theoretical calculations were checked experimentally, using In, Au and Mn foils, in an isotropic 1/E flux in the Argonaut Reactor at I.E.N. As practical application of this method, the deviation from a 1/E spectrum of the epithermal neutron flux in the core and external graphite reflector of the Argonaut Reactor has been measured with the sandwich foils previously calibrated in a 1/E spectrum. (author)

Genetic requirements for Piwi-induced stable transgenerational gene silencing in Caenorhabditis elegans

OpenAIRE

Almeida, Miguel Duarte Dias de Vasconcelos, 1989-

2012-01-01

Tese de mestrado. Biologia (Biologia Evolutiva e do Desenvolvimento). Universidade de Lisboa, Faculdade de Ciências, 2012 A descoberta, em 1998, da interferência por RNA (RNAi) revelou que pequenos RNAs não codificantes estão envolvidos no controlo da expressão genética. Atualmente, várias vias de RNAi são conhecidas em Eucariotas. Apesar de divergirem em muitos aspetos, todas possuem complexos regulatórios envolvendo uma proteína Argonauta e um pequeno RNA. O complexo Argonauta-pequeno RN...

Aspects and application of etch-pit technique in the distribution detection of uranium in solids

International Nuclear Information System (INIS)

Sachett, I.A.

1973-01-01

Some aspects related to the use of standard glass microscope slide as solid state track detector are presented, as well as studies of measurement of distribution of uranium in various solids determined by means of this technique. The behavior of the various parameters related to the properties of the detector and the results of their measurements are treated. Results obtained on the determination of distribution of uranium in samples of fuel elements of the 'ARGONAUTA' research reactor of Instituto de Engenharia Nuclear - Rio de Janeiro, are included. The samples were taken from the fuel-cladding interface. Finally, some data on levels of contamination of the laboratory equipment in use by uranium during the course of this work are presented [pt

Estimation of environmental radiological implications arising from the operation of the Nuclear Engineering Institute - IEN, locate at Fundao Island, Rio de Janeiro, RJ, Brazil

International Nuclear Information System (INIS)

Peres, Sueli da Silva

1999-07-01

The Nuclear Engineering Institute is located at the Fundao Island in the City of the Rio de Janeiro, Brazil. The Institute works in several fields such as reactors, physics, radiation protection and radioactive waste management, instrumentation and control, chemistry and metallurgy. It has a nuclear installation, represented by the Argonauta reactor, and the other installations are classified as radioactive. During the operation of these installations, some radioactive liquid and gaseous effluents are generated and released into the sanitary sewerage system and in the atmosphere, respectively. The main radioactive effluents are generated during the radioisotopes production and processing. The critical radionuclides released by Institute, in the period covered by this work, from 1985 to 1995, were 65 Zn and 123 l, respectively for the aquatic and atmospheric pathways. This study has shown that the main radiation exposure pathways to man were the inhalation of 123 l contaminated plume and external exposure to the 65 Zn contaminated sewage sludge - coming from the final treatment of the liquid effluents at the Sewage Treatment Plant - in the Sanitary landfilling. Considering the conditions of operation studied, the individual equivalent doses received by the critical groups of the population did not exceed 1/500 of the annual limit of 1 mSv.ano -1 established by the Brazilian Nuclear Energy Commission for the members of the public. These values do not represent any significant radiological risk increase for the local population. Therefore, the exposure calculated in this work, 2 (μSv.year -1 , can be considered acceptable. However, any future dose increment should be carefully evaluated in terms of cost-benefit analysis, according to the system of dose limitation established in the national rules and in the recommendations of the ICRP. (author)

RMB. The new Brazilian multipurpose research reactor

International Nuclear Information System (INIS)

Perrotta, Jose Augusto; Soares, Adalberto Jose

2015-01-01

Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also presents the

RMB. The new Brazilian multipurpose research reactor

Energy Technology Data Exchange (ETDEWEB)

Perrotta, Jose Augusto; Soares, Adalberto Jose [Comissao Nacional de Energia Nuclear (CNEN) (Brazil)

2015-01-15

Brazil has four research reactors (RR) in operation: IEA-R1, a 5 MW pool type RR; IPR-R1, a 100 kW TRIGA type RR; ARGONAUTA, a 500 W Argonaut type RR, and IPEN/MB-01, a 100 W critical facility. The first three were constructed in the 50's and 60's, for teaching, training, and nuclear research, and for many years they were the basic infrastructure for the Brazilian nuclear developing program. The last, IPEN/MB-01, is the result of a national project developed specifically for qualification of reactor physics codes. Considering the relative low power of Brazilian research reactors, with exception of IEAR1, none of the other reactors are feasible for radioisotope production, and even IEA-R1 has a limited capacity. As a consequence, since long ago, 100% of the Mo-99 needed to attend Brazilian nuclear medicine services has been imported. Because of the high dependence on external supply, the international Moly-99 supply crisis that occurred in 2008/2009 affected significantly Brazilian nuclear medicine services, and as presented in previous IAEA events, in 2010 Brazilian government formalized the decision to build a new research reactor. The new reactor named RMB (Brazilian Multipurpose Reactor) will be a 30 MW open pool type reactor, using low enriched uranium fuel. The facility will be part of a new nuclear research centre, to be built about 100 kilometres from Sao Paulo city, in the southern part of Brazil. The new nuclear research centre will have several facilities, to use thermal and cold neutron beams; to produce radioisotopes; to perform neutron activation analysis; and to perform irradiations tests of materials and fuels of interest for the Brazilian nuclear program. An additional facility will be used to store, for at least 100 years, all the fuel used in the reactor. The paper describes the main characteristics of the new centre, emphasising the research reactor and giving a brief description of the laboratories that will be constructed, It also

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

International Nuclear Information System (INIS)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M.

2007-01-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

Virtual reality technology as a tool for human factors requirements evaluation in design of the nuclear reactors control desks

Energy Technology Data Exchange (ETDEWEB)

Grecco, Claudio H.S.; Santos, Isaac J.A.L.; Mol, Antonio C.A.; Carvalho, Paulo V.R.; Silva, Antonio C.F.; Ferreira, Francisco J.O.; Dutra, Marco A.M. [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: grecco@ien.gov.br; luquetti@ien.gov.br; mol@ien.gov.br; paulov@ien.gov.br; tonico@ien.gov.br; fferreira@ien.gov.br; dutra@ien.gov.br

2007-07-01

The Virtual Reality (VR) is an advanced computer interface technology that allows the user to internet or to explore a three-dimensional environment through the computer, as was part of the virtual world. This technology presents great applicability in the most diverse areas of the human knowledge. This paper presents a study on the use of the VR as tool for human factors requirements evaluation in design of the nuclear reactors control desks. Moreover, this paper presents a case study: a virtual model of the control desk, developed using virtual reality technology to be used in the human factors requirements evaluation. This case study was developed in the Virtual Reality Laboratory at IEN, and understands the stereo visualization of the Argonauta research nuclear reactor control desk for a static ergonomic evaluation using check-lists, in accordance to the standards and human factors nuclear international guides (IEC 1771, NUREG-0700). (author)

Improved people detection in nuclear plants by video processing for safety purpose

Energy Technology Data Exchange (ETDEWEB)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Carvalho, Paulo Victor R., E-mail: calexandre@ien.gov.br, E-mail: mol@ien.gov.br, E-mail: paulov@ien.gov.br [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.br, E-mail: eduardo@smt.ufrj.br [Coordenacao dos Programas de Pos-Graduacao em Engenharia (COPPE/UFRJ), RJ (Brazil). Programa de Engenharia Eletrica; Waintraub, Fabio, E-mail: fabiowaintraub@hotmail.com [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Escola Politecnica. Departamento de Engenharia Eletronica e de Computacao

2013-07-01

This work describes improvements in a surveillance system for safety purposes in nuclear plants. The objective is to track people online in video, in order to estimate the dose received by personnel, during working tasks executed in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a nuclear research reactor, Argonauta. Cameras have been installed within Argonauta room, supplying the data needed. Video processing methods were combined for detecting and tracking people in video. More specifically, segmentation, performed by background subtraction, was combined with a tracking method based on color distribution. The use of both methods improved the overall results. An alternative approach was also evaluated, by means of blind source signal separation. Results are commented, along with perspectives. (author)

Improved people detection in nuclear plants by video processing for safety purpose

International Nuclear Information System (INIS)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Carvalho, Paulo Victor R.; Seixas, Jose M.; Silva, Eduardo Antonio B.; Waintraub, Fabio

2013-01-01

This work describes improvements in a surveillance system for safety purposes in nuclear plants. The objective is to track people online in video, in order to estimate the dose received by personnel, during working tasks executed in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a nuclear research reactor, Argonauta. Cameras have been installed within Argonauta room, supplying the data needed. Video processing methods were combined for detecting and tracking people in video. More specifically, segmentation, performed by background subtraction, was combined with a tracking method based on color distribution. The use of both methods improved the overall results. An alternative approach was also evaluated, by means of blind source signal separation. Results are commented, along with perspectives. (author)

Occupational radioprotection program at Nuclear Engineering Institute -IEN: results obtained in 1991

International Nuclear Information System (INIS)

Fajardo, P.W.; Pastura, V.F.S.; Soares, M.L.; LeRoy, C.L.; Teixeira, M.V.; Santos, I.H.T.; Pujol Filho, S.V.

1992-01-01

The results of occupational radioprotection program at Nuclear Engineering Institute-IEN- in 1991 are presented. The personnel monitoring, the routine monitoring of limited areas, the operational monitoring during the operation and the cyclotron CV-28 maintenance, the radioisotope processing and Argonauta Reactor operation, the control of radioprotection equipment and the control of radiation sources are included. (C.G.C.)

People detection in nuclear plants by video processing for safety purpose

Energy Technology Data Exchange (ETDEWEB)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A., E-mail: calexandre@ien.gov.b, E-mail: mol@ien.gov.b [Instituto de Engenharia Nuclear (IEN/CNEN), Rio de Janeiro, RJ (Brazil); Seixas, Jose M.; Silva, Eduardo Antonio B., E-mail: seixas@lps.ufrj.b, E-mail: eduardo@lps.ufrj.b [Coordenacao dos Programas de Pos-Graduacao de Engenharia (COPPE/UFRJ), Rio de Janeiro, RJ (Brazil). Programa de Engenharia Eletrica; Cota, Raphael E.; Ramos, Bruno L., E-mail: brunolange@poli.ufrj.b [Universidade Federal do Rio de Janeiro (EP/UFRJ), RJ (Brazil). Dept. de Engenharia Eletronica e de Computacao

2011-07-01

This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

People detection in nuclear plants by video processing for safety purpose

International Nuclear Information System (INIS)

Jorge, Carlos Alexandre F.; Mol, Antonio Carlos A.; Seixas, Jose M.; Silva, Eduardo Antonio B.; Cota, Raphael E.; Ramos, Bruno L.

2011-01-01

This work describes the development of a surveillance system for safety purposes in nuclear plants. The final objective is to track people online in videos, in order to estimate the dose received by personnel, during the execution of working tasks in nuclear plants. The estimation will be based on their tracked positions and on dose rate mapping in a real nuclear plant at Instituto de Engenharia Nuclear, Argonauta nuclear research reactor. Cameras have been installed within Argonauta's room, supplying the data needed. Both video processing and statistical signal processing techniques may be used for detection, segmentation and tracking people in video. This first paper reports people segmentation in video using background subtraction, by two different approaches, namely frame differences, and blind signal separation based on the independent component analysis method. Results are commented, along with perspectives for further work. (author)

Microstructure in welding zone of a zircaloy 4 tube welded by TIG process

International Nuclear Information System (INIS)

Bolfarini, C.; Domingues Filho, H.

1982-01-01

The details concerned with the welding of seamless zircaloy 4 tubes for nuclear application and the earlier welding tests made in the tubes that will be used for the construction of the Argonautas' Reactor fuel element, are described. Based on the references the microestructure changes in the heat affected zone were analyzed in respect to the material's performance in operation. (Author) [pt

Brazilian reactors under safeguards

International Nuclear Information System (INIS)

1967-01-01

Three nuclear reactors in Brazil have been placed under Agency safeguards against diversion to military use. They are used for research purposes under a bilateral treaty with the USA, and are located at Rio de Janeiro, Sao Paulo and Belo Horizonte

Non-destructive assay of mechanical components using gamma-rays and thermal neutrons

Energy Technology Data Exchange (ETDEWEB)

Souza, Erica Silvani; Avelino, Mila R. [PPG-EM/UERJ, R. Sao Francisco Xavier, 524, Maracana - Rio de Janeiro - RJ (Brazil); Almeida, Gevaldo L. de; Souza, Maria Ines S. [IEN/CNEN, Rua Helio de Almeida, 75, Ilha do Fundao, Rio de Janeiro - RJ (Brazil)

2013-05-06

This work presents the results obtained in the inspection of several mechanical components through neutron and gamma-ray transmission radiography. The 4.46 Multiplication-Sign 10{sup 5} n.cm{sup -2}.s{sup -1} thermal neutron flux available at the main port of the Argonauta research reactor in Instituto de Engenharia Nuclear has been used as source for the neutron radiographic imaging. The 412 keV {gamma}-ray emitted by {sup 198}Au, also produced in that reactor, has been used as interrogation agent for the gamma radiography. Imaging Plates - IP specifically designed to operate with thermal neutrons or with X-rays have been employed as detectors and storage devices for each of these radiations.

Performance of a thermal neutron radiographic system using imaging plates

International Nuclear Information System (INIS)

Silvani, Maria Ines; Almeida, Gevaldo L. de; Furieri, Rosanne; Lopes, Ricardo T.

2009-01-01

A performance evaluation of a neutron radiographic system equipped with a thermal neutron sensitive imaging plate has been undertaken. It includes the assessment of spatial resolution, linearity, dynamic range and the response to exposure time, as well as a comparison of these parameters with the equivalent ones for neutron radiography employing conventional films and a gadolinium foil as converter. The evaluation and comparison between the radiographic systems have been performed at the Instituto de Engenharia Nuclear - CNEN, using the Argonauta Reactor as source of thermal neutrons and a commercially available imaging plate reader. (author)

On the Performance of X-ray Imaging Plates in Gamma Radiography employing Reactor-produced Radioisotopes

Science.gov (United States)

Silvani, Maria Ines; de Almeida, Gevaldo L.; Furieri, Rosanne C.; Lopes, Ricardo T.

2011-08-01

Gamma-radiography employing radiographic films is a well established technique for non-destructive assays. The advent of X-ray sensitive Imaging Plates opens up new possibilities to apply this technique thanks to the advantages exhibited by this new device. Indeed, besides a sensitivity about 20 times higher then the conventional photographic film, requiring thus a shorter exposure time, it does not require a dark room for a cumbersome and time-consuming chemical processing associated to the development, an can be erased to be reused many times. Moreover, its development carried out by means of a laser beam produces digitalized images which can be promptly stored in a computer. Although its resolution is still poorer than that of the conventional film, those advantages overwhelms this specific parameter when it is not an essential feature for the intended application. This work evaluates the feasibility of employing X-ray Imaging Plates as detector for higher photon energies as those emitted by reactor-produced radioisotopes. Within this frame, radioisotopes such as 198Au and 56Mn, produced at the Argonauta research reactor in the Instituto de Engenharia Nuclear-CNEN have been employed as sources to acquire radiographic images of several pieces of equipment, devices and components. In order to keep the source appearance—with regard to the detector—as punctual as possible, reducing hence the penumbra effect, the mass of the irradiated material had to be limited. Therefore, due to the low neutron flux available at the main port of the reactor, the exposure times have to be extended along several hours or even a couple of days in order to reach an image with adequate contrast. This demand, nevertheless, does not constitute a serious hindrance as the exposure process can be carried out without any intervention or surveillance. Results have shown that in spite of the higher photon energies used, surpassing the X-ray range for which the imaging plates have been

Rio+20

Directory of Open Access Journals (Sweden)

Robert Horn

2012-10-01

Full Text Available This reflection on Rio+20 examines many of the major social institutions and how they fulfilled their functions during the United Nations Conference on Sustainable Development at Rio. The institutions are: 1. Nation-states as a collective. 2. Individual nation-states. 3. Vanguard institutions (some NGOs. 4. Action and convening NGOs. 5. Global media. 6. Governments of nation-states acting domestically 7. Individual governments in bilateral and multilateral situations. 8. Similar institutions in different countries acting together. 9. Businesses. 10. Global science. Each is considered within the assumptions of what the society expects them to deliver (in general, what is possible for them to deliver, and what they did deliver at Rio. In approaching Rio+20, our account differs considerably from much of the reportage by the mainstream media.

O RIO CAPITAL IMAGINADO PELA CRÍTICA CINEMATOGRÁFICA: os casos de Rio Fantasia e Rio, 40 graus

Directory of Open Access Journals (Sweden)

Eliska Altmann

Full Text Available No artigo, busca-se verificar como o Rio de Janeiro, “cidade-capital”, foi imaginado por críticos cinematográficos brasileiros. Por meio de críticas aos filmes Rio fantasia (1957, de Watson Macedo, e Rio, 40 graus (1955, de Nelson Pereira dos Santos, pretende-se entender como a então Capital Federal foi descrita e legitimada por agentes que formam julgamentos, quiçá, para a posteridade.

Environmental impact assessment, from Rio-92 to Rio+20 and beyond

Directory of Open Access Journals (Sweden)

Luis E. Sánchez

2012-12-01

Full Text Available The 1992 Rio Earth Summit was of paramount importance in the consolidation and international dissemination of environmental impact assessment, officially recognized as a tool for informed decision-making towards sustainable development (Principle 17, Rio Declaration and for protection of biodiversity (Article 14, Convention on Biological Diversity. A significant development afterwards was the strengthening of strategic environmental assessment in the design of policies, plans and programs. Both forms of impact assessment can establish the necessary connections between one goal of the Rio+20 Conference - reaching an agreement on the transition to a green economy - and the underpinning decision making processes. Although the Rio+20 Summit has faced challenges to acknowledge its potential, impact assessment should be strengthened in support of both government and business decisions.La Cumbre de la Tierra de 1992 fue de la más grande importancia en la consolidación y diseminación de la evaluación de impacto ambiental, oficialmente reconocida como una herramienta para la toma de decisiones informada hacia el desarrollo sostenible (Principio 17, Declaración de Rio y para la protección de la biodiversidad (Artículo 14, Convención de la Diversidad Biológica. Un avanzo posterior importante fue el fortalecimiento de la evaluación ambiental estratégica en la preparación de políticas, planos y programas. Ambas formas de evaluación de impacto son capaces de establecer los necesarios vínculos entre un objetivo declarado de la Conferencia Rio+2- - llegar a un acuerdo sobre la transición para una economía verde - y los procesos decisorios subyacentes. Aunque la Cumbre Rio+20 tenga encontrado dificultades en reconocer su potencial, la evaluación de impactos debería ser fortalecida en soporte de decisiones gubernamentales y privadas.A Cúpula da Terra de 1992, no Rio de Janeiro, teve a maior importância na consolidação e dissemina

Corrosion behaviour of aluminium plates in aqueous medium

International Nuclear Information System (INIS)

Oliveira, M.F. de; Gaio, J.C.

1985-01-01

The process of corrosion concerning the aluminium 1050 plate was studied at room temperatures, 45 and 60 0 C in deionized water, the same Argonauta Reactor Water. Beyond the temperature influence, it was verified the effect of chloride ion and oxygen. It ws found that the amount of oxyde formed at room temperatures is almost negligible; at 45 and 60 0 C the samples were covered with bayerita, the quantity of oxide formed at 45 0 C being higher than at 60 0 C. It was observed that there will be risk of corrosion in the case of Reactor Water to undergo contamination with chloride ions. The results have shown that the material can be used since the medium don't be strongly oxidizing. At potentials higher than - 900M sup(V) ess (-280 m sup(V) sub(H)), the material will undergo pitting corrosion. (Author) [pt

Rio+20 ou Rio-20?: crônica de um fracasso anunciado

Directory of Open Access Journals (Sweden)

Roberto Pereira Guimarães

2012-12-01

Full Text Available Passadas quatro décadas da Conferência de Estocolmo sobre o Meio Ambiente Humano, e decorridos apenas alguns meses da Rio+20, parece apropriado analisar o caminho percorrido a partir de Rio-92 e os desafios, em grande parte frustrados, da conferência recém concluída no Rio de Janeiro. Para tais propósitos, são analisados os avanços e retrocessos da agenda global de desenvolvimento sustentável, do processo preparatório e dos resultados alcançados no Rio em Junho de 2012, como também das ameaças provocadas pela nova agenda de segurança estratégica após os eventos de 11 Setembro de 2001 e pela crise econômica e financeira que já dura praticamente uma década. O artigo conclui com as perspectivas da agenda internacional nos próximos anos.Pasadas cuatro décadas desde la Conferencia de Estocolmo sobre Medio Ambiente Humano, y transcorridos tan solo algunos meses de la Rio+20, pareciera apropiado analisar el camino percorrido a partir de la Rio-92 y los desafíos, en grande parte frustrados, de la conferencia recien concluída en Rio de Janeiro. Para tales propósitos, serán analisados los avances e retrocesos en la agenda global de desarrollo sustentable, en el proceso preparatorio y en los resultados alcanzados en Rio en Junho de 2012, como también de las amenazas provocadas por la nueva agenda de segurida estratégica luego de los eventos de 11 Setembro de 2001 y por la crisis económica y financiera que ya dura prácticamente una década. El artículo concluye con las perspectivas de la agenda internacional em los próximos anos.After four decades since the Stockholm Conference on the Human Environment and after just a few months of Rio+20, it seems appropriate to assess the path followed since Rio+92 and the challenges, mostly frustrated, posed by Rio+20 . For this purpose, it is analyzed the advances and shortcomings of the global agenda of sustainable development, of the preparatory process and the results achieved in Rio

Vigilando la Calidad del Agua de los Grandes Rios de la Nacion: El Programa NASQAN del Rio Grande (Rio Bravo del Norte)

Science.gov (United States)

Lurry, Dee L.; Reutter, David C.; Wells, Frank C.; Rivera, M.C.; Munoz, A.

1998-01-01

La Oficina del Estudio Geologico de los Estados Unidos (U.S. Geological Survey, 0 USGS) ha monitoreado la calidad del agua de la cuenca del Rio Grande (Rio Bravo del Norte) desde 1995 como parte de la rediseiiada Red Nacional para Contabilizar la Calidad del Agua de los Rios (National Stream Quality Accounting Network, o NASOAN) (Hooper and others, 1997). EI programa NASOAN fue diseiiado para caracterizar las concentraciones y el transporte de sedimento y constituyentes quimicos seleccionados, encontrados en los grandes rios de los Estados Unidos - incluyendo el Misisipi, el Colorado y el Columbia, ademas del Rio Grande. En estas cuatro cuencas, el USGS opera actualmente (1998) una red de 40 puntos de muestreo pertenecientes a NASOAN, con un enfasis en cuantificar el flujo en masa (la cantidad de material que pasa por la estacion, expresado en toneladas por dial para cada constituyente. Aplicacando un enfoque consistente, basado en la cuantificacion de flujos en la cuenca del Rio Grande, el programa NASOAN esta generando la informacion necesaria para identificar fuentes regionales de diversos contaminantes, incluyendo sustancias qui micas agricolas y trazas elementos en la cuenca. EI efecto de las grandes reservas en el Rio Grande se puede observar segun los flujos de constituyentes discurren a 10 largo del rio. EI analisis de los flujos de constituyentes a escala de la cuenca proveera los medios para evaluar la influencia de la actividad humana sobre las condiciones de calidad del agua del Rio Grande.

Retinue of the beans roots growth by using neutron radiography technique

International Nuclear Information System (INIS)

Jesus, Selma Parente de; Crispim, Verginia Reis

2002-01-01

Agricultural practices frequently cause the development of a soil compacted layer below the surface. These compacted layers restrict the root penetration into deeper layers of soil, in search for water. It is proposed to monitor, using Non Destructive Test, the roots growth due to the planting of standard seeds in different agricultural soils, in function of their compactness and humidity. It will be used the neutrons beams derived from an irradiation channel called J-9 of the Reactor Argonauta (IEN/CNEN), so that the neutron radiographic images of the soil-plant system can be obtained. Each root can be evaluated for its ability to penetrate into compacted soil layers; this fact would mean an optimization of agricultural harvests. (author)

76 FR 80430 - Rio Tinto plc and Rio Tinto Limited; Notice of Application

Science.gov (United States)

2011-12-23

... plc and Rio Tinto Limited; Notice of Application December 19, 2011. AGENCY: Securities and Exchange Commission (``Commission''). ACTION: Notice of application under section 3(b)(2) and 45(a) of the Investment Company Act of 1940 (the ``Act''). SUMMARY: Summary of Application: Rio Tinto plc (``RTP'') and Rio Tinto...

Programa de controle do tabagismo do hospital universitário Cassiano Antônio de Moraes: perfil de usuários e funcionários

Directory of Open Access Journals (Sweden)

Lorena ALBERTASSE

2013-09-01

Full Text Available funcionários do Hospital Universitário Cassiano Antônio de Moraes, quanto a aspectos socioeconômicos e tabagísticos. Metodologia: Trata-se de um estudo descritivo e exploratório, conduzido sobre abordagem quantitativa. Resultados: Entre os usuários do serviço, 19,2% são fumantes e 24% ex-fumante. A faixa etária em que mais se fuma foi a de 20-39 anos (8,5%. 39,2% dos usuários fumantes possuem o Ensino Fundamental Incompleto e renda de até 2 salários mínimos (41,3%. A quantidade em anos que se fuma é maior naqueles que fumam há mais de 10 anos (42,3%. Entre os funcionários o número de fumantes foi de 12 (12,2%, sendo que 5 (41,6% fumam há mais de 20 anos; 66,7% tinham o Ensino Médio e 67,6% recebiam renda de 2-5 salários mínimos. Nos dois grupos estudados foi elevada à prevalência de fumantes que referiu o desejo de cessar o fumo (74% usuários, 83,3% funcionários, no entanto apenas uma pequena parcela já se submeteu a algum tipo de tratamento.

Nos caminhos do pai: influências de Francisco Palmério na formação do escritor Mário Palmério

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André Azevedo da Fonseca

2011-12-01

Full Text Available O artigo traça uma biografia de Francisco Palmério (1867-1947, pai do escritor mineiro Mário Palmério (1916-1996 – autor de Vila dos Confins (1956 e Chapadão do Bugre (1965. Através de fontes primárias e análise documental, a pesquisa desenvolve interpretações sobre as influências paternas de caráter moral, cultural, intelectual e profissional que marcaram a primeira geração da família Palmério no Brasil e, particularmente, condicionaram as experiências que mais tarde seriam ressignificadas na obra literária e na trajetória pessoal de Mário Palmério. Notamos que as permanentes viagens a trabalho do pai e as suas diversas atividades profissionais favoreceram uma consciência familiar das particularidades da região. Essa experiência favoreceu a criação de vínculos econômicos, políticos e afetivos com a cultura regional e estimulou nos filhos um profundo conhecimento histórico e geográfico do Oeste mineiro. Além disso, o pai parece ter exercido uma profunda influência sobre os filhos no que diz respeito ao gosto pela política regional. O artigo desenvolve a hipótese de que todas essas experiências foram elementos presentes na formação de Mário Palmério e, mais tarde, apareceriam de modo explícito em sua literatura marcada pela descrição da natureza, do cotidiano e das intrigas políticas regionalistas. Palavras-chave: Regionalismo; Literatura regionalista; Literatura mineira; Mário Palmério; Vila dos Confins; Chapadão do Bugre.

Search for other natural fission reactors

International Nuclear Information System (INIS)

Apt, K.E.; Balagna, J.P.; Bryant, E.A.; Cowan, G.A.; Daniels, W.R.; Vidale, R.J.

1977-01-01

Precambrian uranium ores have been surveyed for evidence of other natural fission reactors. The requirements for formation of a natural reactor direct investigations to uranium deposits with large, high-grade ore zones. Massive zones with volumes approximately greater than 1 m 3 and concentrations approximately greater than 20 percent uranium are likely places for a fossil reactor if they are approximately greater than 0.6 b.a. old and if they contained sufficient water but lacked neutron-absorbing impurities. While uranium deposits of northern Canada and northern Australia have received most attention, ore samples have been obtained from the following worldwide locations: the Shinkolobwe and Katanga regions of Zaire; Southwest Africa; Rio Grande do Norte, Brazil; the Jabiluka, Nabarlek, Koongarra, Ranger, and El Sharana ore bodies of the Northern Territory, Australia; the Beaverlodge, Maurice Bay, Key Lake, Cluff Lake, and Rabbit Lake ore bodies and the Great Bear Lake region, Canada. The ore samples were tested for isotopic variations in uranium, neodymium, samarium, and ruthenium which would indicate natural fission. Isotopic anomalies were not detected. Criticality was not achieved in these deposits because they did not have sufficient 235 U content (a function of age and total uranium content) and/or because they had significant impurities and insufficient moderation. A uranium mill monitoring technique has been considered where the ''yellowcake'' output from appropriate mills would be monitored for isotopic alterations indicative of the exhumation and processing of a natural reactor

The BDS iGMAS RIOS station at Observatório Nacional, Rio de Janeiro

Science.gov (United States)

Humberto Andrei, Alexandre; Song, Shuli; Junqueira, Selma; Beauvalet, Laurene

2016-07-01

GNSS navigation satellites are currently being developed by all major players in the science and technology scene, to compete with the GPS system. Because their applications span many different areas, from traffic and cargo control, to geodesy and seismic monitoring, it is required to assess the coherence between the different constellations. BDS is the GNSS system currently developed in China. Its first generation of satellites consisted of 3 geostationnary satellites allowing geolocalisation in China only. In addition to these satellites, other satellites have been launched in geostationnary and geosynchronous orbits, as well as satellites orbiting with a classical GNSS semi-major axis. With these additions, the BDS system possesses 19 operating satellites, and though the system is mostly efficient for geolocalisation in Asia, the satellites are also visible in other parts of the globe. In parallel to the development of the BDS constellation, China has launched the iGMAS (International GNSS Monitoring and Assessment Service) project to develop a global tracking network of multi-GNSS geodetic receivers. One of the goals of this project is to evaluate the efficiency of the BDS constellation as well as the efficiency of the receivers developed by the Chinese laboratories. As part of the Brazilian program COSBAN leaded by the Foreign Affairs Ministry to foster up the science and technology partnership with China, materialized by the collaboration between the Shanghai Astronomical Observatory/CAS and the Observatório Nacional/MCTI, in Rio de Janeiro. Through it the RIOS-iGMAS station was installed at Observatório Nacional, where the RJEP GNSS station already operates as part of the Brazilian reference system. Thus at the Observatório Nacional can be observed satellites from any constellation with both systems of reception, leading to a direct, efficient way to compare the results obtained for each network. In this communication we focus on the determination of the

Abiquiu Dam and Reservoir, Rio Grande Basin, Rio Chama, New Mexico. Embankment Criteria and Performance Report.

Science.gov (United States)

1987-04-01

EMBANKMENT CRITERIA AND PERFORMANCE REPORT PERTINENT DATA 1. General Data. LOCATION: Rio Arriba County, New Mexico, on the Rio Chama at river mile 33. PURPOSE...is located across the Rio Chama, approximately 30 miles upstream from its confluence with the Rio Grande, in Rio Arriba County, New Mexico. The dam is...6600- 4 i ’. 6600 65060- -60 6600- a + v6500s-go FA**v~w -6500 6300- 60 - ~ ~ ~ wo Ala filll------------------ EMBNKEN SECTION62 *LDN WOR SAFEL VAIE

DIREITO AGRÁRIO E O TRATAMENTO DOS CONTRATOS AGRÁRIOS ATÍPICOS

OpenAIRE

Fabrício Pinto Weiblen; Marcelo Scherer da Silva; Tarso Wayhs Tech; José Fernando Lutz Coelho

2012-01-01

Aborda a necessidade de um tratamento adequado e diferenciado aos contratos agrários atípicos em face das complexas relações que se desenvolvem no meio rural atualmente. Apresenta ainda uma visão crítica a respeito das características e aplicabilidade da legislação agrária no cenário jurídico e propõe alternativas com o objetivo de uma prestação mais eficiente do Direito Agrário na área contratual.

Fotocatálise heterogênea com TiO2 aplicada ao tratamento de esgoto sanitário secundário TiO2 heterogeneous photocatalysis in secondary wastewater treatment

Directory of Open Access Journals (Sweden)

Ivete Vasconcelos Lopes Ferreira

2004-12-01

Full Text Available Neste trabalho são apresentados resultados da aplicação da fotocatálise heterogênea utilizando dióxido de titânio imobilizado sobre placa de vidro, irradiado por luz solar, para desinfecção de esgoto sanitário secundário. Utilizou-se o efluente de um reator anaeróbio/aeróbio com leito expandido de carvão ativado que trata o esgoto do Campus da USP/São Carlos, e também de contribuições domésticas. Os experimentos foram do tipo batelada, com tempo de recirculação de 4 horas. As vazões estudadas foram 15, 22,5 e 30 L/h. Foram avaliadas as remoções de matéria orgânica (DQO e COT e a inativação de microrganismos indicadores de contaminação fecal (coliformes totais, E. coli, Clostridium perfringens e colifagos.The results of wastewater anaerobic-aerobic reactor effluent disinfected with heterogeneous photocatalysis using titanium dioxide fixed in a glass plate and solar radiation are presented in this work. The anaerobic-aerobic reactor has a granular activated carbon expanded bed and it receives the wastewater collected in the Campus of São Paulo University at São Carlos-SP, Brazil, and from the surrounding neighborhood of the campus. The assays were conducted in batch with recirculation time of 4 hours. The flow rate used was of 15, 22.5 and 30 L/h. The removal of organic matter (COD and TOC and inactivation of total coliforms, E. coli, Clostridium perfringens and coliphages was evaluated.

Design of a Loose Part Monitoring System Test-bed using CompactRIO

Energy Technology Data Exchange (ETDEWEB)

Kim, Min-seok; Lee, Kwang-Dae; Lee, Eui-Jong [KHNP CRI, Daejeon (Korea, Republic of)

2016-10-15

A loose part monitoring system (LPMS) is included in the NSSS integrity monitoring system (NIMS), which serves to detect loose parts in reactor coolant systems (RCS). LPMSs at Nuclear Power Plants (NPPs) in Korea follow the ASME OM standard and acquire data from 18 sensors simultaneously. Data acquisition requires a sampling rate of more than 50KHz along with a 12bit A/D converter. Existing LPMS equipment is composed of several different platforms, such as a digital signal processor (DSP), a field-programmable gate array (FPGA), a micro control unit (MCU), and electric circuit cards. These systems have vulnerabilities, such as discontinuance due to aging and incompatibility issues between different pieces of equipment. This paper suggests CompactRIO as a new platform. We devised a Test-bed using CompactRIO and demonstrate that the proposed method meets the criteria required by the standard. The LPMS provides an alert when an impact event occurs and provides information with which to analyze the location, energy, and mass of the loose parts. LPMSs in NPPs in Korea operate on a variety of platforms. Thus, these systems are vulnerable to discontinuances due to aging and incompatibilities arising from the use of different type of equipment. In order to solve these problems, this paper suggests CompactRIO as a new platform. It is a rugged, reconfigurable, high-performance industrial embedded system. The results of performance tests meet the criteria set by the current standard.

Carcinoma inflamatório mamário canino.

OpenAIRE

Gomes, Cristiano; Voll, Juliana; Ferreira, Kelly; Ferreira, Rafael Rodrigues; Oliveira, Luciana Oliveira de; Contesini, Emerson Antônio; Oliveira, Rosemari Teresinha de

2006-01-01

O carcinoma inflamatório mamário é um carcinoma anaplásico com características clínicas e histopatológicas como crescimento rápido, envolvimento difuso, eritema, calor e dor nas mamas, edema nos membros posteriores, extensa infiltração de células inflamatórias, células epiteliais malignas nos linfonodos regionais apresentando um péssimo prognóstico. O cão é a única espécie animal em que esta neoplasia ocorre espontaneamente, entretanto apresenta uma incidência bastante rara tanto em humanos q...

Acesso a ambulatório pediátrico de um hospital universitário

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Selma C. Franco

1998-08-01

Full Text Available INTRODUÇÃO: No Brasil verifica-se um descompasso entre o aumento das necessidades de atenção à saúde e de sua oferta. O Sistema Único de Saúde, cujas deretrizes preconizam a atenção universal e eqüânime, determina a relevância desta temática dentro do campo da avaliação dos serviços de saúde. Assim, foram estudados dois ambulatórios de pediatria de um hospital universitário, um geral e outro de uma subespecialiadade (pneumologia, comparando os usuários quanto ao acesso. MÉTODO: Foram aplicados 221 questionários entre clientes de ambos os ambulatórios de pediatria com o objetivo de se estudar e comparar variáveis socioeconômicas, procedência, acesso aos referidos ambulatórios e outros serviços de saúde. RESULTADOS: Evidenciou-se grande dificuldade de locomoção dos pacientes, a maioria dos quais são encaminhados por serviços de saúde locais. Dos pacientes atendidos 40% não receberam nenhum atendimento anteriormente à sua chegada ao hospital, fato que decorre principalmente de seu baixo nível socioeconômico, que os torna dependentes exclusivamente dos serviços públicos de saúde. A comparação entre os dois ambulatórios mostra que os pacientes do ambulatório de especialidade têm melhor nível socioeconômico e são menos dependentes dos serviços públicos, configurando desta forma uma situação de ineqüidade. CONCLUSÕES: É apontado o melhor nível socioeconômico dos usuários da especialidade bem como questões organizacionais do próprio serviço como os responsáveis pela iniqüidade verificada.

Ovários policísticos: critérios hemodinâmicos

OpenAIRE

Ávila,Márcio Augusto Pinto de; Murta,Carlos Geraldo Viana

2001-01-01

O advento da ultra-sonografia endovaginal de alta resolução abriu novas áreas de pesquisa nos ovários policísticos. O conhecimento da hemodinâmica ovariana é fundamental para o entendimento do comportamento fisiopatológico dos ovários policísticos. Os autores tecem considerações sobre a possibilidade da utilização do Doppler colorido na melhor definição dos ovários policísticos. Os dados sugerem que o aumento da vascularidade e a diminuição da resistência dos vasos do estroma ovariano, assim ...

Detection of drugs and plastic explosives using neutron tomography

Energy Technology Data Exchange (ETDEWEB)

Ferreira, F.J.O. [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil)], E-mail: fferreira@ien.gov.br; Crispim, V.R; Silva, A.X. [Universidade Federal do Rio de Janeiro (UFRJ), RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia (COPPE). Programa de Engenharia Nuclear], E-mail: ademir@con.ufrj.br, E-mail: verginia@com.ufrj.br

2007-07-01

The unique ability of neutrons to image certain elements and isotopes that are either completely undetectable or poorly detected by other Non-Destructive-Assay (NDA) methods makes neutron radiography an important tool for the NDA community. Neutron radiography, like other imaging techniques takes a number of different forms (i.e. / that is film, radioscopic, transfer methods, tomography, etc.) In this work report the Neutron Tomography System developed, which will allow inspections NDA of samples with high efficiency, in terms of minors measure time and the result analysis, and the application for detection of drugs and plastic explosives, which is very important for the combat to the terrorism and drug trafficking. The neutron tomography system developed is third generation. Therefore a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel to this a suitable electronic imaging device has been designed and can be controlled by a computer in order to synchronize the software the detector and of the rotary table with the aim of an automation of measurements. To obtain 2D tomography image, a system with an electronic imaging system for producing real time neutron radiography. Images are processing digital for cancel random noise effects and to optimize spatial resolution. Finally, using a (ARIEN) algorithm reconstruction of tomography images by finite element maximum entropy. The system was installed adjacent to the exit of the J-9 irradiation channel of the Argonauta Reactor in the Nuclear Engineering Institute (IEN) - which is an organ of the National Nuclear Energy Commission (CNEN - Brazil).The Argonauta reactor operates at 340 watts, being that the characteristics of the neutron beam on the plane of the image: thermal neutron flux 4,46 x10{sup 5} n/cm{sup 2}s. In the tomography assays, several encapsulated samples of paste, rock and cocaine powder and plastic explosives devices

Detection of drugs and plastic explosives using neutron tomography

International Nuclear Information System (INIS)

Ferreira, F.J.O.; Crispim, V.R; Silva, A.X.

2007-01-01

The unique ability of neutrons to image certain elements and isotopes that are either completely undetectable or poorly detected by other Non-Destructive-Assay (NDA) methods makes neutron radiography an important tool for the NDA community. Neutron radiography, like other imaging techniques takes a number of different forms (i.e. / that is film, radioscopic, transfer methods, tomography, etc.) In this work report the Neutron Tomography System developed, which will allow inspections NDA of samples with high efficiency, in terms of minors measure time and the result analysis, and the application for detection of drugs and plastic explosives, which is very important for the combat to the terrorism and drug trafficking. The neutron tomography system developed is third generation. Therefore a rotary table driven by a step motor connected to a computerized motion control system has been installed at the sample position. In parallel to this a suitable electronic imaging device has been designed and can be controlled by a computer in order to synchronize the software the detector and of the rotary table with the aim of an automation of measurements. To obtain 2D tomography image, a system with an electronic imaging system for producing real time neutron radiography. Images are processing digital for cancel random noise effects and to optimize spatial resolution. Finally, using a (ARIEN) algorithm reconstruction of tomography images by finite element maximum entropy. The system was installed adjacent to the exit of the J-9 irradiation channel of the Argonauta Reactor in the Nuclear Engineering Institute (IEN) - which is an organ of the National Nuclear Energy Commission (CNEN - Brazil).The Argonauta reactor operates at 340 watts, being that the characteristics of the neutron beam on the plane of the image: thermal neutron flux 4,46 x10 5 n/cm 2 s. In the tomography assays, several encapsulated samples of paste, rock and cocaine powder and plastic explosives devices. (author)

Rio responses in the Netherlands

International Nuclear Information System (INIS)

Bruggink, J.J.C.

1994-01-01

Three of the five agreements reached in Rio - the Rio Declaration, Agenda 21 and the Framework Convention on Climate Change - are briefly summarised from and energy perspective. The state of the art in the two national policy areas that are crucial for sustainable development, environmental policy and development cooperation, are then described. Some conclusions are drawn regarding the major bottlenecks and challenges for Dutch policies in the wake of Rio. 2 figs

Riscos de cont?gio em tuberculose entre funcion?rios em um hospital universit?rio no munic?pio de Niter?i - Rio de Janeiro

OpenAIRE

Couto, Ingrid Ramos Reis

2012-01-01

Problema: O aparecimento de casos de adoecimentos por tuberculose entre os funcion?rios do HUAP. Objetivos: Analisar os fatores de risco para tuberculose e o perfil epidemiol?gico dos funcion?rios do HUAP/UFF com resultado da prova tubercul?nica ? 10 mm no per?odo de 2007 a junho de 2011; - Investigar os casos de adoecimento por tuberculose em funcion?rios do HUAP/UFF no per?odo de janeiro de 2004 a julho de 2011; - Identificar a poss?vel associa??o entre o perfil epidemiol?gico dos funcion?r...

Foundational development of an advanced nuclear reactor integrated safety code

International Nuclear Information System (INIS)

Clarno, Kevin; Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth; Hooper, Russell Warren; Humphries, Larry LaRon

2010-01-01

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Foundational development of an advanced nuclear reactor integrated safety code.

Energy Technology Data Exchange (ETDEWEB)

Clarno, Kevin (Oak Ridge National Laboratory, Oak Ridge, TN); Lorber, Alfred Abraham; Pryor, Richard J.; Spotz, William F.; Schmidt, Rodney Cannon; Belcourt, Kenneth (Ktech Corporation, Albuquerque, NM); Hooper, Russell Warren; Humphries, Larry LaRon

2010-02-01

This report describes the activities and results of a Sandia LDRD project whose objective was to develop and demonstrate foundational aspects of a next-generation nuclear reactor safety code that leverages advanced computational technology. The project scope was directed towards the systems-level modeling and simulation of an advanced, sodium cooled fast reactor, but the approach developed has a more general applicability. The major accomplishments of the LDRD are centered around the following two activities. (1) The development and testing of LIME, a Lightweight Integrating Multi-physics Environment for coupling codes that is designed to enable both 'legacy' and 'new' physics codes to be combined and strongly coupled using advanced nonlinear solution methods. (2) The development and initial demonstration of BRISC, a prototype next-generation nuclear reactor integrated safety code. BRISC leverages LIME to tightly couple the physics models in several different codes (written in a variety of languages) into one integrated package for simulating accident scenarios in a liquid sodium cooled 'burner' nuclear reactor. Other activities and accomplishments of the LDRD include (a) further development, application and demonstration of the 'non-linear elimination' strategy to enable physics codes that do not provide residuals to be incorporated into LIME, (b) significant extensions of the RIO CFD code capabilities, (c) complex 3D solid modeling and meshing of major fast reactor components and regions, and (d) an approach for multi-physics coupling across non-conformal mesh interfaces.

Em foco: sustentabilidade Rio 2016, Agosto 2015

OpenAIRE

2015-01-01

Neste endereço, é possível encontrar o primeiro relatório de sustentabilidade do Rio 2016, "Abraçando Mudanças", bem como o Plano de Gestão de Sustentabilidade, o Relatório de Gestão de Pegada de Carbono e o Relatório de Impacto dos Jogos.

Visualization of two-phase flow in metallic pipes using neutron radiographic technique

International Nuclear Information System (INIS)

Luiz, L.C.; Crispim, V.R.

2007-01-01

The study of two-phase flow is a matter of great interest both for the engineering and oil industries. The production of oil and natural gas involves the transportation of fluids in their liquid and gaseous states, respectively, to the processing plant for refinement. The forecasting of two-phase flow in oil pipes is of the utmost important yet an extremely difficult task. With the development of the electronic imaging system, installed in J-9 irradiation channel of the IEN/CNEN Argonauta Reactor, it is possible to visualize the different types of two phase air-water flows in small-diameter metallic pipes. After developing the captured image the liquid-gas drift flux correlation as well as the void fraction in relation to the injected air outflow for a fixed water outflow can be obtained. (author)

Refractory oxides containing aluminium and barium Oxidos refratários contendo alumínio e bário

Directory of Open Access Journals (Sweden)

T. J. Davies

1998-10-01

Full Text Available Oxides containing aluminium and barium, optionally with chromium, are refractory with several possible industrial uses. A gel precursor of an oxide having the formula BaO.n(Al2xCr2yO3, where 1Oxidos contendo alumínio e bário, opcionalmente com crômio, são refratários com vários possíveis usos industriais. Foi preparado um gel precursor de um óxido de formula BaO.n(Al2xCr2yO3, com 1rio com uma solução de um sal de bário com solução de um sal de alumínio ou uma solução de um sal de alumínio e um sal de cromo III, formando então um gel que é queimado para se obter o óxido desejado. Filamentos podem ser estraídos duramente a formação do gel ou extrudados de um gel semi-rígido. Estudos de infravermelho com transformada de Fourier, difração de raios X e ressonância magnética nuclear com 27AL mostraram que o bário não é incorporado diretamente na estrutura do gel. Oxidos de alumínio e bário foram obtidos somente após liquefação de espécies de bário. Foi preparada uma mistura de pós adequada para queima para se obter um óxido de fórmula BaO.m[Al2x Cr2y O3] com 4,6rio, óxido de bário, carbonato de bário e mono-aluminato de bário, alumina e/ou alumina hidratada e óxido de cromo III, com quantidades relativas variando para se obter na queima valores desejados de m e de y. Corpos cerâmicos resistentes da fórmula BaO 6 Al2O3 (m=6 e y=0 foram preparados. Estudos de difração de raios X de óxidos de composições (n ou m=6 e y=0 sinterizados em alta temperatura mostraram que mono-aluminato de bário é uma fase intermediária de baixa temperatura. Cromo III reduz a temperatura necessária para formar um óxido de alumínio e bário. É feito um sumário de trabalhos anteriormente publicados.

On Brazil's participation in the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO)

International Nuclear Information System (INIS)

Goncalves Filho, Orlando Joao Agostinho

2007-01-01

In response to a resolution of its 44th General Conference (GC(44)/RES/21) held in September 2000, the International Atomic Energy Agency launched in May 2001 the International Project on Innovative Nuclear Reactors and Fuels Cycles (INPRO) with the objective of supporting the safe, sustainable, economic and proliferation-resistant use of nuclear technology to meet the global energy needs of the 21st century. Brazil joined the project from its beginnings and in 2005 submitted a proposal for the screening assessment using INPRO methodology of two small-size light-water reactors as potential components of an innovative nuclear reactor system (INS) completed with a conventional open nuclear fuel cycle. The INS reactor components currently being assessed are the International Reactor Innovative and Secure (IRIS) that is being developed by an international consortium made of 21 organizations from 10 countries (Brazil included) led by the Westinghouse Company, and the Fixed Bed Nuclear Reactor (FBNR) that is being developed at the Federal University of Rio Grande do Sul. This paper gives an overview of Brazil's participation in INPRO, highlighting the objective, scope and intermediate results of the assessment study being performed, and the possibilities for participation in one or two collaborative research projects under INPRO Phase 2 Action Plan for 2008-2009. (author)

Fitossociologia de florestas de mangue plantadas e naturais no estuário do Rio das Ostras, Rio de Janeiro, Brasil

Directory of Open Access Journals (Sweden)

Elaine Bernini

2013-10-01

Full Text Available http://dx.doi.org/10.5007/2175-7925.2014v27n1p37 A fitossociologia de florestas de mangue plantadas e naturais foi comparada no estuário do Rio das Ostras, Rio de Janeiro, Brasil. A amostragem da vegetação foi feita pelo método de parcelas, sendo registrado o diâmetro à altura do peito (DAP e a altura dos indivíduos > 1 m de altura. Os resultados indicaram que a floresta plantada apresenta menores valores de DAP médio e área basal, e maior densidade de troncos em relação à floresta natural. A distribuição de indivíduos por classes de altura e a distribuição de troncos por classes diamétricas mostraram que a floresta plantada é mais jovem. Laguncularia racemosa e Rhizophora mangle ocorreram em ambas as florestas, enquanto Avicennia schaueriana foi registrada apenas na floresta plantada. Laguncularia racemosa apresentou maior dominância e densidade relativa em todos os sítios analisados, provavelmente, por ser característica de locais com menor influência marinha e pelo fato do estuário ter sido alterado por perturbações antrópicas.

Análise da qualidade de água dos principais rios do município de Rio Negrinho (SC / Analysis of water quality of principal rivers in the Rio Negrinho city (SC

Directory of Open Access Journals (Sweden)

Simone Malutta

2013-01-01

Full Text Available As bacias hidrográficas do rio Preto e do rio Negrinho são as principais unidades do município de Rio Negrinho (SC. Nestas, há pontos de monitoramento de alguns parâmetros de qualidade de água realizados pelo Programa Intermunicipal da Água. O objetivo do presente trabalho foi realizar a análise da qualidade de água nesses vários pontos de monitoramento nos principais rios desse município. Para entender melhor os recursos hídricos da região em termos tanto de qualidade quanto de quantidade, foram feitas análises de correlações entre os dados monitorados de qualidade de água e os dados de vazão diários simulados pelo modelo SWAT. Não se encontrou correlação significativa entre os dados de vazão simulados pelo modelo SWAT e os dados de qualidade de água em todos os pontos analisados. Foi identificado que os rios Serrinhas e Banhado, os quais se localizam na bacia do rio Negrinho, apresentaram índices de qualidade de água inferiores aos demais rios estudados devido principalmente aos efluentes provindos da urbanização. Foi identificado que há medianas, vários outlier e valores extremos dos parâmetros de DBO e OD que ficaram muito acima da legislação vigente.

Efeito do retorno de lodo aeróbio sobre as características da biomassa presente em reatores UASB tratando esgoto sanitário Effect of aerobic sludge return on the characteristics of anaerobic biomass present in UASB reactors treating domestic sewage

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Patrícia Procópio Pontes

2009-06-01

Full Text Available O presente trabalho buscou avaliar a influência do retorno do lodo produzido em filtros biológicos percoladores (FBP sobre as características da biomassa em reatores UASB utilizados para o tratamento de esgoto sanitário. Os experimentos foram conduzidos em reatores em escala piloto e em escala de demonstração, sendo que os reatores UASB foram operados com e sem retorno do lodo produzido nos FBP. Os resultados obtidos indicaram uma diminuição no diâmetro das partículas de lodo, durante as fases com retorno de lodo, mas apenas para as amostras de lodo tomadas nos pontos mais altos dos reatores anaeróbios. A estabilidade e a atividade metanogênica específica do lodo anaeróbio praticamente não se modificaram com o retorno de lodo. Conforme esperado, a produção específica de lodo anaeróbio aumentou com o retorno de lodo.This work aimed at evaluating the influence of the return of excess aerobic sludge produced in trickling filters (TF upon the biomass characteristics in UASB reactors used for the treatment of domestic sewage. The experiments were carried out in pilot and demonstration-scale reactors, with the UASB reactors being operated with and without the return of sludge produced in the TF. Smaller sludge particle sizes were observed when the aerobic sludge was returned to the UASB reactor, but only for sludge samples collected in the upper parts of the anaerobic reactors. Sludge stability and specific methanogenic activity were not affected by the return of sludge. As expected, the specific anaerobic sludge production increased with the return of sludge.

CONSTRUÇÃO DE IDENTIDADE(S NA VELHICE: OS TERRITÓRIOS ENQUANTO MARCOS IDENTITÁRIOS

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Marcia Regina Medeiros Veiga

Full Text Available RESUMO Este artigo tem por objetivo refletir sobre o contributo específico dos territórios - a casa, a rua, o entorno - enquanto referência fundamental na construção identitária de pessoas idosas. Nossa base reflexiva foi construída a partir de observações e descrições do território conhecido como "Alta", no casco histórico de Coimbra, Portugal; entrevistas semiestruturadas, com 12 de seus residentes; e com notas de campo, sistematizadas num diário de bordo da pesquisa, construído para o efeito. A construção identitária de grande parte das pessoas idosas encontra-se profundamente ancorada nos territórios onde vivem, principalmente quando estas pessoas residem há muito tempo em um mesmo espaço geográfico, no qual vivenciam uma parte muito substantiva do seu cotidiano. Esta centralidade é, ainda, reforçada quando apresentam mobilidades reduzidas ou condicionadas, quer pelas dificuldades de acessibilidade dos próprios territórios, quer por limitações pessoais, iniciadas e/ou acentuadas na velhice.

Deforestation near Rio Branco, Brazil

Science.gov (United States)

2001-01-01

Settlement and deforestation surrounding the Brazilian town of Rio Branco are seen here in the striking 'herring bone' deforestation patterns that cut through the rainforest. Rio Brancois the capital of the Brazilian state of Acre and is situated near the border with northeastern Bolivia. The town is a center for the distribution of goods, including rubber, metals, medicinal plants, Brazil nuts and timber. Colonization projects in the region are supported by farming, logging activities, and extensive cattle ranching. Much of the surrounding terrain is of a poorly-draining clay hardpan soil, and heavy rainfall periodically converts parts of the forested region to swamp.The large overview image was acquired by the Multi-angle Imaging SpectroRadiometer's vertical-viewing (nadir) camera on July 28, 2000, and covers an area of 336 kilometers x 333 kilometers. A plume of smoke is visible north of the Rio Branco road, which roughly parallels the slender, twisting Rio Abuna. Most of the major rivers in the image provide reference points for state or international (Bolivia-Brazil) boundaries, and flow northeast to the Rio Madeira (east of the smoke plume). The border between Acre and the Bolivian department of Pando is marked by the Rio Abuna. Pando's southern boundary with the department of Beni is marked by the Rio Madre de Dios, the large river in the lower half of the image.The two higher-resolution inset images highlight a settled area north of the town of Rio Branco. These nadir views cover an area of 60 kilometers x 67 kilometers, and were acquired eleven months apart during Terra orbits 3251 and 8144. In the later image, more haze is present, possibly due to smoke from fires on that day. Comparing the two images provides a method of measuring the changes and expansion in the area of cleared land. One newly cleared patch is apparent near the middle of the later image, slightly off to the right. This polygon represents an area of about 16 square kilometers, or 4000

TERRITÓRIOS E FRONTEIRAS AMAZÔNICAS

OpenAIRE

Nogueira, Ricardo José Batista

2014-01-01

O texto apresenta uma discussão sobre a diversidade de territórios e fronteiras na Amazônia. Demonstra as diferenças entre fronteiras políticas e econômicas e a mobilidade no interior destes territórios. Aponta ainda que a criação de novos territórios - ecológicos e étnicos - instituiu novas fronteiras às populações rurais.

Sulfato de bário versus carbonato de bário: um trágico equívoco de solubilidade

OpenAIRE

NEVES, Eduardo Almeida; NEVES, Regina Maria de Almeida

2004-01-01

Envenenamento seguido de morte de pessoas que ingeriram um sulfato de bário preparado em laboratório farmacêutico (em exames de Raios X), foram vítimas de produto contendo alguma porcentagem de carbonato de bário como contaminante. Tratamento por equilíbrio químico dos dados de solubilidade dos precipitados nas condições de acidez estomacal mostrou que a presença do carbonato de bário causa um aumento de solubilidade de 19200 vezes em íons de bário, em comparação com a esperada pelo sulfat...

Rock in Rio: forever young

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Ricardo Ferreira Freitas

2014-12-01

Full Text Available The purpose of this article is to discuss the role of Rock in Rio: The Musical, as herald of megafestival Rock in Rio. Driven by the success that musicals have reached in Brazil, we believe that the design of this spectacle of music, dance and staging renews the brand of the rock festival, once it adds the force of young and healthy bodies to its concept. Moreover, the musical provides Rock in Rio with some distance from the controversal trilogy of sex, drugs and rock and roll, a strong mark of past festivals around the world. Thus, the musical expands the possibilities of growth for the brand.

Comportamento aleatório: algumas considerações

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Barba Lourenço de Souza

2000-01-01

Full Text Available Este estudo defende que o comportamento aleatório pode tornar-se legítimo objeto de estudo de uma ciência do comportamento. Analisamos inicialmente algumas considerações que B. F. Skinner formulou sobre o comportamento aleatório em suas Contingências do Reforço. Segundo Skinner (1969/1975, o comportamento aleatório "não apresenta interesse como processo de comportamento". Apresentamos uma rigorosa definição de "comportamento aleatório". Sustentamos que o comportamento aleatório pode constituir objeto de análise funcional, examinando alguns estudos empíricos que se têm conduzido sobre o comportamento aleatório. Apresentamos ainda algumas dificuldades empíricas e teóricas que podem afetar as investigações nessa área. Concluímos que o comportamento aleatório é um fascinante e importante tópico para uma completa ciência do comportamento.

Inventário de Emissões de Gases de Efeito Estufa no Campus Gávea da PUC-Rio

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João Paulo Andrade F. de Carvalho

Full Text Available RESUMO O presente trabalho apresenta resultados preliminares de um inventário de emissões de gases de efeito estufa (GEE elaborado para o campus da PUC-Rio, situado no bairro da Gávea, zona sul da cidade do Rio de Janeiro. Foram identificadas emissões de GEE nos escopos 1 (combustão estacionária e móvel, emissões fugitivas, escopo 2 (consumo de energia elétrica e escopo 3 (transporte, viagens, geração e descarte de resíduos sólidos, seguindo metodologias recomendadas pelo Programa Brasileiro GHG Protocol. Dentre as fontes de emissão, a mais difícil de quantificar foi justamente a principal geradora, relacionada com os deslocamentos entre o campus e as residências dos 20 mil potenciais frequentadores diários da PUC-Rio durante 2011.

Tratamento de esgoto sanitário em sistemas alagados construídos cultivados com lírio-amarelo

OpenAIRE

Prata,Renata C. C.; Matos,Antonio T. de; Cecon,Paulo R.; Monaco,Paola A. V. Lo; Pimenta,Leonardo A.

2013-01-01

Neste artigo, avaliou-se a eficiência de quatro sistemas alagados construídos (SACs) no tratamento de esgoto sanitário após ser submetido a tratamento preliminar e, no caso de alguns SACs, a tratamento primário (tanque séptico). Os SACs foram cultivados com lírio-amarelo (Hemerocallis flava), tendo a brita #0 como meio suporte, e submetidos às taxas de carregamento orgânico (TCO) de esgoto sanitário, em termos de DBO (kg ha-1 d-1), de 44; 98; 230 e 395 kg ha-1 d-1 e tempos de detenção hidrául...

Mesohabitats, fish assemblage composition, and mesohabitat use of the Rio Grande silvery minnow over a range of seasonal flow regimes in the Rio Grande/Rio Bravo del Norte, in and near Big Bend National Park, Texas, 2010-11

Science.gov (United States)

Moring, J. Bruce; Braun, Christopher L.; Pearson, Daniel K.

2014-01-01

In 2010–11, the U.S. Geological Survey (USGS), in cooperation with the U.S. Fish and Wildlife Service, evaluated the physical characteristics and fish assemblage composition of mapped river mesohabitats at four sites on the Rio Grande/Rio Bravo del Norte (hereinafter Rio Grande) in and near Big Bend National Park, Texas. The four sites used for the river habitat study were colocated with sites where the U.S. Fish and Wildlife Service has implemented an experimental reintroduction of the Rio Grande silvery minnow (Hybognathus amarus), a federally listed endangered species, into part of the historical range of this species. The four sites from upstream to downstream are USGS station 08374340 Rio Grande at Contrabando Canyon near Lajitas, Tex. (hereinafter the Contrabando site), USGS station 290956103363600 Rio Grande at Santa Elena Canyon, Big Bend National Park, Tex. (hereinafter the Santa Elena site), USGS station 291046102573900 Rio Grande near Ranger Station at Rio Grande Village, Tex. (hereinafter the Rio Grande Village site), and USGS station 292354102491100 Rio Grande above Stillwell Crossing near Big Bend National Park, Tex. (hereinafter the Stillwell Crossing site).

Itinerário dos usuários de medicamentos via judicial no estado do Amazonas, Brasil

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Marselle Nobre de Carvalho

2014-12-01

Full Text Available Este artigo teve como objetivo analisar o itinerário dos usuários que tiveram acesso a medicamentos via judicial no estado do Amazonas, Brasil. Trata-se de estudo qualitativo, prospectivo, baseado em dados coletados por meio de entrevistas semiestruturadas com usuários que receberam medicamentos via mandado judicial. A judicialização na saúde mostrou-se um fator agregador ao reconhecimento dos direitos e da cidadania pelos usuários que, na sua trajetória de vida, acabaram adquirindo um grande aprendizado sobre formas de enfrentar a falta de acesso aos medicamentos. Conclui-se que a relação entre o sujeito e o Estado permanece desigual, e o direito à saúde se deu na dimensão individual e restritiva, desconsiderando a dimensão coletiva e a concepção de cidadania.

Albuquerque/Middle Rio Grande Urban Waters Viewer

Science.gov (United States)

These data have been compiled in support of the Middle Rio Grande/Albuquerque Urban Waters Partnership for the region including Albuquerque, New Mexico.The Middle Rio Grande/Albuquerque Urban Waters Federal Partnership is co-chaired by the U.S. Dept. of Housing and Urban Development and the U.S. Environmental Protection Agency. There are also a number of other federal agencies engaged in projects with Tribal, State, and local officials, and community stakeholders. Like many western river ecosystems, the Middle Rio Grande faces numerous challenges in balancing competing needs within a finite water supply and other resource constrains. Historical practices by our ancestors and immigrants to the Middle Rio Grande have established the conditions that we have inherited. Long-term drought exacerbated by climate change is changing conditions that affect natural and human communities as we strive to improve our precious Rio Grande.The Middle Rio Grande/Albuquerque Urban Waters Federal Partnership will reconnect our urban communities, particularly those that are overburdened or economically distressed, with the waterway by improving coordination among federal agencies and collaborating with community-led revitalization efforts. Our projects will improve our community water systems and promote their economic, environmental and social benefits. Specifically, the Middle Rio Grande/Albuquerque Urban Waters Federal Partnership will support the development of the Valle de Oro

O Barão do Rio Branco no Itamaraty (1902-1912 Baron of Rio Branco in Itamaraty (1902-1912

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Clodoaldo Bueno

2012-12-01

Full Text Available Os cem anos do fim da gestão do Barão do Rio Branco no Ministério das Relações Exteriores do Brasil coincidem com um momento politicamente propício para se revisitar o legado do patrono da diplomacia brasileira, em especial o referente aos Estados Unidos e ao Prata, os dois principais eixos das relações externas do País. Examinam-se o teor das relações com a potência hegemônica do hemisfério e o caráter oscilante daquelas com a Argentina. A partir de fontes primárias e bibliográficas, o autor procura demonstrar que Rio Branco, além do fechamento dos limites do território nacional, firmou tendências e procedimentos que se incorporaram à tradição da diplomacia brasileira, analisando, para isso, a função do alinhamento Rio de Janeiro-Washington no conjunto da política externa do chanceler e o padrão das relações com o governo argentino, fatores que influenciaram seus movimentos no entorno geográfico. A política de prestígio desenvolvida por Rio Branco decorreu da aspiração em diferenciar seu país do conjunto de nações do segmento sul do hemisfério, identificadas com convulsões políticas e insolvência financeira.The hundredth anniversary of the end of Baron of Rio Branco's administration at the Brazilian Ministry of External Relations matches with a politically favorable moment for examining the legacy of the patron of the Brazilian Diplomacy, especially concerning the United States and the Río de la Plata, the two main axes of Brazilian foreign relations. It examines the content of the relations with the hemisphere's hegemonic power and the oscillating nature of the relations with Argentina. Using primary and bibliographic sources, the author aims to demonstrate that, in addition to accomplishing the process of delimiting the country's boundaries, Rio Branco established trends and procedures which were incorporated into the Brazilian Diplomatic Tradition. For this, the author analyzes the role the Rio de

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

International Nuclear Information System (INIS)

Henry, A.F.

1980-01-01

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

Reactor core in FBR type reactor

International Nuclear Information System (INIS)

Masumi, Ryoji; Kawashima, Katsuyuki; Kurihara, Kunitoshi.

1989-01-01

In a reactor core in FBR type reactors, a portion of homogenous fuels constituting the homogenous reactor core is replaced with multi-region fuels in which the enrichment degree of fissile materials is lower nearer to the axial center. This enables to condition the composition such that a reactor core having neutron flux distribution either of a homogenous reactor core or a heterogenous reactor core has substantially identical reactivity. Accordingly, in the transfer from the homogenous reactor core to the axially heterogenous reactor core, the average reactivity in the reactor core is substantially equal in each of the cycles. Further, by replacing a portion of the homogenous fuels with a multi-region fuels, thereby increasing the heat generation near the axial center, it is possiable to reduce the linear power output in the regions above and below thereof and, in addition, to improve the thermal margin in the reactor core. (T.M.)

Record of Pleopis schmackeri (Poppe Branchiopoda in Rio das Ostras, Rio de Janeiro, Brazil

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Wanda Maria Monteiro-Ribas

2013-03-01

Full Text Available The paper describes the first occurrence of Pleopis schmackeri (Poppe, 1889 (Branchiopoda, Onychopoda in Rio das Ostras, Rio de Janeiro, Brazil is described. This marine cladoceran species occurred in zooplanktonic samples obtained on July, 2003 with mean density of 10 ind.m-3. Its presence may be related to two hypotheses, due to ballast water and through the Brazilian current, which gets closer to the coast Winter.

Reactor core and initially loaded reactor core of nuclear reactor

International Nuclear Information System (INIS)

Koyama, Jun-ichi; Aoyama, Motoo.

1989-01-01

In BWR type reactors, improvement for the reactor shutdown margin is an important characteristic condition togehter with power distribution flattening . However, in the reactor core at high burnup degree, the reactor shutdown margin is different depending on the radial position of the reactor core. That is , the reactor shutdown margin is smaller in the outer peripheral region than in the central region of the reactor core. In view of the above, the reactor core is divided radially into a central region and as outer region. The amount of fissionable material of first fuel assemblies newly loaded in the outer region is made less than the amount of the fissionable material of second fuel assemblies newly loaded in the central region, to thereby improve the reactor shutdown margin in the outer region. Further, the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower portion of the first fuel assemblies is made smaller than the ratio between the amount of the fissionable material in the upper region and that of the fissionable material in the lower region of the second fuel assemblies, to thereby obtain a sufficient thermal margin in the central region. (K.M.)

Aspectos de leiaute e de design de lojas de vestuário: estudo da percepção dos usuários

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Márcia Machado França

2017-05-01

Full Text Available Esta pesquisa tem como objetivo analisar o leiaute e os elementos do design tais como: iluminação, mobiliário presentes nos espaços da rede de varejo do vestuário do modelo fast fashion e a influência destes na percepção dos usuários. Foram realizadas entrevistas semiestruturadas e observação não participante com os usuários destes espaços, buscando informações da interação deles com o ambiente. A revisão da literatura abordou os seguintes tópicos: design de lojas, modelo fast fashion, varejo de moda e usuários do vestuário. Por meio dos dados da pesquisa será possível identificar possíveis obstáculos do ambiente de loja para poder gerar melhores alternativas deste espaço ao usuário. Esta pesquisa aponta para abertura de novas oportunidades de exploração do design de lojas nos segmentos de varejo, por meio dos levantamentos obtidos nesta pesquisa.

RIO: a program to determine reliability importance and allocate optimal reliability goals

International Nuclear Information System (INIS)

Poloski, J.P.

1978-09-01

The designer of a nuclear plant must know the plant's associated risk limitations so that he can design the plant accordingly. To design a safety system, he must understand its importance and how it relates to the overall plant risk. The computer program RIO can aid the designer to understand a system's contribution to the plant's overall risk. The methodology developed and presented was sponsored by the Nuclear Research Applications Division of the Department of Energy for use in the Gas Cooled Fast Breeder Reactor (GCFR) Program. The principal motivation behind its development was the need to translate nuclear plants safety goals into reliability goals for systems which make up that plant. The method described herein will make use of the GCFR Accident Initiation and Progression Analyses (AIPA) event trees and other models in order to determine these reliability goals

Teorias do abuso no planejamento tributário

OpenAIRE

Luís Flávio Neto

2011-01-01

O presente estudo analisa teorias do abuso no planejamento tributário. Inicialmente, busca-se definir e diferenciar planejamento tributário, planejamento tributário abusivo e evasão fiscal, partindo-se da premissa de que compete a cada Estado estabelecer, de forma peculiar, quais os critérios devem ser adotados para a identificação dessas figuras em seu ordenamento jurídico. Analisam-se os princípios constitucionais que podem ser ponderados no Brasil em relação a esse tema. Diante das teses q...

Os limiares planetários, a Rio+20 e o papel do Brasil

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Eduardo Viola

Full Text Available Neste artigo consideramos os problemas ambientais globais dentro do conceito de limiares planetários, em convergência com os últimos avanços das ciências naturais. Nesse contexto, nosso objetivo é explorar o papel do Brasil na governança do espaço de operação seguro para a humanidade, avaliando como o país complementa o enorme capital ambiental físico que possui com ações políticas específicas orientadas para uma economia verde de baixo carbono (EVBC, tanto no âmbito doméstico quanto no internacional. Para atingir essa meta, em primeiro lugar discutimos conceitualmente a economia verde de baixo carbono como paradigma de desenvolvimento compatível com um espaço de operação seguro para a humanidade; em segundo lugar, analisamos a Rio+20 pelo prisma da governança global dos limiares planetários e pela atuação brasileira na Cúpula; e finalmente fazemos um diagnóstico da situação do Brasil em relação ao novo paradigma de desenvolvimento. Como conclusões da análise, destacamos a crescente distância entre a aceleração dos problemas da interdependência - especialmente a definição de um espaço seguro de operação para a humanidade - e os mecanismos globais de governança existentes, derivada de um sistema internacional bloqueado e dominado por forças conservadoras. O resultado frustrante da Rio+20 é evidência clara dessa defasagem. Nessa dinâmica, o Brasil tem o potencial para ser um ator central da governança dos limiares planetários, por seu vasto capital ambiental físico. No entanto, o mínimo avanço da EVBC no país degrada essa capacidade de agência, e o torna uma potência ambiental subdesenvolvida (underachiever environmental power.

Nuclear reactor physics course for reactor operators

International Nuclear Information System (INIS)

Baeten, P.

2006-01-01

The education and training of nuclear reactor operators is important to guarantee the safe operation of present and future nuclear reactors. Therefore, a course on basic 'Nuclear reactor physics' in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The aim of the basic course on 'Nuclear Reactor Physics for reactor operators' is to provide the reactor operators with a basic understanding of the main concepts relevant to nuclear reactors. Seen the education level of the participants, mathematical derivations are simplified and reduced to a minimum, but not completely eliminated

Reactor core of FBR type reactor

International Nuclear Information System (INIS)

Hayashi, Hideyuki; Ichimiya, Masakazu.

1994-01-01

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

PRONTUÁRIO ELETRÔNICO DO PACIENTE: REVISÃO DE LITERATURA

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Luan Barbosa Hubner

2017-03-01

Full Text Available O prontuário eletrônico é uma ferramenta de grande auxilio para gestão em unidade básica de saúde (UBS, hospitais e clinicas. Quando falamos de prontuário eletrônico percebemos que possui vários nomes, como: Prontuário do Paciente, Prontuário Familiar, Prontuário Médico, Prontuário Hospitalar, Registro do Paciente entre outros. Com a ideia de melhorar o atendimento dos pacientes, garantir segurança para os dados e manter um histórico do paciente da sua vida toda, se seu uso for bem trabalhado com cuidado e alimentado o sistema corretamente irá ser de grande aproveitamento e ajuda para a instituição. Diante disto o objetivo do presente estudo é uma revisão de literatura, para avaliar a eficácia da implantação de um prontuário eletrônico. Nenhum estudo mostrou que o prontuário teve efeito negativo em sua implantação, apenas apresenta algumas desvantagens, sendo a implantação do prontuário eletrônico de grande valia em UBS que ainda não os possuem.

Nuclear reactors

International Nuclear Information System (INIS)

Barre, Bertrand

2015-10-01

After some remarks on the nuclear fuel, on the chain reaction control, on fuel loading and unloading, this article proposes descriptions of the design, principles and operations of different types of nuclear reactors as well as comments on their presence and use in different countries: pressurized water reactors (design of the primary and secondary circuits, volume and chemistry control, backup injection circuits), boiling water reactors, heavy water reactors, graphite and boiling water reactors, graphite-gas reactors, fast breeder reactors, and fourth generation reactors (definition, fast breeding). For these last ones, six concepts are presented: sodium-cooled fast reactor, lead-cooled fast reactor, gas-cooled fast reactor, high temperature gas-cooled reactor, supercritical water-cooled reactor, and molten salt reactor

Availability analysis of the nuclear instrumentation of a research reactor

International Nuclear Information System (INIS)

Vianna Filho, Alfredo Marques

2016-01-01

The maintenance of systems and equipment is a central question related to Production Engineering. Although systems are not fully reliable, it is often necessary to minimize the failure occurrence likelihood. The failures occurrences can have disastrous consequences during a plane flight or operation of a nuclear power plant. The elaboration of a maintenance plan has as objective the prevention and recovery from system failures, increasing reliability and reducing the cost of unplanned shutdowns. It is also important to consider the issues related to organizations safety, especially those dealing with dangerous technologies. The objective of this thesis is to propose a method for maintenance analysis of a nuclear research reactor, using a socio-technical approach, and focused on existing conditions in Brazil. The research reactor studied belongs to the federal government and it is located in the city of Rio de Janeiro. The specific objective of this thesis is to develop the availability analysis of one of the principal systems of the research reactor, the nuclear instrumentation system. In this analysis, were taken into account not only the technical aspects of the modules related to nuclear instrumentation system, but also the human and organizational factors that could affect the availability of the nuclear instrumentation system. The results showed the influence of these factors on the availability of the nuclear instrumentation system. (author)

MUDANÇAS PALEO-HIDROLÓGICAS NA PLANÍCIE DO RIO PARAGUAI, QUATERNÁRIO DO PANTANAL

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Hudson de Azevedo Macedo

2014-04-01

Full Text Available O Paraguai é o rio-tronco do trato de sistemas deposicionais do Pantanal. Com base em dados de sensores remotos e verificação de campo, foi realizado mapeamento geomorfológico da planície do rio Paraguai no trecho entre as confluências dos rios Cuiabá e Miranda, onde foram reconhecidas formas deposicionais atuais e antigas. A análise das associações de formas permitiu estabelecer proposta de evolução geomorfológica para a área, mas os eventos carecem ainda de datação precisa por métodos geocronológicos. Uma rede de drenagem abandonada multicanais está parcialmente preservada na planície, sendo composta por formas de canais com diques marginais que evidenciam período de menor descarga fluvial, provavelmente do Pleistoceno tardio ao Holoceno inferior. Um sistema constituído por paleocinturões de meandros trunca a paleorrede de drenagem multicanais, registrando aumento na umidade e na descarga fluvial. Sob essas condições o rio Paraguai construiu um sistema composto por cinturões de meandros com direção aproximada norte-sul no Holoceno inferior/médio. Agradação dos cinturões favoreceu importante evento de avulsão, com a mudança do curso do rio Paraguai para o cinturão de meandros atual no Holoceno superior. As gerações de formas identificadas e mapeadas resultaram num padrão de sobreposição de diferentes estilos fluviais, que registram significativas mudanças hidrológicas na planície desde o Pleistoceno tardio.

Amino acids analysis by total neutron cross-sections determinations: part V

International Nuclear Information System (INIS)

Voi, Dante L.; Ferreira, Francisco de O.; Rocha, Helio F. da

2013-01-01

Total neutron cross-sections of twenty essential and non-essential amino acids to human were determined using crystal spectrometer installed on the Argonauta reactor of IEN (Instituto de Engenharia Nuclear (CNEN-RJ) and compared with data generated by parceling and grouping methodologies developed at this institution. For each amino acid was calculated the respective neutron cross-section by molecular structure, conformation and chemistry analysis. The results obtained for eighteen of twenty amino acids confirm the specifications and product formulations indicated by manufactures. These initial results allow to build a neutron cross-sections database as part of quality control of the amino supplied to hospitals for production of nutriments for parenteral or enteral formulations used in critical patients dependent on artificial feed, and for application in future studies of structure and dynamics for more complex molecules, including proteins, enzymes, fatty acids, membranes, organelles and other cell components. (author)

Detection of microorganisms in culture medium through the neutron radiographic technique; Deteccao de microorganismos em meios de cultura pela tecnica de neutrongrafia

Energy Technology Data Exchange (ETDEWEB)

Wacha, Reinaldo

1999-05-01

The study aims to obtain a more effective and faster method for the detection of bacteria in several culture media, such as potable water and blood. After the process growth in the culture medium, separation and suspension in buffer solution based in boron, the bacteria are deposited in track detectors that are submitted to thermal neutron beams (neutron flux: 2,2 x 10{sup 5} n.cm{sup -2}.s{sup -1}), resulting from the channel J-9 of the Argonauta research reactor, from the Nuclear Engineering Institute, IEN/CNEN. The latent tracks arisen from the alpha particles proceeding from the reaction B ({eta}, {alpha}) Li and, after having been revealed, are analyzed by an optical microscope that allows to detect the existence of the bacteria. Afterwards, they were analyzed in a nanoscope which helps the identification of the tracks of the alpha particles. (author)

Use of virtual reality to estimate radiation dose rates in nuclear plants

International Nuclear Information System (INIS)

Augusto, Silas C.; Mol, Antonio C.A.; Jorge, Carlos A.F.; Couto, Pedro M.

2007-01-01

Operators in nuclear plants receive radiation doses during several different operation procedures. A training program capable of simulating these operation scenarios will be useful in several ways, helping the planning of operational procedures so as to reduce the doses received by workers, and to minimize operations' times. It can provide safe virtual operation training, visualization of radiation dose rates, and estimation of doses received by workers. Thus, a virtual reality application, a free game engine, has been adapted to achieve the goals of this project. Simulation results for Argonauta research reactor of Instituto de Engenharia Nuclear are shown in this paper. A database of dose rate measurements, previously performed by the radiological protection service, has been used to display the dose rate distribution in the region of interest. The application enables the user to walk in the virtual scenario, displaying at all times the dose accumulated by the avatar. (author)

Reactor core for LMFBR type reactors

International Nuclear Information System (INIS)

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

1987-01-01

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

CARACTERIZAÇÃO GEOMORFOLÓGICA DA BACIA DO RIO TURVO-RJ: MÉDIO VALE DO RIO PARAÍBA DO SUL (MVPRS

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Rafael Albuquerque Xavier

2014-04-01

Full Text Available O mapeamento geomorfológico da bacia do rio Turvo confirmou as evidências apontadas em estudos anteriores, de que a bacia apresentava feições diferentes das observadas em bacias vizinhas. Foram observadas 222 depressões fechadas em divisores de drenagem, indicando forte atuação de mecanismos geoquímicos. Por outro lado, o reduzido número de voçorocas (33 e a presença de pacotes sedimentares poucos espessos (média de 7 metros, apontam a baixa efetividade dos processos mecânicos na bacia, sobretudo ao compararmos com a sub-bacia do rio Piracema, tributária do rio Bananal, com 117 voçorocas, terraços de até 23 metros de espessura e apenas 1 depressão fechada. Internamente, a bacia do rio Turvo apresentou variações, onde, de modo geral, a sub-bacia do rio das Pedras concentrou 21 das 33 voçorocas ativas, os mais espessos pacotes fluviais e apenas 16 depressões fechadas. Assim, conclui-se que a bacia do rio Turvo é fortemente influenciada pelos processos de denudação química, e a sub-bacia do rio das Pedras apresenta as maiores características da atuação do trabalho mecânico de toda a bacia.

Desempenho de reator anaeróbio-aeróbio de leito fixo no tratamento de esgoto sanitário Performance of anaerobic-aerobic packed-bed reactor in the treatment of domestic sewage

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Sérgio Brasil Abreu

2008-06-01

Full Text Available Este artigo relata a avaliação do desempenho de um reator anaeróbio-aeróbio, preenchido com espuma de poliuretano, para tratamento de esgoto sanitário. Inicialmente, foram testados diferentes tempos de detenção hidráulica (TDH no reator que operou apenas em condições anaeróbias. Em seguida, foi operado o reator combinado anaeróbio-aeróbio. O melhor resultado para o reator em operação exclusivamente anaeróbia foi para o TDH de 10 horas, no qual se conseguiu reduzir a DQO de 389 ± 70 mg/L para 137 ± 16 mg/L. Para o reator anaeróbio-aeróbio, a DQO foi reduzida de 259 ± 69 mg/L para 93 ± 31 mg/L para TDH de 12 h (6 h no estágio anaeróbio e 6 h no aeróbio. A comparação de todos os resultados obtidos evidenciou a importância do pós-tratamento aeróbio na remoção de parcela de matéria orgânica não removida em tratamento unicamente anaeróbio.This paper reports on the performance evaluation of an upflow anaerobic-aerobic reactor, filled with polyurethane matrices, for domestic sewage treatment. Initially, different hydraulic retention times were assayed with the reactor operating exclusively in anaerobic condition. Afterwards, anaerobic-aerobic combined reactor was operated. The anaerobic operation with HRT of 10 h provided the best organic matter removal with COD reduction from 389 ± 70 mg/L to 137 ± 16 mg/L. Under anaerobic-aerobic condition, the COD dropped from 259 ± 69 mg/L to 93 ± 31 mg/L with HRT of 12 h (6 h in anaerobic and 6 h in aerobic stages. Finally, comparing all the obtained results, it was possible to verify the importance of the aerobic post treatment in the removal of part of the organic matter not removed in an exclusively anaerobic treatment.

Record of Pleopis schmackeri (Poppe Branchiopoda in Rio das Ostras, Rio de Janeiro, Brazil

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Wanda Maria Monteiro-Ribas

2012-10-01

Full Text Available http://dx.doi.org/10.5007/2175-7925.2013v26n1p201 The paper describes the first occurrence of Pleopis schmackeri (Poppe, 1889 (Branchiopoda, Onychopoda in Rio das Ostras, Rio de Janeiro, Brazil is described. This marine cladoceran species occurred in zooplanktonic samples obtained on July, 2003 with mean density of 10 ind.m-3. Its presence may be related to two hypotheses, due to ballast water and through the Brazilian current, which gets closer to the coast Winter.

DEGRADAÇÃO AMBIENTAL DO RIO PAVUNA-MERITI

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Marcos Antonio Braga de Barros

2016-10-01

Full Text Available O Rio Pavuna-Meriti banha em seus últimos 7,4km o município de Duque de Caxias, que segundo dados de 2014 do Instituto Brasileiro de Geografia e Estatísticas (IBGE é a 15ª maior economia do Brasil. Duque de Caxias sofre constantemente com inundações por conta do assoreamento dos rios, além da falta d’água potável que causam grande prejuízo econômico, sociais e à saúde da população. Os problemas de assoreamento existentes neste rio são comuns em outros rios do Brasil, entre suas principais causas estão o lançamento de esgotos sem tratamento, ausência de coleta de lixo, sem falar dos aspectos indiretos como desmatamento de suas margens, ocupação da calha secundária do rio.

Estudo da geometria hidráulica do Rio dos Bugres, no município de Rio Negrinho - SC

OpenAIRE

Grison, Fernando

2013-01-01

Tese (doutorado) - Universidade Federal de Santa Catarina, Centro Tecnológico, Programa de Pós-Graduação em Engenharia Ambiental, Florianópolis, 2013. O presente trabalho aplicou a teoria da geometria hidráulica no rio dos Bugres, em várias seções e trechos desse rio. Foi feita uma comparação entre resultados da geometria hidráulica obtidos pelo método clássico proposto por Leopold com derivações analíticas propostas por Dingman. Foram definidos 11 pontos de estudo ao longo do rio dos Bugr...

Fatores associados ao atraso no desenvolvimento em crianças, Rio Grande, Rio Grande do Sul, Brasil Factores asociados con retraso en el desarrollo de los niños, Rio Grande, Rio Grande do Sul, Brasil Factors associated with delay in development in children, Rio Grande, Rio Grande do Sul, Brazil

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Aline Alves Veleda

2011-03-01

Full Text Available Estudo analítico com o objetivo de avaliar os fatores associados ao atraso no desenvolvimento em crianças entre 8 a 12 meses de idade indicadas como de risco ao nascer no município do Rio Grande, Rio Grande do Sul, Brasil. Foram utilizados como instrumentos o Teste de Triagem de Desenvolvimento de Denver II (TTDD II, a avaliação antropométrica e questionários estruturados. Participaram 220 crianças consideradas de risco ou não ao nascer. Foi encontrada uma prevalência de 20,5% de suspeita de atraso no desenvolvimento neuropsicomotor. As crianças que apresentaram risco de um TTDD II suspeito faziam parte de famílias de mais baixa renda; eram filhos de mães que haviam realizado menos de seis consultas de pré-natal e apresentavam índice peso-idade inadequado. Os dados sugerem a necessidade de um replanejamento das políticas de saúde infantil, visto que outros critérios poderiam ser incluídos nas condições de risco para a criança ao nascer.Estudio analítico con el objetivo de evaluar los factores asociados al atraso en el desarrollo en niños de 8 a 12 meses de edad indicados como riesgo al nacer en el municipio de Rio Grande, RS, Brasil. Fueron utilizadas como herramientas la Prueba de Tamizaje del Desarrollo de Denver II, la evaluación antropométrica y cuestionarios estructurados. Participaron 220 niños considerados de riesgo o no al nacer. Fue encontrada una prevalencia del 20,5% de sospecha de atraso en el desarrollo neuropsicomotor. Los niños que presentaron riesgo de un DDST II sospechoso formaban parte de familias de más baja renta; eran hijos de madres que habían realizado menos de seis consultas de prenatal y presentaban índice peso-edad inadecuado. Los datos sugieren la necesidad de un replanteamiento de las políticas de salud infantil, así como otros criterios podrían ser inclusos en las condiciones de riesgo para el niño al nacer.This analytical study aims to evaluate the factors associated to

Nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

This patent describes an improved liquid metal nuclear reactor construction comprising: (a) a nuclear reactor core having a bottom platform support structure; (b) a reactor vessel for holding a large pool of low pressure liquid metal coolant and housing the core; (c) a containment structure surrounding the reactor vessel and having a sidewall spaced outwardly from the reactor vessel side wall and having a base mat spaced below the reactor vessel bottom end wall; (d) a central small diameter post anchored to the containment structure base mat and extending upwardly to the reactor vessel to axially fix the bottom end wall of the reactor vessel and provide a center column support for the lower end of the reactor core; (e) annular support structure disposed in the reactor vessel on the bottom end wall and extending about the lower end of the core; (f) structural support means disposed between the containment structure base mat and bottom end of the reactor vessel wall and cooperating for supporting the reactor vessel at its bottom end wall on the containment structure base mat to allow the reactor vessel to expand radially but substantially prevent any lateral motions that might be imposed by the occurrence of a seismic event; (g) a bed of insulating material disposed between the containment structure base mat and the bottom end wall of the reactor vessel and uniformly supporting the reactor vessel at its bottom end wall; freely expand radially from the central post as it heats up while providing continuous support thereof; (h) a deck supported upon the wall of the containment vessel above the top open end of the reactor vessel; and (i) extendible and retractable coupling means extending between the deck and the top open end of the reactor vessel and flexibly and sealably interconnecting the reactor vessel at its top end to the deck

Maconha e contexto familiar: um estudo psicossocial entre universitários do Rio de Janeiro Marijuana and family context: a psychosocial study among university students of Rio de Janeiro

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Violeta Martins Ferreira

2007-04-01

Full Text Available O objetivo deste trabalho foi estudar o contexto familiar de usuários e não-usuários de maconha. Adotamos a teoria das representações sociais de Moscovici (1961/1976, 1988, além de algumas reflexões de Becker (1971 e Foucault (1977, 1994, 1997. Participaram da pesquisa sessenta universitários do Rio de Janeiro, de ambos os sexos, entre 17 e 30 anos. Utilizamos um questionário com perguntas abertas, no qual eles apresentaram seus familiares. O material obtido foi analisado em termos temáticos e estatísticos. Entre os usuários de maconha, prevaleceu a autoridade e a ênfase nos papéis sociais, sendo a interação familiar marcada pelo acento emocional e pela idealização. Entre os não-usuários a autoridade coexistiu com relações interpessoais de companheirismo e partilha, num contexto familiar em que predominaram não aspectos afetivos mas práticas de proteção e cuidados. Podemos afirmar que o papel da família na prevenção ao uso de drogas está associado à promoção da autonomia, diferenciação e garantia de um espaço próprio para o jovem.The objective of this paper was to study the family context among marijuana users and non-users. Moscovici's theory of social representations, as well as some considerations from Becker and Foucault, was used as theoretical basis for data analysis. The empirical research included sixty university students from Rio de Janeiro, 17-30 years old, of both sexes. Using a questionnaire with open questions, we requested participants to freely describe their family members. The answers were treated according to content analysis principles, followed by chi-square tests. The results presented significant differences between both groups. Among marijuana users, authority and emphasis of social roles predominated, family interactions being characterized by emotional emphasis and idealization. Among non-users, authority coexisted with interpersonal relations characterized by fellowship and sharing

Generation IV reactors: reactor concepts

International Nuclear Information System (INIS)

Cardonnier, J.L.; Dumaz, P.; Antoni, O.; Arnoux, P.; Bergeron, A.; Renault, C.; Rimpault, G.; Delpech, M.; Garnier, J.C.; Anzieu, P.; Francois, G.; Lecomte, M.

2003-01-01

Liquid metal reactor concept looks promising because of its hard neutron spectrum. Sodium reactors benefit a large feedback experience in Japan and in France. Lead reactors have serious assets concerning safety but they require a great effort in technological research to overcome the corrosion issue and they lack a leader country to develop this innovative technology. In molten salt reactor concept, salt is both the nuclear fuel and the coolant fluid. The high exit temperature of the primary salt (700 Celsius degrees) allows a high energy efficiency (44%). Furthermore molten salts have interesting specificities concerning the transmutation of actinides: they are almost insensitive to irradiation damage, some salts can dissolve large quantities of actinides and they are compatible with most reprocessing processes based on pyro-chemistry. Supercritical water reactor concept is based on operating temperature and pressure conditions that infers water to be beyond its critical point. In this range water gets some useful characteristics: - boiling crisis is no more possible because liquid and vapour phase can not coexist, - a high heat transfer coefficient due to the low thermal conductivity of supercritical water, and - a high global energy efficiency due to the high temperature of water. Gas-cooled fast reactors combining hard neutron spectrum and closed fuel cycle open the way to a high valorization of natural uranium while minimizing ultimate radioactive wastes and proliferation risks. Very high temperature gas-cooled reactor concept is developed in the prospect of producing hydrogen from no-fossil fuels in large scale. This use implies a reactor producing helium over 1000 Celsius degrees. (A.C.)

ICLEI submission for Rio+20. Contribution to the Zero Draft of the Rio+20 outcome document

Energy Technology Data Exchange (ETDEWEB)

NONE

2011-10-31

ICLEI is an association of over 1200 local government Members who are committed to sustainable development. This document is ICLEI's submission to the zero draft document being developed for RIO+20, the United Nations Conference on Sustainable Development, scheduled for June 2012 in Rio de Janeiro, Brazil. In the paper, ICLEI calls for a UN Decade of Sustainable Urbanization to raise awareness, create synergies and to share solutions and good practices.

Germanidade e banhos medicinais nos primórdios dos balneários no Rio Grande do Sul Germanism and medicinal bathing in the early days of health resorts in Rio Grande do Sul

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Sílvio Marcus de Souza Correa

2010-03-01

Full Text Available Nos primórdios dos balneários no Rio Grande do Sul, encontravam-se alguns imigrantes alemães, não apenas entre os banhistas, mas também entre os empresários do incipiente ramo do curismo-turismo. Era um grupo pequeno de imigrantes de origem urbana que, em geral, já conhecia as vantagens curativas ou revigorantes dos banhos em balneários europeus. Entre eles destacavam-se os médicos, importantes emissores de um discurso científico em prol dos balneários. As práticas terapêuticas de banhos de mar chegaram ao Brasil meridional pela imigração européia da segunda metade do século XIX, embora sua difusão só tenha ocorrido na primeira metade do século seguinte, quando se desenvolveram as primeiras praias balneárias no Rio Grande do Sul.In the early days of bathing resorts some German immigrants were found not only among the bathers, but also among the entrepreneurs of the incipient branch of 'curism-tourism'. It was a small group of immigrants of urban origin who, in general, already knew the curative or reinvigorating advantages of the baths in European bathing resorts. Among them, doctors were prominent, important emissaries of a scientific discourse in favor of bathing resorts. The therapeutic practices of bathing in the sea arrived to meridional Brazil with the European immigration of the second half of the nineteenth century, although its diffusion only took place in the first half of the following century, when the first bathing beaches in Rio Grande do Sul were developed.

Imaginary Documentary: reflecting upon contemporary documental photography Documentário Imaginário: reflexões sobre a fotografia documental contemporânea

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Kátia Hallak Lombardi

2008-01-01

Full Text Available This article pursues the idea of an Imaginary Documentary – a possible new inflexion on the practices of contemporary documental photography. The text establishes its theoretical foundations through a forthcoming approach of the discussions about documental photography to the concept of imaginary, by Gilbert Durand, and the notion of Imaginary Museum, by André Malraux. Photographers that are part of documental photography history are the elected objects in which we shall confront the potentialities of the Imaginary Documentary. Este artigo tem como propósito buscar a estruturação da idéia de Documentário Imaginário – uma possível inflexão na prática da fotografia documental contemporânea. O texto assenta suas bases teóricas por meio da aproximação de reflexões sobre a fotografia documental ao conceito de imaginário em Gilbert Durand e à noção de Museu Imaginário de André Malraux. Fotógrafos que fazem parte da história da fotografia documental são os objetos eleitos para aferir as potencialidades do Documentário Imaginário.

Micetomas actinomicóticos no Rio Grande do Sul: relato de quatro casos Actinomycotic mycetomas in Rio Grande do Sul: report of 4 cases

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Alberto T. Londero

1986-03-01

Full Text Available São relatados quatro casos de micetoma causados por Nocardia brasiliensis, ocorridos no Rio Grande do Sul. É revista a literatura rio-grandense-do-sul.Four cases of mycetoma caused by N. brasiliensis, occurring in Rio Grande do Sul (Brazil, are reported.

Nuclear reactor

International Nuclear Information System (INIS)

Hattori, Sadao; Sato, Morihiko.

1994-01-01

Liquid metals such as liquid metal sodium are filled in a reactor container as primary coolants. A plurality of reactor core containers are disposed in a row in the circumferential direction along with the inner circumferential wall of the reactor container. One or a plurality of intermediate coolers are disposed at the inside of an annular row of the reactor core containers. A reactor core constituted with fuel rods and control rods (module reactor core) is contained at the inside of each of the reactor core containers. Each of the intermediate coolers comprises a cylindrical intermediate cooling vessels. The intermediate cooling vessel comprises an intermediate heat exchanger for heat exchange of primary coolants and secondary coolants and recycling pumps for compulsorily recycling primary coolants at the inside thereof. Since a plurality of reactor core containers are thus assembled, a great reactor power can be attained. Further, the module reactor core contained in one reactor core vessel may be small sized, to facilitate the control for the reactor core operation. (I.N.)

The CAREM reactor and present currents in reactor design

International Nuclear Information System (INIS)

Ordonez, J.P.

1990-01-01

INVAP has been working on the CAREM project since 1983. It concerns a very low power reactor for electrical energy generation. The design of the reactor and the basic criteria used were described in 1984. Since then, a series of designs have been presented for reactors which are similar to CAREM regarding the solutions presented to reduce the chance of major nuclear accidents. These designs have been grouped under different names: Advanced Reactors, Second Generation Reactors, Inherently Safe Reactors, or even, Revolutionary Reactors. Every reactor fabrication firm has, at least, one project which can be placed in this category. Presently, there are two main currents of Reactor Design; Evolutionary and Revolutionary. The present work discusses characteristics of these two types of reactors, some revolutionary designs and common criteria to both types. After, these criteria are compared with CAREM reactor design. (Author) [es

Materialidade e memória do Rio de Janeiro nas fotografias de Augusto Malta e do projeto Rio 365

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Débora Gauziski

2013-12-01

Full Text Available Neste artigo investigamos a relação da fotografia com a produção e difusão de imagens da cidade do Rio de Janeiro em dois momentos distintos: durante a modernização de Pereira Passos (início do século XX e no Rio dos megaeventos (século XXI. Em ambos os períodos históricos, a cidade sofreu profundas transformações urbanísticas e a fotografia atua como importante agente nesse processo. Para analisar o papel que a fotografia tem nesse contexto, trabalhamos com as imagens clicadas pelo fotógrafo Augusto Malta e com aquelas produzidas por usuários do Instagram no contexto do projeto Rio 365. Ao longo do artigo, nossa base teórica concentra-se em autores que trabalham ou tangenciam as questões da memória e da materialidade.

A violência do Rio às portas da emergência Violence in Rio as seen from the emergency ward

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Paulo Pinheiro

1994-01-01

Full Text Available Este trabalho trata de revelar o aumento dos danos físicos e lesões corporais que chegam a um hospital de emergência da Rede Municipal de Saúde do Rio de Janeiro. Como Diretor deste serviço, ao mesmo tempo que constato a mudança progressiva no perfil de atendimento do hospital, comparo-o com o crescimento da onda de criminalidade que envolveu a vida social do Rio de Janeiro.This study is intended to demonstrate the increase in bodily injuries that are currently being observed in a public hospital in Rio de Janeiro. As director of an emergency ward, I have observed a steady change in the type of hospital care provided, a phenonmenon which I ascribe to the increase in criminality engulfing the community of Rio de Janeiro.

MAGISTÉRIO E CONSCIÊNCIA

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Bernard Sesboüé

2012-01-01

Full Text Available Este artigo propõe uma breve reflexão sobre a relação histórica e atual entre o exercício do magistério e o necessário respeito da consciência dos crentes. Uma primeira parte retoma a evolução da consciência a partir dos tempos modernos e de suas consequências : uma nova figura da fé e da vida no seio da comunidade cristã. Uma segunda parte recapitula as diferentes formas de exercício do magistério eclesial no curso da história e as dificuldades postas por seu encontro com a modernidade. O autor apresenta então um sonho, propondo uma nova maneira de proceder: não mais a simples vigilância, mas a animação de um grande debate planetário sobre todas as dificuldades postas ao ato de crer, a fim de revivificar o sensus fidei do povo cristão. A terceira parte retoma o problema da verdade na qual magistério e consciência moderna devem encontrar um consenso autêntico. ABSTRACT: This article proposes a brief reflection on the historical and current relationship between the exercise of the Magisterium and the need to respect the conscience of believers. A first part follows the evolution of conscience from modern times and its consequences: a new figure of faith and of life within the Christian community. A second part recapitulates the different forms of exercise of the ecclesial Magisterium in the course of history and the difficulties posed by its encounter with modernity. The author proposes a dream by proposing a new way to proceed: no longer simply surveillance, but the animation of a large planetary debate about all difficulties made the act of believing, in order to give new life to the sensus fidei of Christian people. The third part takes up the problem of truth in which teaching and modern conscience must find a genuine consensus.

As Câmaras Municipais no Império Português: o exemplo do Rio de Janeiro

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Maria Fernanda Bicalho

1998-01-01

Full Text Available O presente artigo visa analisar o papel representado pelas Câmaras Municipais Ultrama-rinas no interior do Império Colonial Português. Ele centra sua análise sobre a Câmara do Rio de Janeiro ao longo dos séculos XVII e XVIII, no sentido de ilustrar a composição das municipalidades, suas funções rotineiras, sua ação nos tempos de crise e de guerra, e o tipo de suas demandas dirigidas aos representantes da Coroa nos dois lados do Atlântico. Enquanto centro político-administrativo, de imposição de tributos, de comércio e defesa, o Rio de Janeiro se tornou locus privilegiado do exercício do domínio metropolitano sobre a vasta região do Atlântico-Sul. Este artigo pretende discutir as tensões, negociações e compro-missos entre a política metropo-litana e o papel de uma das mais importantes municipalidades no mundo luso-americano.The present article analises the role played by the overseas municipal councils in Portuguese Colonial Empire. It focus the Municipal Council of Rio de Janeiro during the seventeenth and eighteenth centuries, in order to illustrate the composition of the municipalities, their routine functions, their action in times of crisis and war, and the kind of it's demands to the Crown representatives on both sides of the Atlantic. As the center of political administration, tax collection, commerce, and defense, Rio de Janeiro was the privileged stage for the exercise of metropolian dominance over the vast South-Atlantic world. This article intends to discuss the tensions, negociations, and compromises between metropolitan politics and the role of one of the most important luso-american municipalities.

Neutron behavior, reactor control, and reactor heat transfer. Volume four

International Nuclear Information System (INIS)

Anon.

1986-01-01

Volume four covers neutron behavior (neutron absorption, how big are nuclei, neutron slowing down, neutron losses, the self-sustaining reactor), reactor control (what is controlled in a reactor, controlling neutron population, is it easy to control a reactor, range of reactor control, what happens when the fuel burns up, controlling a PWR, controlling a BWR, inherent safety of reactors), and reactor heat transfer (heat generation in a nuclear reactor, how is heat removed from a reactor core, heat transfer rate, heat transfer properties of the reactor coolant)

Laboratório químico-prático do Rio de Janeiro: primeira tentativa de difusão da Química no Brasil (1812- 1819) "Laboratório químico-prático do Rio de Janeiro": the first attempt at establishing the science of Chemistry in Brazil (1812- 1819)

OpenAIRE

Nadja Paraense dos Santos

2004-01-01

Until the present date, historians of science have described inaccurately the first laboratory created in Brazil for establishing and divulging Chemistry, namely the "Laboratório Químico-Prático do Rio de Janeiro". During recent research carried out in the Arquivo do Museu Imperial (Petrópolis, RJ), I localized a document entitled "Ensaio histórico analítico das operações do Laboratório Químico-Prático do Rio de Janeiro", which allowed me to gain the relevant information to correct some of th...

Stereographic images acquired with gamma rays and thermal neutron radiography

International Nuclear Information System (INIS)

Souza, Maria Ines Silvani; Almeida, Gevaldo L. de; Furieri, Rosanne C.; Lopes, Ricardo T.

2011-01-01

Full text: The inner structure of an object, which should not be submitted to an invasive assay, can only be perceived by using a suitable technique in order to render it transparent. A widely employed technique for this purpose involves the using of a radiation capable to pass through the object, collecting the transmitted radiation by a proper device, which furnishes a radiographic attenuation map of the object. This map, however, does not display the spatial distribution of the inner components of the object, but a convoluted view for each specific attitude of the object with regard to the set beam-detector. A 3D tomographic approach would show that distribution but it would demand a large number of projections requiring special equipment and software, not always available or affordable. In some circumstances however, a 3D tomography can be replaced by a stereographic view of the object under inspection, as done in this work, where instead of tens of radiographic projections, only two of them taken at suitable object attitudes are employed. Once acquired, these projections are properly processed and observed through a red and green eyeglass. For monochromatic images, this methodology requires the transformation of the black and white radiographs into red and white and green and white ones, which are afterwards merged to yield a single image. All the process is carried out with the software Image J . In this work, the Argonauta reactor at the Instituto de Engenharia Nuclear in Rio de Janeiro has been used as a source of thermal neutrons to acquire the neutron radiographic images, as well as to produce 198 Au sources employed in the acquisition of gamma-ray radiographic ones. X-ray or neutron-sensitive imaging plates have been used as detector, which after exposure were developed by a reader using a 0.5μm-diameter laser beam. (author)

Reactor science and technology: operation and control of reactors

International Nuclear Information System (INIS)

Qiu Junlong

1994-01-01

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

Nuclear power reactors

International Nuclear Information System (INIS)

1982-11-01

After an introduction and general explanation of nuclear power the following reactor types are described: magnox thermal reactor; advanced gas-cooled reactor (AGR); pressurised water reactor (PWR); fast reactors (sodium cooled); boiling water reactor (BWR); CANDU thermal reactor; steam generating heavy water reactor (SGHWR); high temperature reactor (HTR); Leningrad (RMBK) type water-cooled graphite moderated reactor. (U.K.)

Research reactors

International Nuclear Information System (INIS)

Merchie, Francois

2015-10-01

This article proposes an overview of research reactors, i.e. nuclear reactors of less than 100 MW. Generally, these reactors are used as neutron generators for basic research in matter sciences and for technological research as a support to power reactors. The author proposes an overview of the general design of research reactors in terms of core size, of number of fissions, of neutron flow, of neutron space distribution. He outlines that this design is a compromise between a compact enough core, a sufficient experiment volume, and high enough power densities without affecting neutron performance or its experimental use. The author evokes the safety framework (same regulations as for power reactors, more constraining measures after Fukushima, international bodies). He presents the main characteristics and operation of the two families which represent almost all research reactors; firstly, heavy water reactors (photos, drawings and figures illustrate different examples); and secondly light water moderated and cooled reactors with a distinction between open core pool reactors like Melusine and Triton, pool reactors with containment, experimental fast breeder reactors (Rapsodie, the Russian BOR 60, the Chinese CEFR). The author describes the main uses of research reactors: basic research, applied and technological research, safety tests, production of radio-isotopes for medicine and industry, analysis of elements present under the form of traces at very low concentrations, non destructive testing, doping of silicon mono-crystalline ingots. The author then discusses the relationship between research reactors and non proliferation, and finally evokes perspectives (decrease of the number of research reactors in the world, the Jules Horowitz project)

Roles of plasma neutron source reactor in development of fusion reactor engineering: Comparison with fission reactor engineering

International Nuclear Information System (INIS)

Hirayama, Shoichi; Kawabe, Takaya

1995-01-01

The history of development of fusion power reactor has come to a turning point, where the main research target is now shifting from the plasma heating and confinement physics toward the burning plasma physics and reactor engineering. Although the development of fusion reactor system is the first time for human beings, engineers have experience of development of fission power reactor. The common feature between them is that both are plants used for the generation of nuclear reactions for the production of energy, nucleon, and radiation on an industrial scale. By studying the history of the development of the fission reactor, one can find the existence of experimental neutron reactors including irradiation facilities for fission reactor materials. These research neutron reactors played very important roles in the development of fission power reactors. When one considers the strategy of development of fusion power reactors from the points of fusion reactor engineering, one finds that the fusion neutron source corresponds to the neutron reactor in fission reactor development. In this paper, the authors discuss the roles of the plasma-based neutron source reactors in the development of fusion reactor engineering, by comparing it with the neutron reactors in the history of fission power development, and make proposals for the strategy of the fusion reactor development. 21 refs., 6 figs

Reactor physics aspects of CANDU reactors

International Nuclear Information System (INIS)

Critoph, E.

1980-01-01

These four lectures are being given at the Winter Course on Nuclear Physics at Trieste during 1978 February. They constitute part of the third week's lectures in Part II: Reactor Theory and Power Reactors. A physical description of CANDU reactors is given, followed by an overview of CANDU characteristics and some of the design options. Basic lattice physics is discussed in terms of zero energy lattice experiments, irradiation effects and analytical methods. Start-up and commissioning experiments in CANDU reactors are reviewed, and some of the more interesting aspects of operation discussed - fuel management, flux mapping and control of the power distribution. Finally, some of the characteristics of advanced fuel cycles that have been proposed for CANDU reactors are summarized. (author)

Research reactors

International Nuclear Information System (INIS)

Kowarski, L.

1955-01-01

It brings together the techniques data which are involved in the discussion about the utility for a research institute to acquire an atomic reactor for research purposes. This type of decision are often taken by non-specialist people who can need a brief presentation of a research reactor and its possibilities in term of research before asking advises to experts. In a first part, it draws up a list of the different research programs which can be studied by getting a research reactor. First of all is the reactor behaviour and kinetics studies (reproducibility factor, exploration of neutron density, effect of reactor structure, effect of material irradiation...). Physical studies includes study of the behaviour of the control system, studies of neutron resonance phenomena and study of the fission process for example. Chemical studies involves the study of manipulation and control of hot material, characterisation of nuclear species produced in the reactor and chemical effects of irradiation on chemical properties and reactions. Biology and medicine research involves studies of irradiation on man and animals, genetics research, food or medical tools sterilization and neutron beams effect on tumour for example. A large number of other subjects can be studied in a reactor research as reactor construction material research, fabrication of radioactive sources for radiographic techniques or applied research as in agriculture or electronic. The second part discussed the technological considerations when choosing the reactor type. The technological factors, which are considered for its choice, are the power of the reactor, the nature of the fuel which is used, the type of moderator (water, heavy water, graphite or BeO) and the reflector, the type of coolants, the protection shield and the control systems. In the third part, it described the characteristics (place of installation, type of combustible and comments) and performance (power, neutron flux ) of already existing

Comparison between TRU burning reactors and commercial fast reactor

International Nuclear Information System (INIS)

Fujimura, Koji; Sanda, Toshio; Ogawa, Takashi

2001-03-01

Research and development for stabilizing or shortening the radioactive wastes including in spent nuclear fuel are widely conducted in view point of reducing the environmental impact. Especially it is effective way to irradiate and transmute long-lived TRU by fast reactors. Two types of loading way were previously proposed. The former is loading relatively small amount of TRU in all commercial fast reactors and the latter is loading large amount of TRU in a few TRU burning reactors. This study has been intended to contribute to the feasibility studies on commercialized fast reactor cycle system. The transmutation and nuclear characteristics of TRU burning reactors were evaluated and compared with those of conventional transmutation system using commercial type fast reactor based upon the investigation of technical information about TRU burning reactors. Major results are summarized as follows. (1) Investigation of technical information about TRU burning reactors. Based on published reports and papers, technical information about TRU burning reactor concepts transmutation system using convectional commercial type fast reactors were investigated. Transmutation and nuclear characteristics or R and D issue were investigated based on these results. Homogeneously loading of about 5 wt% MAs on core fuels in the conventional commercial type fast reactor may not cause significant impact on the nuclear core characteristics. Transmutation of MAs being produced in about five fast reactors generating the same output is feasible. The helium cooled MA burning fast reactor core concept propose by JAERI attains criticality using particle type nitride fuels which contain more than 60 wt% MA. This reactor could transmute MAs being produced in more than ten 1000 MWe-LWRs. Ultra-long life core concepts attaining more than 30 years operation without refueling by utilizing MA's nuclear characteristics as burnable absorber and fertile nuclides were proposed. Those were pointed out that

Nuclear reactor types

International Nuclear Information System (INIS)

Jones, P.M.S.

1987-01-01

The characteristics of different reactor types designed to exploit controlled fission reactions are explained. Reactors vary from low power research devices to high power devices especially designed to produce heat, either for direct use or to produce steam to drive turbines to generate electricity or propel ships. A general outline of basic reactors (thermal and fast) is given and then the different designs considered. The first are gas cooled, including the Magnox reactors (a list of UK Magnox stations and reactor performance is given), advanced gas cooled reactors (a list of UK AGRs is given) and the high temperature reactor. Light water cooled reactors (pressurized water [PWR] and boiling water [BWR] reactors) are considered next. Heavy water reactors are explained and listed. The pressurized heavy water reactors (including CANDU type reactors), boiling light water, steam generating heavy water reactors and gas cooled heavy water reactors all come into this category. Fast reactors (liquid metal fast breeder reactors and gas cooled fast reactors) and then water-cooled graphite-moderated reactors (RBMK) (the type at Chernobyl-4) are discussed. (U.K.)

Archaeozoology of marine mollusks from Sambaqui da Tarioba, Rio das Ostras, Rio de Janeiro, Brazil

Directory of Open Access Journals (Sweden)

Rosa C. C. L. de Souza

2010-06-01

Full Text Available A reference inventory of prehistoric marine mollusks from the Rio das Ostras region was created based on an excavation carried out at the Sambaqui da Tarioba shellmound. Patterns of richness and biogeography were studied, and the representativeness of bivalve and gastropod diversities found at this archaeological site were inferred. A total of 47 taxa belonging to 28 families, most of which from unconsolidated substrates, was identified. The shellmound species composition does not differ from the present-day composition. All recorded species are characteristic of a wide transition zone between the south of the states of Espírito Santo (21°S and Rio Grande do Sul (32°S. Thus, the data show little evidence of evolution in the composition, richness,and biodiversity distribution patterns of mollusks in the Rio das Ostras region. Likewise, a reconstitution of the paleoenvironment from the functional characteristics of the shellmound species indicates that the locality's geomorphology and climate remained largely unchanged in the last 4,000 years BP.

Reactor containment and reactor safety in the United States

International Nuclear Information System (INIS)

Kouts, H.

1986-01-01

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

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2002-01-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2001-04-01

The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised.

Reactor Physics

International Nuclear Information System (INIS)

Ait Abderrahim, A.

2001-01-01

The Reactor Physics and MYRRHA Department of SCK-CEN offers expertise in various areas of reactor physics, in particular in neutronics calculations, reactor dosimetry, reactor operation, reactor safety and control and non-destructive analysis of reactor fuel. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2000 are summarised

Thermoluminescence dating of Rio Claro and Piracununga formations

International Nuclear Information System (INIS)

Ferreira, Sandra Regina; Chang, Maria Rita Caetano

2008-01-01

The Rio Claro and Piracununga formations cover extensive areas of the Paulista Peripheral Depression, dominantly in the region of Rio Claro and Piracununga cities. These units lie over the Corumbatai and Piramboia formations, exhibiting discordant contacts. The Rio Claro and Piracununga formations are composed of fine to medium sand facies, showing local cross-stratifications and parallel beddings with thin interbeddings of mud and gravel. These sands were dated by the Thermoluminescence Method, which indicated they were from the Pleistocene age. The oldest age (745,000 years BP) was found in deposits of the Rio Claro Formation; the other ages varied from 400,000 years BP to 145,000 years BP, for both formations. The youngest age (15,000 years BP - close to Pleistocene/ Holocene limit) was found in colluvial deposits, which rest on the Piracununga Formation. (author)

Desgaste ondulatório em caminhos de ferro

OpenAIRE

Martins, Paulo Manuel Caldeira

2010-01-01

Trata-se de uma análise técnica completa a um desgaste específico que aparece frequentemente nos sistemas ferroviários, sejam eles comboios (passageiros, carga e alta velocidade), Metropolitanos (ligeiros e pesados) ou mesmo sistemas de carros eléctricos. Anualmente são gastos pelos sistemas ferroviários, consideráveis somas na correcção dos defeitos provocados pelo aparecimento do desgaste ondulatório nos carris de rolamento. Ainda hoje a relativa pouca troca de conhecimentos entre os ...

Reactor

International Nuclear Information System (INIS)

Toyama, Masahiro; Kasai, Shigeo.

1978-01-01

Purpose: To provide a lmfbr type reactor wherein effusion of coolants through a loop contact portion is reduced even when fuel assemblies float up, and misloading of reactor core constituting elements is prevented thereby improving the reactor safety. Constitution: The reactor core constituents are secured in the reactor by utilizing the differential pressure between the high-pressure cooling chamber and low-pressure cooling chamber. A resistance port is formed at the upper part of a connecting pipe, and which is connect the low-pressure cooling chamber and the lower surface of the reactor core constituent. This resistance part is formed such that the internal sectional area of the connecting pipe is made larger stepwise toward the upper part, and the cylinder is formed larger so that it profiles the inner surface of the connecting pipe. (Aizawa, K.)

Reactor Physics

Energy Technology Data Exchange (ETDEWEB)

Ait Abderrahim, A

2002-04-01

SCK-CEN's Reactor Physics and MYRRHA Department offers expertise in various areas of reactor physics, in particular in neutron and gamma calculations, reactor dosimetry, reactor operation and control, reactor code benchmarking and reactor safety calculations. This expertise is applied in the Department's own research projects in the VENUS critical facility, in the BR1 reactor and in the MYRRHA project (this project aims at designing a prototype Accelerator Driven System). Available expertise is also used in programmes external to the Department such as the reactor pressure steel vessel programme, the BR2 materials testing reactor dosimetry, and the preparation and interpretation of irradiation experiments by means of neutron and gamma calculations. The activities of the Fuzzy Logic and Intelligent Technologies in Nuclear Science programme cover several domains outside the department. Progress and achievements in these topical areas in 2001 are summarised.

Research reactor standards and their impact on the TRIGA reactor community

International Nuclear Information System (INIS)

Richards, W.J.

1980-01-01

The American Nuclear Society has established a standards committee devoted to writing standards for research reactors. This committee was formed in 1971 and has since that time written over 15 standards that cover all aspects of research reactor operation. The committee has representation from virtually every group concerned with research reactors and their operation. This organization includes University reactors, National laboratory reactors, Nuclear Regulatory commission, Department of Energy and private nuclear companies and insurers. Since its beginning the committee has developed standards in the following areas: Standard for the development of technical specifications for research reactors; Quality control for plate-type uranium-aluminium fuel elements; Records and reports for research reactors; Selection and training of personnel for research reactors; Review of experiments for research reactors; Research reactor site evaluation; Quality assurance program requirements for research reactors; Decommissioning of research reactors; Radiological control at research reactor facilities; Design objectives for and monitoring of systems controlling research reactor effluents; Physical security for research reactor facilities; Criteria for the reactor safety systems of research reactors; Emergency planning for research reactors; Fire protection program requirements for research reactors; Standard for administrative controls for research reactors. Besides writing the above standards, the committee is very active in using communications with the nuclear regulatory commission on proposed rules or positions which will affect the research reactor community

Reactor operation

CERN Document Server

Shaw, J

2013-01-01

Reactor Operation covers the theoretical aspects and design information of nuclear reactors. This book is composed of nine chapters that also consider their control, calibration, and experimentation.The opening chapters present the general problems of reactor operation and the principles of reactor control and operation. The succeeding chapters deal with the instrumentation, start-up, pre-commissioning, and physical experiments of nuclear reactors. The remaining chapters are devoted to the control rod calibrations and temperature coefficient measurements in the reactor. These chapters also exp

Improved nuclear reactor construction with bottom supported reactor vessel

International Nuclear Information System (INIS)

Sharbaugh, J.E.

1987-01-01

An improved liquid metal nuclear reactor construction has a reactor core and a generally cylindrical reactor vessel for holding liquid metal coolant and housing the core within the pool. A generally cylindrical concrete containment structure surrounds the reactor vessel and a central support pedestal is anchored to the containment structure base mat and supports the bottom wall of the reactor vessel and the reactor core. The periphery of the reactor vessel bore is supported by an annular structure which allows thermal expansion but not seismic motion of the vessel, and a bed of thermally insulating material uniformly supports the vessel base whilst allowing expansion thereof. A guard ring prevents lateral seismic motion of the upper end of the reactor vessel. The periphery of the core is supported by an annular structure supported by the vessel base and keyed to the vessel wall so as to be able to expand but not undergo seismic motion. A deck is supported on the containment structure above the reactor vessel open top by annular bellows, the deck carrying the reactor control rods such that heating of the reactor vessel results in upward expansion against the control rods. (author)

Reactor as furnace and reactor as lamp

International Nuclear Information System (INIS)

Goldanskii, V.I.

1992-01-01

There are presented general characteristics of the following ways of transforming of nuclear energy released in reactors into chemical : ordinary way (i.e. trough the heat, mechanical energy and electricity); chemonuclear synthesis ; use of high-temperature fuel elements (reactor as furnace); use of the mixed nγ-radiation of reactors; use of the radiation loops; radiation - photochemical synthesis (reactor as lamp). Advantage and disadvantages of all above variants are compared. The yield of the primary product of fixation of nitrogen (nitric oxide NO) in reactor with the high-temperature (above ca. 1900degC) fuel elements (reactor-furnace) can exceed W ∼ 200 kg per gram of burned uranium. For the latter variant (reactor-lamp) the yield of chemical products can reach W ∼ 60 kg. per gram of uranium. Such values of W are close to or even strongly exceed the yields of chemical products for other abovementioned variants and - what is particularly important - are not connected to the necessity of archscrupulous removal of radioactive contamination of products. (author)

Development of Reactor Console Simulator for PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Mohd Idris Taib; Izhar Abu Hussin; Mohd Khairulezwan Abdul Manan; Nufarhana Ayuni Joha; Mohd Sabri Minhat

2012-01-01

The Reactor Console Simulator will be an interactive tool for operator training and teaching of PUSPATI TRIGA Reactor. Behaviour and characteristic for reactor console and reactor itself can be evaluated and understand. This Simulator will be used as complement for actual present reactor console. Implementation of man-machine interface is using computer screens, keyboard and mouse. Multiple screens are used to match the physical of present reactor console. LabVIEW software are using for user interface and mathematical calculation. Polynomial equation based on control rods calibration data as well as operation parameters record was used to calculate the estimated reactor console parameters. (author)

Reactor safeguards

CERN Document Server

Russell, Charles R

1962-01-01

Reactor Safeguards provides information for all who are interested in the subject of reactor safeguards. Much of the material is descriptive although some sections are written for the engineer or physicist directly concerned with hazards analysis or site selection problems. The book opens with an introductory chapter on radiation hazards, the construction of nuclear reactors, safety issues, and the operation of nuclear reactors. This is followed by separate chapters that discuss radioactive materials, reactor kinetics, control and safety systems, containment, safety features for water reactor

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

International Nuclear Information System (INIS)

Greneche, D.

2014-01-01

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

Control of reactor coolant flow path during reactor decay heat removal

International Nuclear Information System (INIS)

Hunsbedt, A.N.

1988-01-01

This patent describes a sodium cooled reactor of the type having a reactor hot pool, a slightly lower pressure reactor cold pool and a reactor vessel liner defining a reactor vessel liner flow gap separating the hot pool and the cold pool along the reactor vessel sidewalls and wherein the normal sodium circuit in the reactor includes main sodium reactor coolant pumps having a suction on the lower pressure sodium cold pool and an outlet to a reactor core; the reactor core for heating the sodium and discharging the sodium to the reactor hot pool; a heat exchanger for receiving sodium from the hot pool, and removing heat from the sodium and discharging the sodium to the lower pressure cold pool; the improvement across the reactor vessel liner comprising: a jet pump having a venturi installed across the reactor vessel liner, the jet pump having a lower inlet from the reactor vessel cold pool across the reactor vessel liner and an upper outlet to the reactor vessel hot pool

The research reactors their contribution to the reactors physics

International Nuclear Information System (INIS)

Barral, J.C.; Zaetta, A.; Johner, J.; Mathoniere, G.

2000-01-01

The 19 october 2000, the french society of nuclear energy organized a day on the research reactors. This associated report of the technical session, reactors physics, is presented in two parts. The first part deals with the annual meeting and groups general papers on the pressurized water reactors, the fast neutrons reactors and the fusion reactors industry. The second part presents more technical papers about the research programs, critical models, irradiation reactors (OSIRIS and Jules Horowitz) and computing tools. (A.L.B.)

Reactor noise analysis of experimental fast reactor 'JOYO'

International Nuclear Information System (INIS)

Ohtani, Hideji; Yamamoto, Hisashi

1980-01-01

As a part of dynamics tests in experimental fast reactor ''JOYO'', reactor noise tests were carried out. The reactor noise analysis techniques are effective for study of plant characteristics by determining fluctuations of process signals (neutron signal, reactor inlet temperature signals, etc.), which are able to be measured without disturbances for reactor operations. The aims of reactor noise tests were to confirm that no unstable phenomenon exists in ''JOYO'' and to gain initial data of the plant for reference of the future data. Data for the reactor noise tests treated in this paper were obtained at 50 MW power level. Fluctuations of process signals were amplified and recorded on analogue tapes. The analysis was performed using noise code (NOISA) of digital computer, with which statistical values of ASPD (auto power spectral density), CPSD (cross power spectral density), and CF (coherence function) were calculated. The primary points of the results are as follows. 1. RMS value of neutron signal at 50 MW power level is about 0.03 MW. This neutron fluctuation is not disturbing reactor operations. 2. The fluctuations of A loop reactor inlet temperatures (T sub(AI)) are larger than the fluctuations of B loop reactor inlet temperature (T sub(BI)). For this reason, the major driving force of neutron fluctuations seems to be the fluctuations of T sub(AI). 3. Core and blanket subassemblies can be divided into two halves (A and B region), with respect to the spacial motion of temperature in the reactor core. A or B region means the region in which sodium temperature fluctuations in subassembly are significantly affected by T sub(AI) or T sub(BI), respectively. This phenomenon seems to be due to the lack of mixing of A and B loop sodium in lower plenum of reactor vessel. (author)

A paisagem de rios urbanos

OpenAIRE

Porath, Soraia Loechelt

2004-01-01

Dissertação (mestrado) - Universidade Federal de Santa Catarina, Centro Tecnológico. Programa de Pós-Graduação em Arquitetura e Urbanismo Os rios têm sido uma presença constante na formação e crescimento das cidades. Desde os primórdios das civilizações, por uma questão de sobrevivência e utilidade, servem como fonte de recursos e meio de circulação. Porém, os rios urbanos são mal compreendidos. São entendidos como um limite ao crescimento das cidades, um obstáculo a ser transposto, e dest...

Reactor physics and reactor computations

International Nuclear Information System (INIS)

Ronen, Y.; Elias, E.

1994-01-01

Mathematical methods and computer calculations for nuclear and thermonuclear reactor kinetics, reactor physics, neutron transport theory, core lattice parameters, waste treatment by transmutation, breeding, nuclear and thermonuclear fuels are the main interests of the conference

Reactor water spontaneous circulation structure in reactor pressure vessel

International Nuclear Information System (INIS)

Takahashi, Kazumi

1998-01-01

The gap between the inner wall of a reactor pressure vessel of a BWR type reactor and a reactor core shroud forms a down comer in which reactor water flows downwardly. A feedwater jacket to which feedwater at low temperature is supplied is disposed at the outer circumference of the pressure vessel just below a gas/water separator. The reactor water at the outer circumferential portion just below the air/water separator is cooled by the feedwater jacket, and the feedwater after cooling is supplied to the feedwater entrance disposed below the feedwater jacket by way of a feedwater introduction line to supply the feedwater to the lower portion of the down comer. This can cool the reactor water in the down comer to increase the reactor water density in the down comer thereby forming strong downward flows and promote the recycling of the reactor water as a whole. With such procedures, the reactor water can be recycled stably only by the difference of the specific gravity of the reactor water without using an internal pump. In addition, the increase of the height of the pressure vessel can be suppressed. (I.N.)

Reactor

International Nuclear Information System (INIS)

Ikeda, Masaomi; Kashimura, Kazuo; Inoue, Kazuyuki; Nishioka, Kazuya.

1979-01-01

Purpose: To facilitate the construction of a reactor containment building, whereby the inspections of the outer wall of a reactor container after the completion of the construction of the reactor building can be easily carried out. Constitution: In a reactor accommodated in a container encircled by a building wall, a space is provided between the container and the building wall encircling the container, and a metal wall is provided in the space so that it is fitted in the building wall in an attachable or detatchable manner. (Aizawa, K.)

Reactor Physics Training

International Nuclear Information System (INIS)

Baeten, P.

2007-01-01

University courses in nuclear reactor physics at the universities consist of a theoretical description of the physics and technology of nuclear reactors. In order to demonstrate the basic concepts in reactor physics, training exercises in nuclear reactor installations are also desirable. Since the number of reactor facilities is however strongly decreasing in Europe, it becomes difficult to offer to students a means for demonstrating the basic concepts in reactor physics by performing training exercises in nuclear installations. Universities do not generally possess the capabilities for performing training exercises. Therefore, SCK-CEN offers universities the possibility to perform (on a commercial basis) training exercises at its infrastructure consisting of two research reactors (BR1 and VENUS). Besides the organisation of training exercises in the framework of university courses, SCK-CEN also organizes theoretical courses in reactor physics for the education and training of nuclear reactor operators. It is indeed a very important subject to guarantee the safe operation of present and future nuclear reactors. In this framework, an understanding of the fundamental principles of nuclear reactor physics is also necessary for reactor operators. Therefore, the organisation of a basic Nuclear reactor physics course at the level of reactor operators in the initial and continuous training of reactor operators has proven to be indispensable. In most countries, such training also results from the direct request from the safety authorities to assure the high level of competence of the staff in nuclear reactors. The objectives this activity are: (1) to provide training and education activities in reactor physics for university students and (2) to organise courses in nuclear reactor physics for reactor operators

Stereoscopic radiographic images with thermal neutrons

Science.gov (United States)

Silvani, M. I.; Almeida, G. L.; Rogers, J. D.; Lopes, R. T.

2011-10-01

Spatial structure of an object can be perceived by the stereoscopic vision provided by eyes or by the parallax produced by movement of the object with regard to the observer. For an opaque object, a technique to render it transparent should be used, in order to make visible the spatial distribution of its inner structure, for any of the two approaches used. In this work, a beam of thermal neutrons at the main port of the Argonauta research reactor of the Instituto de Engenharia Nuclear in Rio de Janeiro/Brazil has been used as radiation to render the inspected objects partially transparent. A neutron sensitive Imaging Plate has been employed as a detector and after exposure it has been developed by a reader using a 0.5 μm laser beam, which defines the finest achievable spatial resolution of the acquired digital image. This image, a radiographic attenuation map of the object, does not represent any specific cross-section but a convoluted projection for each specific attitude of the object with regard to the detector. After taking two of these projections at different object attitudes, they are properly processed and the final image is viewed by a red and green eyeglass. For monochromatic images this processing involves transformation of black and white radiographies into red and white and green and white ones, which are afterwards merged to yield a single image. All the processes are carried out with the software ImageJ. Divergence of the neutron beam unfortunately spoils both spatial and contrast resolutions, which become poorer as object-detector distance increases. Therefore, in order to evaluate the range of spatial resolution corresponding to the 3D image being observed, a curve expressing spatial resolution against object-detector gap has been deduced from the Modulation Transfer Functions experimentally. Typical exposure times, under a reactor power of 170 W, were 6 min for both quantitative and qualitative measurements. In spite of its intrinsic constraints

Stereoscopic radiographic images with thermal neutrons

International Nuclear Information System (INIS)

Silvani, M.I.; Almeida, G.L.; Rogers, J.D.; Lopes, R.T.

2011-01-01

Spatial structure of an object can be perceived by the stereoscopic vision provided by eyes or by the parallax produced by movement of the object with regard to the observer. For an opaque object, a technique to render it transparent should be used, in order to make visible the spatial distribution of its inner structure, for any of the two approaches used. In this work, a beam of thermal neutrons at the main port of the Argonauta research reactor of the Instituto de Engenharia Nuclear in Rio de Janeiro/Brazil has been used as radiation to render the inspected objects partially transparent. A neutron sensitive Imaging Plate has been employed as a detector and after exposure it has been developed by a reader using a 0.5 μm laser beam, which defines the finest achievable spatial resolution of the acquired digital image. This image, a radiographic attenuation map of the object, does not represent any specific cross-section but a convoluted projection for each specific attitude of the object with regard to the detector. After taking two of these projections at different object attitudes, they are properly processed and the final image is viewed by a red and green eyeglass. For monochromatic images this processing involves transformation of black and white radiographies into red and white and green and white ones, which are afterwards merged to yield a single image. All the processes are carried out with the software ImageJ. Divergence of the neutron beam unfortunately spoils both spatial and contrast resolutions, which become poorer as object-detector distance increases. Therefore, in order to evaluate the range of spatial resolution corresponding to the 3D image being observed, a curve expressing spatial resolution against object-detector gap has been deduced from the Modulation Transfer Functions experimentally. Typical exposure times, under a reactor power of 170 W, were 6 min for both quantitative and qualitative measurements. In spite of its intrinsic constraints

Pyxiloricaria menezesi, a new genus and species of mailed catfish from Rio Miranda and Rio Cuiabá, Brazil (Pisces, Siluriformes, Loricariidae)

NARCIS (Netherlands)

Isbrücker, I.J.H.; Nijssen, H.

1984-01-01

Pyxiloricaria menezesi n. gen., n. sp., is described and illustrated from Rio Miranda (Est. Mato Grosso do Sul) and from Rio Cuiabá (Est. Mato Grosso), Brazil. It is assigned to the subtribe Planiloricariina of the tribe Loricariini, subfamily Loricariinae. A comparison is made with sympatric

FBR type reactor

International Nuclear Information System (INIS)

Kimura, Kimitaka; Fukuie, Ken; Iijima, Tooru; Shimpo, Masakazu.

1994-01-01

In an FBR type reactor for exchanging fuels by pulling up reactor core upper mechanisms, a connection mechanism is disposed for connecting the top of the reactor core and the lower end of the reactor core upper mechanisms. In addition, a cylindrical body is disposed surrounding the reactor core upper mechanisms, and a support member is disposed to the cylindrical body for supporting an intermediate portion of the reactor core upper mechanisms. Then, the lower end of the reactor core upper mechanisms is connected to the top of the reactor core. Same displacements are caused to both of them upon occurrence of earthquakes and, as a result, it is possible to eliminate mutual horizontal displacement between a control rod guide hole of the reactor core upper mechanisms and a control rod insertion hole of the reactor core. In addition, since the intermediate portion of the reactor core upper mechanisms is supported by the support member disposed to the cylindrical body surrounding the reactor core upper mechanisms, deformation caused to the lower end of the reactor core upper mechanisms is reduced, so that the mutual horizontal displacement with respect to the control rod insertion hole of the reactor core can be reduced. As a result, performance of control rod insertion upon occurrence of the earthquakes is improved, so that reactor shutdown is conducted more reliably to improve reactor safety. (N.H.)

RB Research nuclear reactor RB reactor, Annual report for 2000

International Nuclear Information System (INIS)

Milosevic, M.

2000-12-01

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

Reactor container

International Nuclear Information System (INIS)

Kato, Masami; Nishio, Masahide.

1987-01-01

Purpose: To prevent the rupture of the dry well even when the melted reactor core drops into a reactor pedestal cavity. Constitution: In a reactor container in which a dry well disposed above the reactor pedestal cavity for containing the reactor pressure vessel and a torus type suppression chamber for containing pressure suppression water are connected with each other, the pedestal cavity and the suppression chamber are disposed such that the flow level of the pedestal cavity is lower than the level of the pressure suppression water. Further, a pressure suppression water introduction pipeway for introducing the pressure suppression water into the reactor pedestal cavity is disposed by way of an ON-OFF valve. In case if the melted reactor core should fall into the pedestal cavity, the ON-OFF valve for the pressure suppression water introduction pipeway is opened to introduce the pressure suppression water in the suppression chamber into the pedestal cavity to cool the melted reactor core. (Ikeda, J.)

Tratamento conjugado de lixiviado de aterro sanitário e esgoto sanitário em lagoas de estabilização rasas

OpenAIRE

Campos, Andrezza Raphaella Costa

2012-01-01

A busca para desenvolver alternativas viáveis e eficientes para o tratamento do lixiviado de aterro sanitário, fez com que surgisse a iniciativa de pesquisar sobre o tratamento conjugado entre lixiviado de aterro sanitário e esgoto sanitário, visando tratar o lixiviado diluindo este no esgoto, reduzindo as elevadas concentrações de matéria orgânica e nitrogênio amoniacal, deixando em proporções adequadas ao tratamento convencional. Neste estudo, foi analisada a eficiência do processo de trata...

Construção de uma escala de ansiedade para pacientes de ambulatório: um es tu do exploratório

OpenAIRE

Oliveira, José Carlos Silva; Sisto, Fermino Fernandes

2009-01-01

O presente trabalho teve como objetivo estudar a possibilidade de construção de uma escala para avaliar a ansiedade de pessoas em ambulatório. Participaram 636 pacientes, atendidos no ambulatório pelos serviços de saúde de um hospital universitário, nas áreas de Cardiologia, Clínica Médica, Dermatologia, Endocrinologia, Gastroenterologia, Ginecologia, Neurologia, Oftalmologia, Ortopedia e Urologia, com idades entre 25 e 50 anos. O instrumento foi composto por 57 frases e, em uma primeira anál...

Reactor Physics Programme

Energy Technology Data Exchange (ETDEWEB)

De Raedt, C

2000-07-01

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

Reactor Physics Programme

International Nuclear Information System (INIS)

De Raedt, C.

2000-01-01

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

Sistema internacional de hegemonia conservadora: o fracasso da Rio + 20 na governança dos limites planetários

Directory of Open Access Journals (Sweden)

Eduardo Viola

2012-12-01

Full Text Available Em um artigo seminal, Rockström et al. (2009 inauguraram uma nova forma de abordar os problemas ambientais. A abordagem das fronteiras planetárias aparece como um instrumento analítico fundamental para avaliar a governança global do ambiente e, em um sentido mais profundo, para refletir sobre o rumo civilizatório da humanidade. O nosso objetivo nesse artigo, é fazer uma avaliação da Rio+20 utilizando como critério a governança global das fronteiras planetárias. No caminho, fazemos especial referência ao papel do Brasil na Cúpula. Nossa conclusão principal é que a Rio+20 foi um fracasso desde o ponto de vista da definição de um espaço de operação segura para a humanidade e que ele é expressão de um sistema internacional bloqueado e dominado por forças conservadoras. Nesse cenário, o Brasil aparece como uma potência ambiental subdesenvolvida (underachiever environmental power: a combinação de um enorme capital ambiental físico com um deficiente capital ambiental social.En un trabajo seminal, Rockström et al (2009 inauguraron una nueva forma de abordar la problemática ambiental, basada en la noción de fronteras planetarias. Esa perspectiva aparece como un instrumento analítico fundamental para evaluar la gobernanza del medio ambiente y en un sentido mas profundo, el propio rumbo de la civilización. El objetivo de este artículo es hacer un balance de la Rio+20 usando como criterio la gobernanza global de las fronteras planetarias, así como analizar el papel de Brasil en la Cumbre. La conclusión principal es que la Rio+20 fue un fracaso desde el punto de vista de la definición de un espacio de operación segura para la humanidad, fracaso que es expresión de un sistema internacional bloqueado y dominado por fuerzas conservadoras. En ese escenario, Brasil aparece como una potencia ambiental subdesarrollada (underachiever environmental power por combinar un vasto capital ambiental físico con un deficiente capital

Por uma memória do cinema documentário no Rio Grande do Sul: desafios para uma nova historiografia do cinema brasileiro

Directory of Open Access Journals (Sweden)

Cássio dos Santos Tomaim

2010-12-01

Full Text Available A partir de pesquisa bibliográfica e consulta a catálogos e dicionários de filmes brasileiros, buscamos uma compreensão histórica da produção de documentários no Rio Grande do Sul, a fim de problematizar a memória deste cinema. Primeiro foi preciso existir o cinema de não-ficção no Estado, em especial o de curta-metragem, para somente mais tarde ser possível o longa-metragem de ficção gaúcho. Indicativo de que a história do cinema no Rio Grande do Sul não é uma coleção de episódios isolados, como nos fez acreditar a historiografia clássica do cinema brasileiro.

Nuclear reactors. Introduction

International Nuclear Information System (INIS)

Boiron, P.

1997-01-01

This paper is an introduction to the 'nuclear reactors' volume of the Engineers Techniques collection. It gives a general presentation of the different articles of the volume which deal with: the physical basis (neutron physics and ionizing radiations-matter interactions, neutron moderation and diffusion), the basic concepts and functioning of nuclear reactors (possible fuel-moderator-coolant-structure combinations, research and materials testing reactors, reactors theory and neutron characteristics, neutron calculations for reactor cores, thermo-hydraulics, fluid-structure interactions and thermomechanical behaviour of fuels in PWRs and fast breeder reactors, thermal and mechanical effects on reactors structure), the industrial reactors (light water, pressurized water, boiling water, graphite moderated, fast breeder, high temperature and heavy water reactors), and the technology of PWRs (conceiving and building rules, nuclear parks and safety, reactor components and site selection). (J.S.)

Historical review of neutron spectrometry and diffraction in Brazil - 50 years

International Nuclear Information System (INIS)

Voi, Dante L.; Ferreira, Francisco J.O.; Stasiulevicius, Roberto; Rodrigues, Claudio; Parente, Carlos B.R.; Mazzocchi, Vera L.; Mestnik Filho, Jose; Pugliesi, Reinaldo

2011-01-01

Neutron Spectrometry and Diffraction techniques began to be studied in Brazil with the construction of the first research reactors in the years 50 and 60, and were developed with the participation of national and international scientists. In particular, we note the perseverance of the Brazilian pioneer of nuclear energy, Dr. Marcello Damy de Souza Santos, and from that time, with the involvement of some of the early pioneers, such as the physicist Roberto Stasiulevicius, who had the privilege of working in all three Brazilian nuclear research reactors. All these scientists shared half a century of acquired knowledge, helping in the training of a number of experts who are now working in national and international nuclear institutes. The present work reviews in chronological order, the testimony of the historical facts associated with the development and application of experimental techniques using neutrons as a tool for materials analysis and studies for many areas of the sciences and also with the training of personnel. IPEN, IEN and CDTN, all institutes of the CNEN-Brazil, are important in the national and international scene as a result of the research carried out there and the large number of publications produced in the field of neutron spectrometry and diffraction from experimental work carried out using the IEA (5MW), Argonauta (5kW) and more recently, the IPR (250kW) research reactors. An extensive bibliography is also presented and this can be disseminated to everyone interested. (author)

Nuclear reactor, reactor core thereof, and device for constituting the reactor

International Nuclear Information System (INIS)

Takiyama, Masashi.

1994-01-01

A reactor core is constituted by charging coolants (light water) in a reactor pressure vessel and distributing fuel assemblies, reflecting material sealing pipes, moderator (heavy water and helium gas) sealing pipes, and gas sealing pipes therein. A fuel guide tube is surrounded by a cap and the gap therebetween is made hollow and filled with coolant steams. The cap is supported by a baffle plate. The moderator sealing pipe is disposed in a flow channel of coolants in adjacent with the cap. The position of the moderator sealing tube in the reactor core is controlled by water stream from a hydraulic pump with a guide tube extending below the baffle plate being as a guide. Then, the position of the moderator sealing tube is varied to conduct power control, burnup degree compensation, and reactor shut down. With such procedures, moderator cooling facility is no more necessary to simplify the structure. Further, heat generated from the moderator is transferred to the coolants thereby improving heat efficiency of the reactor. (I.N.)

GO RIO: Achieving Universal Access to Mass Transit

Science.gov (United States)

Martinez, Ted, Jr.; Castaneda-Calleros, Russell

2009-01-01

GO RIO is a universal access, mass-transit program that has been offered to all students who are registered full-time at Rio Hondo College. Through an agreement with five local transit agencies, full-time students can obtain a pass that provides full access seven days a week throughout the entire semester.

Research of the Rio Grande Ecosystem Management Program

Science.gov (United States)

Deborah M. Finch

2000-01-01

This paper describes the mission, objectives, and preliminary results of the Middle Rio Grande Ecosystem Management Research Program managed at the Rocky Mountain Research Station's Albuquerque laboratory. This program was initiated in 1994 to address growing pressures to effectively manage the limited resources of the middle Rio Grande Basin. The program is...

Um Visitante do Rio de Janeiro Colonial

Directory of Open Access Journals (Sweden)

Jean M. Carvalho França

1997-01-01

Full Text Available O texto que se segue é a tradução de um manuscrito francês, intitulado Relâche du Vaisseau L'Arc-en-ciel à Rio de Janeiro, 1748, que se encontra na Biblioteca da Ajuda, em Lisboa. Trata-se de um relato anônimo, que dá conta da passagem do navio francês L'Arc-en-ciel pelo porto carioca. Tal relato, um curioso documento para a história dos nossos costumes, contém uma descrição da baía da Guanabara e da cidade do Rio de Janeiro, uma pequena análise do caráter da gente portuguesa do Brasil, um perfil do Governador Dom Fernando Freire e algumas considerações gerais sobre a situação do porto local e sobre os víveres disponíveis na região.The following text is a translation of a French manuscript named Relachê du Vaisseau L'Arc-en-ciel à Rio de Janeiro, 1748, which is in Biblioteca da Ajuda (Ajuda Library in Lisbon. It is an anonymous report and relates the stay of the French ship L'Arc-en-ciel in Rio de Janeiro harbour. Such report, a curious document for the history of our customs, has a description of Guanabara bay and Rio de Janeiro city, a brief analysis of the character of the Portuguese people in Brazil, a prolife of Governor Dom Fernando Freire and some considerations of the situation of local harbour and on the provisions available in that region.

Slurry reactors

Energy Technology Data Exchange (ETDEWEB)

Kuerten, H; Zehner, P [BASF A.G., Ludwigshafen am Rhein (Germany, F.R.)

1979-08-01

Slurry reactors are designed on the basis of empirical data and model investigations. It is as yet not possible to calculate the flow behavior of such reactors. The swarm of gas bubbles and cluster formations of solid particles and their interaction in industrial reactors are not known. These effects control to a large extent the gas hold-up, the gas-liquid interface and, similarly as in bubble columns, the back-mixing of liquids and solids. These hydrodynamic problems are illustrated in slurry reactors which constructionally may be bubble columns, stirred tanks or jet loop reactors. The expected effects are predicted by means of tests with model systems modified to represent the conditions in industrial hydrogenation reactors. In his book 'Mass Transfer in Heterogeneous Catalysis' (1970) Satterfield complained of the lack of knowledge about the design of slurry reactors and hence of the impossible task of the engineer who has to design a plant according to accepted rules. There have been no fundamental changes since then. This paper presents the problems facing the engineer in designing slurry reactors, and shows new development trends.

Optimal reactor strategy for commercializing fast breeder reactors

International Nuclear Information System (INIS)

Yamaji, Kenji; Nagano, Koji

1988-01-01

In this paper, a fuel cycle optimization model developed for analyzing the condition of selecting fast breeder reactors in the optimal reactor strategy is described. By dividing the period of planning, 1966-2055, into nine ten-year periods, the model was formulated as a compact linear programming model. With the model, the best mix of reactor types as well as the optimal timing of reprocessing spent fuel from LWRs to minimize the total cost were found. The results of the analysis are summarized as follows. Fast breeder reactors could be introduced in the optimal strategy when they can economically compete with LWRs with 30 year storage of spent fuel. In order that fast breeder reactors monopolize the new reactor market after the achievement of their technical availability, their capital cost should be less than 0.9 times as much as that of LWRs. When a certain amount of reprocessing commitment is assumed, the condition of employing fast breeder reactors in the optimal strategy is mitigated. In the optimal strategy, reprocessing is done just to meet plutonium demand, and the storage of spent fuel is selected to adjust the mismatch of plutonium production and utilization. The price hike of uranium ore facilitates the commercial adoption of fast breeder reactors. (Kako, I.)

Computerized reactor monitor and control for nuclear reactors

International Nuclear Information System (INIS)

Buerger, L.

1982-01-01

The analysis of a computerized process control system developed by Transelektro-KFKI-Videoton (Hangary) for a twenty-year-old research reactor in Budapest and or a new one in Tajura (Libya) is given. The paper describes the computer hardware (R-10) and the implemented software (PROCESS-24K) as well as their applications at nuclear reactors. The computer program provides for man-machine communication, data acquisition and processing, trend and alarm analysis, the control of the reactor power, reactor physical calculations and additional operational functions. The reliability and the possible further development of the computerized systems which are suitable for application at reactors of different design are also discussed. (Sz.J.)

Laboratórios na Área de Ensino de Línguas

Directory of Open Access Journals (Sweden)

José Carlos Paes de Almeida Filho

2017-03-01

Full Text Available O imaginário do laboratório como local de experimentação e invenções acrescentou um sentido novo a esse lugar de nascimento do conhecimento quando o Ensino de Línguas deu a essa palavra o sentido de local de prática de produção automatizadora de uma nova língua nos anos 60 e 70 do século anterior. A realidade metodológica estrutural audiolingual com sua ênfase oral na forma sistêmica rotinizadora para atender princípios psicológicos da superaprendizagem deu as condições necessárias para a invenção do laboratório de línguas que consolidou o nome laboratório associado ao ensino e aprendizagem de idiomas. Passados quase cinquenta anos da introdução do laboratório de línguas, qual o cenário de sentidos de um laboratório para os dias de hoje?  Para explorar o arco de sentidos que foram organicamente se condensando na área de Ensino de Línguas e para avaliar os sentidos de lugar e práticas condizentes de um laboratório, sete significados foram reconhecidos na prática contemporânea para que alunos de graduação em Letras (Linguagem, futuros professores e pesquisadores, e mestres já atuando na prática pudessem avaliar as possibilidades de se criar ou manter um laboratório justificável associado ao ensino de línguas.

Safeguarding research reactors

International Nuclear Information System (INIS)

Powers, J.A.

1983-03-01

The report is organized in four sections, including the introduction. The second section contains a discussion of the characteristics and attributes of research reactors important to safeguards. In this section, research reactors are described according to their power level, if greater than 25 thermal megawatts, or according to each fuel type. This descriptive discussion includes both reactor and reactor fuel information of a generic nature, according to the following categories. 1. Research reactors with more than 25 megawatts thermal power, 2. Plate fuelled reactors, 3. Assembly fuelled reactors. 4. Research reactors fuelled with individual rods. 5. Disk fuelled reactors, and 6. Research reactors fuelled with aqueous homogeneous fuel. The third section consists of a brief discussion of general IAEA safeguards as they apply to research reactors. This section is based on IAEA safeguards implementation documents and technical reports that are used to establish Agency-State agreements and facility attachments. The fourth and last section describes inspection activities at research reactors necessary to meet Agency objectives. The scope of the activities extends to both pre and post inspection as well as the on-site inspection and includes the examination of records and reports relative to reactor operation and to receipts, shipments and certain internal transfers, periodic verification of fresh fuel, spent fuel and core fuel, activities related to containment and surveillance, and other selected activities, depending on the reactor

Control of reactor coolant flow path during reactor decay heat removal

Science.gov (United States)

Hunsbedt, Anstein N.

1988-01-01

An improved reactor vessel auxiliary cooling system for a sodium cooled nuclear reactor is disclosed. The sodium cooled nuclear reactor is of the type having a reactor vessel liner separating the reactor hot pool on the upstream side of an intermediate heat exchanger and the reactor cold pool on the downstream side of the intermediate heat exchanger. The improvement includes a flow path across the reactor vessel liner flow gap which dissipates core heat across the reactor vessel and containment vessel responsive to a casualty including the loss of normal heat removal paths and associated shutdown of the main coolant liquid sodium pumps. In normal operation, the reactor vessel cold pool is inlet to the suction side of coolant liquid sodium pumps, these pumps being of the electromagnetic variety. The pumps discharge through the core into the reactor hot pool and then through an intermediate heat exchanger where the heat generated in the reactor core is discharged. Upon outlet from the heat exchanger, the sodium is returned to the reactor cold pool. The improvement includes placing a jet pump across the reactor vessel liner flow gap, pumping a small flow of liquid sodium from the lower pressure cold pool into the hot pool. The jet pump has a small high pressure driving stream diverted from the high pressure side of the reactor pumps. During normal operation, the jet pumps supplement the normal reactor pressure differential from the lower pressure cold pool to the hot pool. Upon the occurrence of a casualty involving loss of coolant pump pressure, and immediate cooling circuit is established by the back flow of sodium through the jet pumps from the reactor vessel hot pool to the reactor vessel cold pool. The cooling circuit includes flow into the reactor vessel liner flow gap immediate the reactor vessel wall and containment vessel where optimum and immediate discharge of residual reactor heat occurs.

Geographic distribution of genetic diversity in populations of Rio Grande Chub Gila pandora

Science.gov (United States)

Galindo, Rene; Wilson, Wade; Caldwell, Colleen A.

2016-01-01

In the southwestern United States (US), the Rio Grande chub (Gila pandora) is state-listed as a fish species of greatest conservation need and federally listed as sensitive due to habitat alterations and competition with non-native fishes. Characterizing genetic diversity, genetic population structure, and effective number of breeders will assist with conservation efforts by providing a baseline of genetic metrics. Genetic relatedness within and among G. pandora populations throughout New Mexico was characterized using 11 microsatellite loci among 15 populations in three drainage basins (Rio Grande, Pecos, Canadian). Observed heterozygosity (HO) ranged from 0.71–0.87 and was similar to expected heterozygosity (0.75–0.87). Rio Ojo Caliente (Rio Grande) had the highest allelic richness (AR = 15.09), while Upper Rio Bonito (Pecos) had the lowest allelic richness (AR = 6.75). Genetic differentiation existed among all populations with the lowest genetic variation occurring within the Pecos drainage. STRUCTURE analysis revealed seven genetic clusters. Populations of G. pandora within the upper Rio Grande drainage (Rio Ojo Caliente, Rio Vallecitos, Rio Pueblo de Taos) had high levels of admixture with Q-values ranging from 0.30–0.50. In contrast, populations within the Pecos drainage (Pecos River and Upper Rio Bonito) had low levels of admixture (Q = 0.94 and 0.87, respectively). Estimates of effective number of breeders (N b ) varied from 6.1 (Pecos: Upper Rio Bonito) to 109.7 (Rio Grande: Rio Peñasco) indicating that populations in the Pecos drainage are at risk of extirpation. In the event that management actions are deemed necessary to preserve or increase genetic diversity of G. pandora, consideration must be given as to which populations are selected for translocation.

As Redes Sociais no Sector primário

OpenAIRE

Areias, Marcos André Caetano

2013-01-01

Dissertação apresentada como requisito parcial para obtenção do grau de Mestre em Estatística e Gestão de Informação A dissertação que de seguida será apresentada enquadra-se no âmbito da importância das redes sociais, enquanto factor de utilização e de trabalho no sector primário. Como tal, tem como objectivo estudar e aprofundar o conhecimento da utilização das redes sociais no sector primário. Desta forma, a dissertação foca-se no estudo das redes sociais no sector primário de três p...

Reactor operations Brookhaven medical research reactor, Brookhaven high flux beam reactor informal monthly report

International Nuclear Information System (INIS)

Hauptman, H.M.; Petro, J.N.; Jacobi, O.

1995-04-01

This document is the April 1995 summary report on reactor operations at the Brookhaven Medical Research Reactor and the Brookhaven High Flux Beam Reactor. Ongoing experiments/irradiations in each are listed, and other significant operations functions are also noted. The HFBR surveillance testing schedule is also listed

Neoplasmas do sistema urinário em 113 cães

OpenAIRE

Inkelmann,Maria Andréia; Kommers,Glaucia Denise; Fighera,Rafael A.; Irigoyen,Luiz Francisco; Barros,Claudio S.L.; Silveira,Isadora P.; Trost,Maria Elisa

2011-01-01

Foram revisados 4.723 protocolos de necropsias de cães realizadas entre janeiro de 1990 e julho de 2010 no LPV-UFSM. Os principais objetivos deste estudo retrospectivo foram determinar a prevalência e os tipos de neoplasmas que ocorreram no sistema urinário. Em 113 (2,4%) dos cães necropsiados, foram diagnosticados 27 neoplasmas primários e 86 metastáticos ou como parte de tumores multicêntricos no sistema urinário. Dos neoplasmas primários, a grande maioria teve origem epitelial. Treze casos...

Reactor core for FBR type reactor

International Nuclear Information System (INIS)

Fujita, Tomoko; Watanabe, Hisao; Kasai, Shigeo; Yokoyama, Tsugio; Matsumoto, Hiroshi.

1996-01-01

In a gas-sealed assembly for a FBR type reactor, two or more kinds of assemblies having different eigen frequency and a structure for suppressing oscillation of liquid surface are disposed in a reactor core. Coolant introduction channels for introducing coolants from inside and outside are disposed in the inside of structural members of an upper shielding member to form a shielding member-cooling structure in the reactor core. A structure for promoting heat conduction between a sealed gas in the assembly and coolants at the inner side or the outside of the assembly is disposed in the reactor core. A material which generates heat by neutron irradiation is disposed in the assembly to heat the sealed gases positively by radiation heat from the heat generation member also upon occurrence of power elevation-type event to cause temperature expansion. Namely, the coolants flown out from or into the gas sealed-assemblies cause differential fluctuation on the liquid surface, and the change of the capacity of a gas region is also different on every gas-sealed assemblies thereby enabling to suppress fluctuation of the reactor power. Pressure loss is increased by a baffle plate or the like to lower the liquid surface of the sodium coolants or decrease the elevating speed thereof thereby suppressing fluctuation of the reactor power. (N.H.)

Space-time reactor kinetics for heterogeneous reactor structure

Energy Technology Data Exchange (ETDEWEB)

Raisic, N [Boris Kidric Institute of nuclear sciences Vinca, Belgrade (Yugoslavia)

1969-11-15

An attempt is made to formulate time dependent diffusion equation based on Feinberg-Galanin theory in the from analogue to the classical reactor kinetic equation. Parameters of these equations could be calculated using the existing codes for static reactor calculation based on the heterogeneous reactor theory. The obtained kinetic equation could be analogues in form to the nodal kinetic equation. Space-time distribution of neutron flux in the reactor can be obtained by solving these equations using standard methods.

Nuclear Reactor RA Safety Report, Vol. 4, Reactor

International Nuclear Information System (INIS)

1986-11-01

RA research reactor is thermal heavy water moderated and cooled reactor. Metal uranium 2% enriched fuel elements were used at the beginning of its operation. Since 1976, 80% enriched uranium oxide dispersed in aluminium fuel elements were gradually introduced into the core and are the only ones presently used. Reactor core is cylindrical, having diameter 40 cm and 123 cm high. Reaktor core is made up of 82 fuel elements in aluminium channels, lattice is square, lattice pitch 13 cm. Reactor vessel is cylindrical made of 8 mm thick aluminium, inside diameter 140 cm and 5.5 m high surrounded with neutron reflector and biological shield. There is no containment, the reactor building is playing the shielding role. Three pumps enable circulation of heavy water in the primary cooling circuit. Degradation of heavy water is prevented by helium cover gas. Control rods with cadmium regulate the reactor operation. There are eleven absorption rods, seven are used for long term reactivity compensation, two for automatic power regulation and two for safety shutdown. Total anti reactivity of the rods amounts to 24%. RA reactor is equipped with a number of experimental channels, 45 vertical (9 in the core), 34 in the graphite reflector and two in the water biological shield; and six horizontal channels regularly distributed in the core. This volume include detailed description of systems and components of the RA reactor, reactor core parameters, thermal hydraulics of the core, fuel elements, fuel elements handling equipment, fuel management, and experimental devices [sr

Feasible reactor power cutback logic development for an integral reactor

International Nuclear Information System (INIS)

Han, Soon-Kyoo; Lee, Chung-Chan; Choi, Suhn; Kang, Han-Ok

2013-01-01

Major features of integral reactors that have been developed around the world recently are simplified operating systems and passive safety systems. Even though highly simplified control system and very reliable components are utilized in the integral reactor, the possibility of major component malfunction cannot be ruled out. So, feasible reactor power cutback logic is required to cope with the malfunction of components without inducing reactor trip. Simplified reactor power cutback logic has been developed on the basis of the real component data and operational parameters of plant in this study. Due to the relatively high rod worth of the integral reactor the control rod assembly drop method which had been adapted for large nuclear power plants was not desirable for reactor power cutback of the integral reactor. Instead another method, the control rod assembly control logic of reactor regulating system controls the control rod assembly movements, was chosen as an alternative. Sensitivity analyses and feasibility evaluations were performed for the selected method by varying the control rod assembly driving speed. In the results, sensitivity study showed that the performance goal of reactor power cutback system could be achieved with the limited range of control rod assembly driving speed. (orig.)

A Percepção sobre Carreira dos Funcionários de uma Empresa Automotiva do Rio Grande do Sul

Directory of Open Access Journals (Sweden)

Angela Beatriz Busato Garay

2012-11-01

Full Text Available Os estudos sobre carreira têm se mostrado relevantes na área de gestão de pessoas, entretanto, a maioria das pesquisas relativas ao tema é voltada a gerentes e diretores de grandes corporações.  Este artigo, por sua vez, tem como objetivo conhecer a percepção sobre carreira de funcionários das áreas administrativa e de produção de uma empresa automotiva situada na região metropolitana de Porto Alegre, Rio Grande do Sul. Esta pesquisa, com abordagem qualitativa, caracteriza-se como um estudo de caso de natureza exploratório-descritiva. O quadro teórico utilizado contempla o contexto histórico das teorias de carreira, suas concepções e significados e sua gestão. Para obtenção dos dados, utilizaram-se entrevistas semiestruturadas, realizadas com doze funcionários. A escolha dos respondentes considerou que eles não ocupassem cargos de gerência ou direção na organização, bem como seu nível de escolaridade. Os dados obtidos foram analisados quanto ao conteúdo e revelaram que a maioria dos entrevistados entende carreira como sinônimo de evolução ou ascensão profissional. Esses funcionários, de níveis hierárquicos inferiores, relacionam sua permanência na organização ao oferecimento de possibilidades de satisfação pessoal, crescimento e motivação profissional.

Laboratório químico-prático do Rio de Janeiro: primeira tentativa de difusão da Química no Brasil (1812- 1819)

OpenAIRE

Santos Nadja Paraense dos

2004-01-01

Until the present date, historians of science have described inaccurately the first laboratory created in Brazil for establishing and divulging Chemistry, namely the "Laboratório Químico-Prático do Rio de Janeiro". During recent research carried out in the Arquivo do Museu Imperial (Petrópolis, RJ), I localized a document entitled "Ensaio histórico analítico das operações do Laboratório Químico-Prático do Rio de Janeiro", which allowed me to gain the relevant information to correct some of th...

Primeiro registro de Chara indica e Chara zeylanica (Charophyceae, Charales, Characeae em reservatórios do semiárido do estado do Rio Grande do Norte, Brasil

Directory of Open Access Journals (Sweden)

Gustavo Henrique Gonzaga da Silva

2013-04-01

Full Text Available http://dx.doi.org/10.5007/2175-7925.2013v26n3p243 No presente trabalho, apresentamos os primeiros registros das macroalgas Chara indica e Chara zeylanica para o estado do Rio Grande do Norte, Brasil, e para o semiárido nordestino. Exemplares de C. indica e C. zeylanica foram coletados nos reservatórios de Santa Cruz e Umari, respectivamente. Ambos os reservatórios estão localizados na bacia hidrográfica do Rio Apodi-Mossoró (oeste do estado, estando inseridos no bioma Caatinga.

Segunda Guerra Mundial, Rio de Janeiro

Directory of Open Access Journals (Sweden)

Ricardo de Souza Rocha

2007-01-01

Full Text Available The purpose of this paper is to analyze the National Memorial to the World War II Dead (1956-60, a monument designed by Marcos Konder Netto and Hélio Ribas Marinho, and located in Flamengo Park, Rio de Janeiro. We start by commenting on the debates that were going on within the Modernist movement about the need for a new monumentality. Then, we examine the memorial against the urban landscape of Rio de Janeiro and its specific architectural language. Finally, we make an effort to explain the apparent paradox found in modern monuments.

Experimental study of the attenuation waves oriented to transients caused by the sodium-water explosive reaction in fast reactors

International Nuclear Information System (INIS)

Pedroso, L.J.

1990-01-01

One of the problems related to fluid-structure interaction that can compromise the structural integrity of components of a fast reactor is the explosion caused by the sodium-water reaction, in the case of a flood at the level of the thermic exchange wall at the steam generator. In this paper we have considered the aspects of the pressure-waves damping caused by the reaction, when these waves transverse certain perforated structures. In order to solve this problem, we also adopted a parametric experimental approach, using a scale model (RIO test rig). (author)

RA Reactor

International Nuclear Information System (INIS)

1978-02-01

In addition to basic characteristics of the RA reactor, organizational scheme and financial incentives, this document covers describes the state of the reactor components after 18 years of operation, problems concerned with obtaining the licence for operation with 80% fuel, problems of spent fuel storage in the storage pool of the reactor building and the need for renewal of reactor equipment, first of all instrumentation [sr

Study of nuclear reactions involving heavy nuclei and intermediate- and high-energy protons and an application in nuclear reactor physics (ADS)

International Nuclear Information System (INIS)

Matuoka, Paula Fernanda Toledo

2016-01-01

In the present work, intermediate- and high-energy nuclear reactions involving heavy nuclei and protons were studied with the Monte Carlo CRISP (Rio - Ilheus - Sao Paulo Collaboration) model. The most relevant nuclear processes studied were intranuclear cascade and fission-evaporation competition. Preliminary studies showed fair agreement between CRISP model calculation and experimental data of multiplicity of evaporated neutrons (E 20 MeV) were emitted mostly in the intranuclear cascade stage, while evaporation presented larger neutron multiplicity. Fission cross section of 209 mb and spallation cross section of 1788 mb were calculated { both in agreement with experimental data. The fission process resulted in a symmetric mass distribution. Another Monte Carlo code, MCNP, was used for radiation transport in order to understand the role of a spallation neutron source in a ADS (Accelerator Driven System) nuclear reactor. Initially, a PWR reactor was simulated to study the isotopic compositions in spent nuclear fuel. As a rst attempt, a spallation neutron source was adapted to an industrial size nuclear reactor. The results showed no evidence of incineration of transuranic elements and modifications were suggested. (author)

H Reactor

Data.gov (United States)

Federal Laboratory Consortium — The H Reactor was the first reactor to be built at Hanford after World War II.It became operational in October of 1949, and represented the fourth nuclear reactor on...

Reactor container

International Nuclear Information System (INIS)

Naruse, Yoshihiro.

1990-01-01

The thickness of steel shell plates in a reactor container embedded in sand cussions is monitored to recognize the corrosion of the steel shell plates. That is, the reactor pressure vessel is contained in a reactor container shell and the sand cussions are disposed on the lower outside of the reactor container shell to elastically support the shell. A pit is disposed at a position opposing to the sand cussions for measuring the thickness of the reactor container shell plates. The pit is usually closed by a closing member. In the reactor container thus constituted, the closing member can be removed upon periodical inspection to measure the thickness of the shell plates. Accordingly, the corrosion of the steel shell plates can be recognized by the change of the plate thickness. (I.S.)

Hybrid reactors

International Nuclear Information System (INIS)

Moir, R.W.

1980-01-01

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

Nuclear research reactors

International Nuclear Information System (INIS)

1985-01-01

It's presented data about nuclear research reactors in the world, retrieved from the Sien (Nuclear and Energetic Information System) data bank. The information are organized in table forms as follows: research reactors by countries; research reactors by type; research reactors by fuel and research reactors by purpose. (E.G.) [pt

RIO Country Report 2015

DEFF Research Database (Denmark)

Grimpe, Christoph; Mitchell, Jessica

The 2015 series of RIO Country Reports analyse and assess the policy and the national research and innovation system developments in relation to national policy priorities and the EU policy agenda with special focus on ERA and Innovation Union. The executive summaries of these reports put forward...

Resíduos de pesticidas em sedimento de fundo de rio na Bacia Hidrográfica do Rio Cuiabá, Mato Grosso, Brasil

Directory of Open Access Journals (Sweden)

Juliana Possavatz

2014-01-01

Full Text Available O rio Cuiabá é um importante tributário do rio Paraguai, cuja bacia é de grande importância por agasalhar o Pantanal, a maior área úmida do planeta. A base econômica da bacia hidrográfica do rio Cuiabá é a produção agrícola e pecuária que, para manter elevada produtividade, requer grandes quantidades de insumos agrícolas como os pesticidas que, podem atingir diversos ambientes devido aos processos de dispersão que ocorrem após sua introdução no ambiente. Os sedimentos desempenham importante papel para a caracterização da poluição de rios devido a seu potencial de acumulação de poluentes. Este estudo objetivou avaliar a contaminação por pesticidas usados nas lavouras plantadas na bacia do rio Cuiabá, MT. Para tanto, amostras de sedimento de fundo foram coletadas mensalmente de agosto de 2011 a julho de 2012. Para a determinação dos pesticidas atrazina, cipermetrina, clorpirifós, endossulfam (α, β e seu metabólito endossulfam sulfato, lambda-cialotrina, malationa, metolacloro, metribuzim, parationa metílica, permetrina e trifuralina no sedimento utilizou-se método multirresíduo que consiste na extração sólido-líquido por agitação mecânica seguida de purificação por extração líquido-líquido e identificação e quantificação por cromatografia a gás acoplada a espectrometria de massas. Resíduos de pesticidas foram identificados em amostras coletadas em agosto e setembro de 2011 e janeiro, fevereiro, abril e julho de 2012, em concentrações variando de 5,7 a 79,3 µg kg-1 . Embora a frequência de detecção tenha sido baixa, esses resultados indicam que há potencial de transporte de pesticidas usados na bacia do rio Cuiabá e seus tributários atingindo o Pantanal.

Strategic planning for research reactors. Guidance for reactor managers

International Nuclear Information System (INIS)

2001-04-01

The purpose of this publication is to provide guidance on how to develop a strategic plan for a research reactor. The IAEA is convinced of the need for research reactors to have strategic plans and is issuing a series of publications to help owners and operators in this regard. One of these covers the applications of research reactors. That report brings together all of the current uses of research reactors and enables a reactor owner or operator to evaluate which applications might be possible with a particular facility. An analysis of research reactor capabilities is an early phase in the strategic planning process. The current document provides the rationale for a strategic plan, outlines the methodology of developing such a plan and then gives a model that may be followed. While there are many purposes for research reactor strategic plans, this report emphasizes the use of strategic planning in order to increase utilization. A number of examples are given in order to clearly illustrate this function

USO DE RESERVATÓRIOS DOMICILIARES E CONHECIMENTO DA POPULAÇÃO

Directory of Open Access Journals (Sweden)

Juliana Alvares Duarte Bonini CAMPOS

2009-07-01

Full Text Available

A água destinada ao consumo humano deve ser adequada para a manutenção da saúde e para isso não só o tratamento mas também o armazenamento da água deve ser realizado de maneira adequada. Como os reservatórios domiciliares podem atuar como fator deteriorador, realizou-se um inquérito com 74 moradores da cidade de Araraquara visando obter informaçãoes sobre o conhecimento da finalidade e os cuidados despendidos à limpeza dos reservatórios. Os resultados monstraram que 67,6% dos entrevistados conheciam a finalidade dos reservatórios e apenas 59,5% realizavam limpeza periódica. Apesar de 94,6% saberem da necessidade das limpezas 40% justificaram não fazê-las devido as dificuldades de acesso e 53,3% por outros motivos. A classe social foi estimada através de questionário padrão e os dados obtidos avaliados estatisticamente. Dos cruzamentos apenas o estado de conservação do reservatório por classe social foi significativo. Os resutados demonstram portanto que os cuidados necessários à manutenção da qualidade da água não estão sendo observados e que campanhas de informação e esclarecimento devem ser realizadas para evitar a deterioração da qualidade da água armazenada nos reservatórios domiciliares. PALAVRAS-CHAVE: Reservatório domiciliar e qualidade da água.

A atuação do Observatório Nacional registrada nos relatórios ministeriais 1889 a 1930

Science.gov (United States)

Rodrigues, T.

2003-08-01

O período republicano até 1930 foi marcante na história do Observatório Nacional. Diversas reformas levaram a instituição a três ministérios diferentes e mudaram a ênfase do seu trabalho. A tão aguardada mudança para uma nova sede, em São Cristóvão, em 1920, não foi suficiente para que a instituição acompanhasse o ritmo tomado pela astronomia no mundo e se firmasse como ambiente de pesquisa. Uma análise simplificada poderia caracterizar um período de produção científica insignificante, dado o distanciamento da instituição dos novos rumos da astrofísica e da rápida inovação dos instrumentos, além do pequeno volume de publicações. Era uma época em que ainda não existiam os mecanismos formais de apoio e avaliação da atividade científica. Esse trabalho procura identificar a real atividade do Observatório no conteúdo dos Relatórios Ministeriais que, ao final de cada ano, apresentava as atividades, sucessos e problemas enfrentados pela instituição. Questões como instrumental e recursos humanos necessários; entraves burocráticos e financeiros; e articulações com outros observatórios se complementaram entre si ao longo desses anos para definir o perfil institucional e alguns aspectos fundamentais para a construção da astronomia no país. É possível concluir que a ênfase em serviços geográficos e de meteorologia, ao lado da inadequação dos instrumentos e do local, quase fizeram desaparecer a pesquisa em astronomia. Porém, vale destacar a sobrevivência de alguns trabalhos, como, por exemplo, variação de latitude e observação de estrelas duplas que mantiveram importante intercâmbio com outros grupos de pesquisa, demonstrando o constante esforço dos astrônomos e das diretorias em defesa da atividade científica.

Licensed reactor nuclear safety criteria applicable to DOE reactors

International Nuclear Information System (INIS)

1991-04-01

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

A introdução da matemática moderna no Ciclo Preparatório do Ensino Secundário em Portugal

OpenAIRE

Bento, Marta Alexandra Marques

2012-01-01

Dissertação para obtenção do Grau de Mestre em Ensino da Matemática Com o presente estudo pretende-se estudar a introdução do programa de Matemática Moderna no contexto da criação do novo Ciclo Preparatório do Ensino Secundário, através da visão do Inspetor Joaquim Simões Redinha, sendo por isso necessário reunir e digitalizar documentação relativa aos primeiros anos do referido ciclo e obter notas sobre o percurso profissional e perspetivas do supramencionado inspetor. Pretende-se aind...

Research reactors - an overview

International Nuclear Information System (INIS)

West, C.D.

1997-01-01

A broad overview of different types of research and type reactors is provided in this paper. Reactor designs and operating conditions are briefly described for four reactors. The reactor types described include swimming pool reactors, the High Flux Isotope Reactor, the Mark I TRIGA reactor, and the Advanced Neutron Source reactor. Emphasis in the descriptions is placed on safety-related features of the reactors. 7 refs., 7 figs., 2 tabs

Multiregion reactors

International Nuclear Information System (INIS)

Moura Neto, C. de; Nair, R.P.K.

1979-08-01

The study of reflected reactors can be done employing the multigroup diffusion method. The neutron conservation equations, inside the intervals, can be written by fluxes and group constants. A reflected reactor (one and two groups) for a slab geometry is studied, aplying the continuity of flux and current in the interface. At the end, the appropriated solutions for a infinite cylindrical reactor and for a spherical reactor are presented. (Author) [pt

Violência e sofrimento social no itinerário de travestis de Santa Maria, Rio Grande do Sul, Brasil

Directory of Open Access Journals (Sweden)

Martha Helena Teixeira de Souza

2015-04-01

Full Text Available No ano de 2012, realizamos pesquisa etnográfica com travestis de Santa Maria, Rio Grande do Sul, Brasil, por meio de observação participante, entrevistas e acompanhamento de suas vidas cotidianas. Durante esse período, percebemos que as violências física e simbólica e o sofrimento delas decorrentes eram invariantes, condição com a qual tinham que lidar em seus itinerários, em suas práticas e afazeres diários. Este artigo discute as violências vivenciadas nas trajetórias percorridas pelas travestis (família, escola, delegacias, serviços de saúde, procurando, sobretudo, compreender como tais violências estão relacionadas às experiências nos serviços de saúde e como os serviços de saúde por elas acessados reagiram às violências.

Análise de uma iniciativa de valorização de rios e lagoas em áreas urbanas: Programa Águas do rio (Guardiões dos rios).

OpenAIRE

Andreia Cardoso da Silva

2009-01-01

A preocupação com recursos hídricos tem sido crescente em meios urbanos. O despejo de resíduos sólidos em rios é comum por populações ribeirinhas, favorecendo a ocorrência de enchentes, a proliferação de vetores e doenças e o desprezo da comunidade pelos rios. Nesse contexto, programas que relacionam lixo, recursos hídricos e população ribeirinha têm sido objeto de várias iniciativas governamentais. Este trabalho busca avaliar uma delas: o Programa Municipal de valorização de r...

Reactor building

International Nuclear Information System (INIS)

Maruyama, Toru; Murata, Ritsuko.

1996-01-01

In the present invention, a spent fuel storage pool of a BWR type reactor is formed at an upper portion and enlarged in the size to effectively utilize the space of the building. Namely, a reactor chamber enhouses reactor facilities including a reactor pressure vessel and a reactor container, and further, a spent fuel storage pool is formed thereabove. A second spent fuel storage pool is formed above the auxiliary reactor chamber at the periphery of the reactor chamber. The spent fuel storage pool and the second spent fuel storage pool are disposed in adjacent with each other. A wall between both of them is formed vertically movable. With such a constitution, the storage amount for spent fuels is increased thereby enabling to store the entire spent fuels generated during operation period of the plant. Further, since requirement of the storage for the spent fuels is increased stepwisely during periodical exchange operation, it can be used for other usage during the period when the enlarged portion is not used. (I.S.)

Nuclear reactor

International Nuclear Information System (INIS)

Garabedian, G.

1988-01-01

A liquid reactor is described comprising: (a) a reactor vessel having a core; (b) one or more satellite tanks; (c) pump means in the satellite tank; (d) heat exchanger means in the satellite tank; (e) an upper liquid metal conduit extending between the reactor vessel and the satellite tank; (f) a lower liquid metal duct extending between the reactor vessel and satellite tanks the upper liquid metal conduit and the lower liquid metal duct being arranged to permit free circulation of liquid metal between the reactor vessel core and the satellite tank by convective flow of liquid metal; (g) a separate sealed common containment vessel around the reactor vessel, conduits and satellite tanks; (h) the satellite tank having space for a volume of liquid metal that is sufficient to dampen temperature transients resulting from abnormal operating conditions

Reactor physics challenges in GEN-IV reactor design

Energy Technology Data Exchange (ETDEWEB)

Driscoll, Michael K.; Hejzlar, Pavel [Massachusetts Institute of Technology, MA (United States)

2005-02-15

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources.

Reactor physics challenges in GEN-IV reactor design

International Nuclear Information System (INIS)

Driscoll, Michael K.; Hejzlar, Pavel

2005-01-01

An overview of the reactor physics aspects of GENeration Four (GEN-IV) advanced reactors is presented, emphasizing how their special requirements for enhanced sustainability, safety and economics motivates consideration of features not thoroughly analyzed in the past. The resulting concept-specific requirements for better data and methods are surveyed, and some approaches and initiatives are suggested to meet the challenges faced by the international reactor physics community. No unresolvable impediments to successful development of any of the six major types of proposed reactors are identified, given appropriate and timely devotion of resources

Crianças em situação de violência de um ambulatório do Rio de Janeiro: conhecendo seu perfil

OpenAIRE

Pierantoni, Lucia Martins de Magalhães; Cabral, Ivone Evangelista

2009-01-01

Buscou-se caracterizar as crianças envolvidas em situação de violência e seus familiares, e analisar o papel social do agressor/protetor no círculo da violência. Estudo quantitativo descritivo foi desenvolvido no Ambulatório da Família de um Hospital do Rio de Janeiro, entre 2006 e 2007. Dados do prontuário de 44 crianças demonstraram intensa relação entre pobreza, baixa escolaridade e gênero na matriz social da violência. Houve maior registro de meninos (64%) expostos a violência do que meni...

Reactor Vessel Surveillance Program for Advanced Reactor

Energy Technology Data Exchange (ETDEWEB)

Jeong, Kyeong-Hoon; Kim, Tae-Wan; Lee, Gyu-Mahn; Kim, Jong-Wook; Park, Keun-Bae; Kim, Keung-Koo

2008-10-15

This report provides the design requirements of an integral type reactor vessel surveillance program for an integral type reactor in accordance with the requirements of Korean MEST (Ministry of Education, Science and Technology Development) Notice 2008-18. This report covers the requirements for the design of surveillance capsule assemblies including their test specimens, test block materials, handling tools, and monitors of the surveillance capsule neutron fluence and temperature. In addition, this report provides design requirements for the program for irradiation surveillance of reactor vessel materials, a layout of specimens and monitors in the surveillance capsule, procedures of installation and retrieval of the surveillance capsule assemblies, and the layout of the surveillance capsule assemblies in the reactor.

Estruturação elusiva de atos e negócios jurídicos no direito tributário brasileiro: limites ao planejamento tributário 

OpenAIRE

Leonardo Aguirra de Andrade

2014-01-01

O presente estudo analisa os contornos da estruturação elusiva de atos e negócios jurídicos no Direito Tributário brasileiro. Inicialmente, busca-se definir o conceito de planejamento tributário, abordando as diferentes noções de elisão fiscal, elusão fiscal e evasão fiscal, bem como os critérios contemplados pela doutrina brasileira de Direito Tributário para distinguir as condutas oponíveis e inoponíveis ao Fisco. Para melhor compreensão dos limites da conduta elusiva, examinam-se os princí...

Para que servem os inventários de fauna?

Directory of Open Access Journals (Sweden)

Luís Fábio Silveira

2010-01-01

Full Text Available Inventários de fauna acessam diretamente a diversidade de uma localidade, em um determinado espaço e tempo. Os dados primários gerados pelos inventários compõem uma das ferramentas mais importantes na tomada de decisões a respeito do manejo de áreas naturais. Entretanto, vários problemas têm sido observados em diversos níveis relacionados aos inventários de fauna no Brasil e vão desde a formação de recursos humanos até a ausência de padronização, de desenho experimental e de seleção de métodos inadequados. São apresentados estudos de caso com mamíferos, répteis, anfíbios e peixes, nos quais são discutidos problemas como variabilidade temporal e métodos para detecção de fauna terrestre, sugerindo que tanto os inventários quanto os programas de monitoramento devam se estender por prazos maiores e que os inventários devem incluir diferentes metodologias para que os seus objetivos sejam plenamente alcançados.Inventories of fauna directly access the diversity of a locality in a certain period of time. The primary data generated by these inventories comprise one of the most important steps in decisions making regarding the management of natural areas. However, several problems have been observed at different levels related to inventories of fauna in Brazil, and range from the training of humans to the lack of standardization of experimental design and selection of inappropriate methods. We present case studies of mammals, reptiles, amphibians and fishes, where they discussed issues such temporal variability and methods for detection of terrestrial fauna, suggesting that both inventories and monitoring programs should be extended for longer terms and that inventories should include different methodologies to ensure that their goals are fully achieved.

Meliponiculture in Rio Grande do Norte

Directory of Open Access Journals (Sweden)

Ulysses Madureira Maia

2015-12-01

Full Text Available ABSTRACT. Maia U.M., Jaffe R., Carvalho A.T. & Imperatriz-Fonseca V.L. [Meliponiculture in Rio Grande do Norte.] Meliponicultura no Rio Grande do Norte. Revista Brasileira de Medicina Veterinária, 37(4:327-333, 2015. Departamento de Biologia, Faculdade de Filosofia, Ciências e Letras de Ribeirão Preto, Universidade de São Paulo, Avenida Bandeirantes, 3900, Monte Alegre, Ribeirão Preto, SP 14040-901, Brasil. E-mail: ummaia@usp.br This study aimed to assess the current status of stingless bee beekeeping (meliponiculture in the State of Rio Grande do Norte, Brazil, with the aid of structured questionnaires made during visits to beekeepers. The results were compared with a previous census made in the state and with a similar study from Australia. Meliponiculture in Rio Grande do Norte is still informal and little standardized. The activity has grown in recent years considering the mean number of nests per beekeeper. Most apiaries are formed of up to 50 colonies, usually distributed in the backyards of homes. Twelve species of stingless bees were reared in the state, and the most common was the “Jandaíra” bee (Melipona subnitida, whose honey is considered medicinal. While many beekeepers already know the importance of bees as pollinators, stingless bees are still not used for crop pollination. Compared to a recent analysis of beekeeping in Australia, meliponiculture in Brazil is more traditional, honey is the main product and the number of colonies per beekeeper is much higher. Our results highlight the need to reinforce knowledge about bees and promote specific training aimed at improving and standardizing management practices.

“ÁGUA VIRA SAL LÁ NA SALINA”: O GLOSSÁRIO DOS TERMOS DO SAL NO RIO GRANDE DO NORTE NUMA PERSPECTIVA SOCIOTERMINOLÓGICA

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Moisés Batista da Silva

2016-01-01

Full Text Available O presente trabalho tem como objetivo apresentarresultados da pesquisa sobre os termos usados na Indústriado sal, em três municípios que fazem parte da região salineirado Rio Grande do Norte. Primeiramente, abordamosas diferentes ciências do Léxico estudadas por Boutin--Quesnel (1985, Barbosa (1994,1995, Barros (2004,dando ênfase maior nas orientações teórico-metodológicasda Socioterminologia (FAULSTICH, 1995, 1996, 1998,2006. Em seguida, expomos os procedimentos tanto dametodologia de campo quanto da metodologia da organizaçãodo Glossário da Terminologia do Sal - GLOSSAL(SILVA, 2007. Depois, apresentamos uma amostra dosverbetes, as análises feitas a partir desse repertório e, porfim, as considerações finais quanto aos fatos linguísticos,observados nesse glossário. Desse modo, essa pesquisa sejustifica por possibilitar a divulgação de um produto terminográficodestinado, não só aos especialistas e pesquisadoresdas Ciências do Léxico, como também ao grandepúblico e aos interessados em aprofundar seus estudos naterminologia do sal.Palavras-chave: Sal. Indústria do Sal. Terminologia. Socioterminologia.Glossário.

The nuclear reactor strategy between fast breeder reactors and advanced pressurized water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1983-01-01

A nuclear reactor strategy between fast breeder reactors (FBRs) and advanced pressurized water reactors (APWRs) is being studied. The principal idea of this strategy is that the discharged plutonium from light water reactors (LWRs) provides the inventories of the FBRs and the high-converter APWRs, whereby the LWRs are installed according to the derivative of a logistical S curve. Special emphasis is given to the dynamics of reaching an asymptotic symbiosis between FBRs and APWRs. The main conclusion is that if a symbiotic APWR-FBR family with an asymptotic total power level in the terawatt range is to exist in about half a century from now, we need a large number of FBRs already in an early phase

Increased SRP reactor power

International Nuclear Information System (INIS)

MacAfee, I.M.

1983-01-01

Major changes in the current reactor hydraulic systems could be made to achieve a total of about 1500 MW increase of reactor power for P, K, and C reactors. The changes would be to install new, larger heat exchangers in the reactor buildings to increase heat transfer area about 24%, to increase H 2 O flow about 30% per reactor, to increase D 2 O flow 15 to 18% per reactor, and increase reactor blanket gas pressure from 5 psig to 10 psig. The increased reactor power is possible because of reduced inlet temperature of reactor coolant, increased heat removal capacity, and increased operating pressure (larger margin from boiling). The 23% reactor power increase, after adjustment for increased off-line time for reactor reloading, will provide a 15% increase of production from P, K, and C reactors. Restart of L Reactor would increase SRP production 33%

Sedimentation in Rio La Venta Canyon in Netzahualcoyotl Reservoir, Chiapas, Mexico

Science.gov (United States)

de La Fuente, J. A.; Lisle, T.; Velasquez, J.; Allison, B. L.; Miller, A.

2002-12-01

Sedimentation of Rio La Venta as it enters the Netzahualcoyotl Reservoir in Chiapas, Mexico, threatens a unique part of the aquatic ecosystem. Rio La Venta enters the reservoir via a narrow canyon about 16 km long with spectacular, near-vertical limestone bluffs up to 320 m high and inhabited by the flora and fauna of a pristine tropical forest. Karst terrain underlies most of the Rio La Venta basin in the vicinity of the reservoir, while deeply weathered granitic terrain underlies the Rio Negro basin, and the headwaters of the Rio La Venta to the south. The Rio Negro joins Rio La Venta 3 km downstream of the upper limit of the reservoir and delivers the bulk of the total clastic sediment (mostly sand and finer material). The canyon and much of the contributing basin lie within the Reserva de la Biosfera, Selva El Ocote, administered by the Comision Nacional de Areas Naturales Protegidas, part of the Secretaria de Medioambiente y Recursos Naturales. The Klamath National Forest Forest has cooperated with its Mexican counterparts since 1993 in natural resource management, neo-tropical bird inventories, wildfire management, and more recently in watershed analyses. Rates of sedimentation are estimated from bathymetric surveys conducted in March, 2002. A longitudinal profile down the inundated canyon during a high reservoir level shows an inflection from a slope of 0.0017 to one of 0.0075 at 7.2 km downstream of the mouth of Rio Negro. The bed elevation at this point corresponds to the lowest reservoir level, suggesting that the gentler sloping bed upstream is formed by fluvial processes during drawdown and that downstream by pluvial processes. Using accounts that boats could access Rio Negro during low water levels in 1984, we estimate an annual sedimentation rate of roughly 3 million cubic meters per year. This suggests that boats might no longer be able to access the most spectacular section of canyon upstream of Rio Negro within a decade, depending on how the

Validade de indicadores de atividade física e comportamento sedentário da Pesquisa Nacional de Saúde do Escolar entre adolescentes do Rio de Janeiro, Brasil

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Letícia Ferreira Tavares

2014-09-01

Full Text Available Analisou-se a validade relativa dos indicadores de atividade física do questionário utilizado na Pesquisa Nacional de Saúde do Escolar (PeNSE entre adolescentes da cidade do Rio de Janeiro, Brasil. Foram estudados 174 alunos. Avaliaram-se os seguintes indicadores referentes ao tempo semanal acumulado com a prática de atividade física: ATIVO-300MIN (acumulou 300 minutos ou mais; ATIVO-150MIN (acumulou 150 minutos ou mais; INATIVO (não praticou atividade física. Também foram estudados os indicadores de comportamento sedentário referentes ao tempo diário despendido assistindo TV, jogando videogame e usando computador. Foram comparados os resultados do questionário e dos três recordatórios de 24 horas. Os resultados de ATIVO-300MIN, ATIVO-150MIN e INATIVO gerados pela PeNSE apresentaram alta acurácia. Esses indicadores tiveram melhor desempenho que os de comportamento sedentário, tanto em relação às estimativas de frequência quanto em relação à sensibilidade, especificidade e índice de acurácia. Os indicadores de atividade física da PeNSE apresentaram validade relativa satisfatória.

Indicação de exames pré-operatórios segundo critérios clínicos: necessidade de supervisão

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Aline Pallaoro Garcia

2014-01-01

Full Text Available Justificativa e objetivos: a solicitação indiscriminada de exames complementares na avaliação pré-anestésica é comum na prática clínica e implica custos adicionais e a possibilidade de resultados falso-positivos. Os objetivos desta pesquisa foram analisar se os exames pré-operatórios em cirurgias eletivas são solicitados segundo critério clínico e avaliar os custos desnecessários para a instituição. Métodos: foram avaliadas as solicitações de exames pré-operatórios em pacientes adultos submetidos a cirurgias eletivas não cardíacas. Os exames foram solicitados pelos cirurgiões, conforme protocolo do Serviço de Anestesia. Foram avaliados dados demográficos, estado físico, comorbidades e tipo de exame complementar solicitado. Os exames feitos foram comparados com os exames indicados. O custo dos exames foi baseado na tabela Datasus. Resultados: foram avaliados 1.063 pacientes. Verificou-se que 41,9% dos exames feitos nos pacientes classificados como ASA I não estavam indicados. No grupo de risco ASA II foram feitos 442 exames (17,72% sem necessidade. Perceberam-se elevadas porcentagens na solicitação de hemograma, creatinina, coagulograma, raios X de tórax e ECG nos grupos ASA I-II. Apenas 40 (5,25% dos exames feitos no grupo ASA III não estavam indicados. Nos pacientes do grupo ASA IV, 22,5% dos exames necessários não foram feitos. Ressalta-se uma economia anual de 13% (R$1.923,13 caso os exames fossem feitos conforme o protocolo. Conclusões: os exames pré-operatórios nem sempre são solicitados de acordo com critérios clínicos, o que resulta em maiores custos para a instituição.

Tokamak reactor studies

International Nuclear Information System (INIS)

Baker, C.C.

1981-01-01

This paper presents an overview of tokamak reactor studies with particular attention to commercial reactor concepts developed within the last three years. Emphasis is placed on DT fueled reactors for electricity production. A brief history of tokamak reactor studies is presented. The STARFIRE, NUWMAK, and HFCTR studies are highlighted. Recent developments that have increased the commercial attractiveness of tokamak reactor designs are discussed. These developments include smaller plant sizes, higher first wall loadings, improved maintenance concepts, steady-state operation, non-divertor particle control, and improved reactor safety features

Computerized reactor monitor and control for research reactors

International Nuclear Information System (INIS)

Buerger, L.; Vegh, E.

1981-09-01

The computerized process control system developed in the Central Research Institute for Physics, Budapest, Hungary, is described together with its special applications at research reactors. The nuclear power of the Hungarian research reactor is controlled by this computerized system, too, while in Lybia many interesting reactor-hpysical calculations are built into the computerized monitor system. (author)

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

Energy Technology Data Exchange (ETDEWEB)

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

2016-06-15

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

Nuclear Reactor Physics

Science.gov (United States)

Stacey, Weston M.

2001-02-01

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

Reactor. Mind picture of the future Jules-Horowitz Reactor (RHJ)

International Nuclear Information System (INIS)

Eustache, S.

1999-01-01

This paper gives information about the future research reactor, named Reactor Jules-Horowitz (RJH). This irradiation reactor will be placed at industrialists disposal, for research concerning the competitiveness and the safety french electro-nuclear park. Principles and innovations are detailed. This reactor will respect the ALARA principle (as low as reasonably achievable). (A.L.B.)

Rio Chama Floodplain Management Study

Data.gov (United States)

Earth Data Analysis Center, University of New Mexico — The Village of Chama requested the Soil Conservation Service, through the Upper Chama Soil and Water Conservation District, to conduct a study of the Rio Chama and...

Energy balance of the Rio de Janeiro State - 1980/1994

International Nuclear Information System (INIS)

1995-01-01

This document informs the energetic balance for Rio de Janeiro State -1980/1994, containing the energy fluxes from primary and secondary energy sources in the main sectors of Rio de Janeiro economy. 50 figs., 139 tabs

RIO EPICS device support application case study on an ion source control system (ISHP)

Energy Technology Data Exchange (ETDEWEB)

Sanz, Diego [UPM – Universidad Politécnica de Madrid, Madrid (Spain); Ruiz, Mariano, E-mail: mariano.ruiz@upm.es [UPM – Universidad Politécnica de Madrid, Madrid (Spain); Eguiraun, Mikel [Department of Electricity and Electronic, Faculty of Science and Technology, University of Basque Country, Bilbao (Spain); Arredondo, Iñigo [ESS Bilbao Consortium, Zamudio (Spain); Badillo, Inari; Jugo, Josu [Department of Electricity and Electronic, Faculty of Science and Technology, University of Basque Country, Bilbao (Spain); Vega, Jesús; Castro, Rodrigo [Asociación EURATOM/CIEMAT, Madrid (Spain)

2015-10-15

Highlights: • A use case example of RIO/FlexRIO design methodology is described. • Ion source device is controlled and monitored by means EPICS IOCs. • NIRIO EPICS device support demonstrates that is able to manage RIO devices. • Easy and fast deployment is possible using RIO/FlexRIO design methodology using NIRIO-EDS. • RIO/FlexRIO technology and EPICS are a good combination for support large scale experiments in fusion environments. - Abstract: Experimental Physics and Industrial Control System (EPICS) is a software tool that during last years has become relevant as a main framework to deploy distributed control systems in large scientific environments. At the moment, ESS Bilbao uses this middleware to perform the control of their Ion Source Hydrogen Positive (ISHP) project. The implementation of the control system was based on: PXI Real Time controllers using the LabVIEW-RT and LabVIEW-EPICS tools; and RIO devices based on Field-Programmable Gate Array (FPGA) technology. Intended to provide a full compliant EPICS IOCs for RIO devices and to avoid additional efforts on the system maintainability, a migration of the current system to a derivative Red Hat Linux (CentOS) environment has been conducted. This paper presents a real application case study for using the NIRIO EPICS device support (NIRIO-EDS) to give support to the ISHP. Although RIO FPGA configurations are particular solutions for ISHP performance, the NIRIO-EDS has permitted the control and monitoring of devices by applying a well-defined design methodology into the previous FPGA configuration for RIO/FlexRIO devices. This methodology has permitted a fast and easy deployment for the new robust, scalable and maintainable software to support RIO devices into the ISHP control architecture.

A pertinência da arquitetura no marketing imobiliário

OpenAIRE

Silva, António Augusto Ferreira da

2013-01-01

Mestrado Integrado em Arquitectura Exame público realizado em 17 de Outubro de 2013 A habitação surge no mercado atual como um produto repetitivo na oferta e qualidade residencial, resultado da ausência de investigação por parte dos intervenientes no setor imobiliário, demonstrando uma abordagem pouco real das verdadeiras necessidades e desejos dos compradores do produto imobiliário. Num setor imobiliário cada vez mais competitivo, a análise da oferta habitacional torna-se fator esse...

The analysis for inventory of experimental reactor high temperature gas reactor type

International Nuclear Information System (INIS)

Sri Kuntjoro; Pande Made Udiyani

2016-01-01

Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 Bq, 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term and it

The Link between Protein Kinase CK2 and Atypical Kinase Rio1

Directory of Open Access Journals (Sweden)

Konrad Kubiński

2017-02-01

Full Text Available The atypical kinase Rio1 is widespread in many organisms, ranging from Archaebacteria to humans, and is an essential factor in ribosome biogenesis. Little is known about the protein substrates of the enzyme and small-molecule inhibitors of the kinase. Protein kinase CK2 was the first interaction partner of Rio1, identified in yeast cells. The enzyme from various sources undergoes CK2-mediated phosphorylation at several sites and this modification regulates the activity of Rio1. The aim of this review is to present studies of the relationship between the two different kinases, with respect to CK2-mediated phosphorylation of Rio1, regulation of Rio1 activity, and similar susceptibility of the kinases to benzimidazole inhibitors.

FBR type reactors

International Nuclear Information System (INIS)

Suzuoki, Akira; Yamakawa, Masanori.

1985-01-01

Purpose: To enable safety and reliable after-heat removal from a reactor core. Constitution: During ordinary operation of a FBR type reactor, sodium coolants heated to a high temperature in a reactor core are exhausted therefrom, collide against the reactor core upper mechanisms to radially change the flowing direction and then enter between each of the guide vanes. In the case if a main recycling pump is failed and stopped during reactor operation and the recycling force is eliminated, the swirling stream of sodium that has been resulted by the flow guide mechanism during normal reactor operation is continuously maintained within a plenum at a high temperature. Accordingly, the sodium recycling force in the coolant flow channels within the reactor vessel can surely be maintained for a long period of time due to the centrifugal force of the sodium swirling stream. In this way, since the reactor core recycling flow rate can be secured even after the stopping of the main recycling pump, after-heat from the reactor core can safely and surely be removed. (Seki, T.)

FBR type reactor

International Nuclear Information System (INIS)

Hayase, Tamotsu.

1991-01-01

The present invention concerns an FBR type reactor in which transuranium elements are eliminated by nuclear conversion. There are loaded reactor core fuels being charged with mixed oxides of plutonium and uranium, and blanket fuels mainly comprising depleted uranium. Further, liquid sodium is used as coolants. As transuranium elements, isotope elements of neptunium, americium and curium contained in wastes taken out from light water reactors or the composition thereof are used. The reactor core comprises a region with a greater mixing ratio and a region with a less mixing ratio of the transuranium elements. The mixing ratio of the transuranium elements is made greater for the fuels in the reactor core region at the boundary with the blanket of great neutron leakage. With such a constitution, since the positive reactivity value at the reactor core central portion is small in the Na void reactivity distribution in the reactor core, the positive reactivity is small upon Na boiling in the reactor core central region upon occurrence of imaginable accident, to attain reactor safety. (I.N.)

Twitteratura: aproximando letramento literário e letramento digital

Directory of Open Access Journals (Sweden)

Vinicius Carvalho Pereira

2017-07-01

Full Text Available As práticas de letramento literário da escola brasileira voltam-se majoritariamente para textos em suporte impresso, embora parte significativa da produção literária contemporânea em língua portuguesa venha sendo feita em suporte eletrônico ou digital. Tal disjunção se deve, entre outros fatores, à predominância de obras canônicas no currículo escolar, à natureza impressa do livro didático e a um entendimento restrito do que seja o texto literário. Por outro lado, assistimos ao uso crescente de aparelhos celulares e smartphones em sala de aula, raramente articulado ao processo de ensino-aprendizagem, ainda que esses dispositivos possam integrar práticas de letramento literário na esfera digital. No presente artigo, discutem-se questões teórico-metodológicas acerca do uso, em sala de aula, de celulares e smartphones para o trabalho com um gênero literário emergente: a Twitteratura. Da página à tela, do ponto ao pixel, novos entendimentos do literário podem ser introduzidos no currículo escolar, propiciando uma compreensão mais ampla sobre as relações sobredeterminantes entre linguagem, sociedade e tecnologia.

Processo sucessório na governança de organizações familiares: um estudo exploratório nas “Mehores Empresas"

Directory of Open Access Journals (Sweden)

Rodrigo Silva

2014-05-01

Full Text Available Este artigo se propõe a levantar práticas por meio das quais organizações familiaresenfrentam o desafio da sucessão dos seus profissionais. Para o cumprimento desseobjetivo foi realizada uma pesquisa exploratória de levantamento de práticas relativas aoplanejamento sucessório entre as Melhores Empresas para Você Trabalhar no Brasil. Como intuito de levantar as principais características do planejamento sucessório adotadas pelasorganizações familiares, foi realizada uma pesquisa de levantamento exploratória. Para arealização das análises do presente trabalho, foram consideradas as ações de Dutra (2010para estruturação do planejamento sucessório. Em síntese, a literatura evidencia que emboraa sucessão constitua evento de fundamental importância para a continuidade dos negócios esobrevivência das empresas familiares, ela poderá tornar-se traumática, se não for conduzidade forma racional, o que demonstra a necessidade de tal processo se desenvolver através deplanejamento cuidadoso e racional, que procure levar em conta a ampla gama de fatores queo afetam. No caso das empresas familiares, nota-se o desafio de considerar as questõesemocionais e afetivos na discussão do planejamento sucessório. Constatou-se pouca atençãoaos aspectos emocionais do processo sucessório nas organizações familiares.

Aplicação do fluxo unitário da produção na manufatura do vestuário de moda

OpenAIRE

Chi Ming Wan

2016-01-01

O objetivo deste trabalho é discutir a aplicação do Fluxo Unitário da Produção (FUP) no processo de fabricação do vestuário de moda, com ênfase em produtos de moda feminina. Para tanto, foi realizada uma pesquisa de campo, por meio de estudo de caso, em empresa do setor. O resultado da pesquisa mostra que, apesar das particularidades do setor, como o baixo volume de produção, curto ciclo de vida do produto e grande diversidade de modelos, a aplicação do Fluxo Unitário da Produção na manufatur...

Nuclear reactor

International Nuclear Information System (INIS)

Tilliette, Z.

1975-01-01

A description is given of a nuclear reactor and especially a high-temperature reactor in which provision is made within a pressure vessel for a main cavity containing the reactor core and a series of vertical cylindrical pods arranged in spaced relation around the main cavity and each adapted to communicate with the cavity through two collector ducts or headers for the primary fluid which flows downwards through the reactor core. Each pod contains two superposed steam-generator and circulator sets disposed in substantially symmetrical relation on each side of the hot primary-fluid header which conveys the primary fluid from the reactor cavity to the pod, the circulators of both sets being mounted respectively at the bottom and top ends of the pod

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

Energy Technology Data Exchange (ETDEWEB)

Chang, Y.I.

1992-07-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing.

A next-generation reactor concept: The Integral Fast Reactor (IFR)

International Nuclear Information System (INIS)

Chang, Y.I.

1992-01-01

The Integral Fast Reactor (IFR) is an advanced liquid metal reactor concept being developed at Argonne National Laboratory as reactor technology for the 21st century. It seeks to specifically exploit the inherent properties of liquid metal cooling and metallic fuel in a way that leads to substantial improvements in the characteristics of the complete reactor system, in particular passive safety and waste management. The IFR concept consists of four technical features: (1) liquid sodium cooling, (2) pool-type reactor configuration, (3) metallic fuel, and (4) fuel cycle closure based on pyroprocessing

Corpo, mito e imaginário nos postais das praias cariocas

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Euler David de Siqueira

Full Text Available "Cidade Maravilhosa", "capital cultural", o Rio de Janeiro é ícone do Brasil em uma série de discursos, entre eles o turístico. As bancas de jornal da cidade exibem cartões-postais com fotos que exploram a imagem do corpo feminino na orla carioca e a mostram como imagem da cidade. A partir da análise de uma amostra intencional e não-probabilística de exemplares dessa mídia, o objetivo deste trabalho é o de estudar a relação entre o corpo e o espaço urbano na construção do imaginário sobre a cidade do Rio de Janeiro. Entre alguns dos resultados encontrados, observa-se a construção de um imaginário que reforça antigos clichês em que a cidade do Rio de Janeiro e seus personagens são apresentados como tendo uma natureza sensual, quente e festiva.

Elaboração de questionário de frequência alimentar semiquantitativo para adolescentes da região metropolitana do Rio de Janeiro, Brasil Development of a semiquantitative food frequency questionnaire for adolescents from the Rio de Janeiro metropolitan area, Brazil

Directory of Open Access Journals (Sweden)

Marina Campos Araujo

2010-04-01

Full Text Available OBJETIVO: Descrever a elaboração de um questionário de frequência alimentar para adolescentes do Rio de Janeiro, Brasil. MÉTODOS: Para seleção dos itens alimentares incluídos no questionário de frequência alimentar, utilizaram-se dados de três dias de registro alimentar obtidos em uma amostra de 430 estudantes, na faixa etária de 12 a 19 anos, da rede de ensino estadual de Niterói, Rio de Janeiro. Foram incluídos os itens alimentares mais citados nos registros e que contribuíram com 95% do consumo de energia e nutrientes dos registros alimentares. As porções de referência foram as mais frequentemente referidas nos registros do estudo de base. As opções de frequência foram definidas de forma diferenciada para os diversos itens do questionário. RESULTADOS: Nos registros foram listados 306 alimentos, dos quais 249 itens foram incluídos no questionário, isoladamente ou agrupados, compondo uma lista de 90 itens. Os 14 itens alimentares mais consumidos por adolescentes do Rio de Janeiro, nesse estudo e em estudo anterior, foram associados a oito opções de frequência de consumo; 18 itens alimentares foram acoplados a sete opções de frequência e para 58 itens foram definidas cinco opções de frequência. CONCLUSÃO: O estudo permitiu a elaboração do questionário de frequência alimentar para adolescentes da Região Metropolitana do Rio de Janeiro, o qual será submetido às análises de reprodutibilidade e validade. Este questionário representa um instrumento valioso para pesquisas epidemiológicas que investiguem o consumo alimentar de adolescentes.OBJECTIVE: The objective of this study was to describe the development of a food frequency questionnaire for adolescents from the Rio de Janeiro metropolitan area, Brazil. METHODS: The selection of food items included in the questionnaire was done by recording the foods consumed during 3 days by 430 students aged 12 to 19 years from the public schools of Niterói (RJ Brasil

Thai research reactor

International Nuclear Information System (INIS)

Aramrattana, M.

1987-01-01

The Office of Atomic Energy for Peace (OAEP) was established in 1962, as a reactor center, by the virtue of the Atomic Energy for Peace Act, under operational policy and authority of the Thai Atomic Energy for Peace Commission (TAEPC); and under administration of Ministry of Science, Technology and Energy. It owns and operates the only Thai Research Reactor (TRR-1/M1). The TRR-1/M1 is a mixed reactor system constituting of the old MTR type swimming pool, irradiation facilities and cooling system; and TRIGA Mark III core and control instrumentation. The general performance of TRR-1/M1 is summarized in Table I. The safe operation of TRR-1/M1 is regulated by Reactor Safety Committee (RSC), established under TAEPC, and Health Physics Group of OAEP. The RCS has responsibility and duty to review of and make recommendations on Reactor Standing Orders, Reactor Operation Procedures, Reactor Core Loading and Requests for Reactor Experiments. In addition,there also exist of Emergency Procedures which is administered by OAEP. The Reactor Operation Procedures constitute of reactor operating procedures, system operating procedures and reactor maintenance procedures. At the level of reactor routine operating procedures, there is a set of Specifications on Safety and Operation Limits and Code of Practice from which reactor shift supervisor and operators must follow in order to assure the safe operation of TRR-1/M1. Table II is the summary of such specifications. The OAEP is now upgrading certain major components of the TRR-1/M1 such as the cooling system, the ventilation system and monitoring equipment to ensure their adequately safe and reliable performance under normal and emergency conditions. Furthermore, the International Atomic Energy Agency has been providing assistance in areas of operation and maintenance and safety analysis. (author)

Proposed Advanced Reactor Adaptation of the Standard Review Plan NUREG-0800 Chapter 4 (Reactor) for Sodium-Cooled Fast Reactors and Modular High-Temperature Gas-Cooled Reactors

Energy Technology Data Exchange (ETDEWEB)

Belles, Randy [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Poore, III, Willis P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Brown, Nicholas R. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Flanagan, George F. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Holbrook, Mark [Idaho National Lab. (INL), Idaho Falls, ID (United States); Moe, Wayne [Idaho National Lab. (INL), Idaho Falls, ID (United States); Sofu, Tanju [Argonne National Lab. (ANL), Argonne, IL (United States)

2017-03-01

This report proposes adaptation of the previous regulatory gap analysis in Chapter 4 (Reactor) of NUREG 0800, Standard Review Plan (SRP) for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR [Light Water Reactor] Edition. The proposed adaptation would result in a Chapter 4 review plan applicable to certain advanced reactors. This report addresses two technologies: the sodium-cooled fast reactor (SFR) and the modular high temperature gas-cooled reactor (mHTGR). SRP Chapter 4, which addresses reactor components, was selected for adaptation because of the possible significant differences in advanced non-light water reactor (non-LWR) technologies compared with the current LWR-based description in Chapter 4. SFR and mHTGR technologies were chosen for this gap analysis because of their diverse designs and the availability of significant historical design detail.

Nuclear reactor instrumentation at research reactor renewal

International Nuclear Information System (INIS)

Baers, B.; Pellionisz, P.

1981-10-01

The paper overviews the state-of-the-art of research reactor renewals. As a case study the instrumentation reconstruction of the Finnish 250 kW TRIGA reactor is described, with particular emphasis on the nuclear control instrumentation and equipment which has been developed and manufactured by the Central Research Institute for Physics, Budapest. Beside the presentation of the nuclear instrument family developed primarily for research reactor reconstructions, the quality assurance policy conducted during the manufacturing process is also discussed. (author)

Relatório integrador da actividade profissional

OpenAIRE

Oliveira, Maria João Belo

2015-01-01

Relatório integrador da atividade profissional para a obtenção do Grau de Mestre em Tecnologia Alimentar, na Escola Superior Agrária, do Instituto Politécnico de Santarém A informação apresentada neste relatório pretende demonstrar como algumas das competências adquiridas ao longo da formação académica foram aplicadas e desenvolvidas em contexto profissional. São apresentadas as empresas onde a autora colaborou, descrevendo-se as atividades desenvolvidas. A autora obteve em 199...

Reactor System Design

International Nuclear Information System (INIS)

Chi, S. K.; Kim, G. K.; Yeo, J. W.

2006-08-01

SMART NPP(Nuclear Power Plant) has been developed for duel purpose, electricity generation and energy supply for seawater desalination. The objective of this project IS to design the reactor system of SMART pilot plant(SMART-P) which will be built and operated for the integrated technology verification of SMART. SMART-P is an integral reactor in which primary components of reactor coolant system are enclosed in single pressure vessel without connecting pipes. The major components installed within a vessel includes a core, twelve steam generator cassettes, a low-temperature self pressurizer, twelve control rod drives, and two main coolant pumps. SMART-P reactor system design was categorized to the reactor coe design, fluid system design, reactor mechanical design, major component design and MMIS design. Reactor safety -analysis and performance analysis were performed for developed SMART=P reactor system. Also, the preparation of safety analysis report, and the technical support for licensing acquisition are performed

BWR type reactor

International Nuclear Information System (INIS)

Watanabe, Shoichi

1983-01-01

Purpose : To flatten the radial power distribution in the reactor core thereby improve the thermal performance of the reactor core by making the moderator-fuel ratio of fuel assemblies different depending on their position in the reactor core. Constitution : The volume of fuels disposed in the peripheral area of the reactor core is decreased by the increase of the volume of moderators in fuel assemblies disposed in the peripheral area of the reactor core to thereby make the moderator-fuel volume greater in the peripheral area than that in the central area. The moderator-fuel ratio adjustment is attained by making the number of water rods greater, decreasing the diameter of fuel pellets or decreasing the number of fuel pins in fuel assemblies disposed at the peripheral area of the reactor core as compared with fuel assemblies disposed at the central area of the reactor core. In this way, the infinite multiplication factors of fuels can be increased to thereby improve the reactor core performance. (Aizawa, K.)

Prevention device for rapid reactor core shutdown in BWR type reactors

International Nuclear Information System (INIS)

Koshi, Yuji; Karatsu, Hiroyuki.

1986-01-01

Purpose: To surely prevent rapid shutdown of a nuclear reactor upon partial load interruption due to rapid increase in the system frequency. Constitution: If a partial load interruption greater than the sum of the turbine by-pass valve capacity and the load setting bias portion is applied in a BWR type power plant, the amount of main steams issued from the reactor is decreased, the thermal input/output balance of the reactor is lost, the reactor pressure is increased, the void is collapsed, the neutron fluxes are increased and the reactor power rises to generate rapid reactor shutdown. In view of the above, the turbine speed signal is compared with a speed setting value in a recycling flowrate control device and the recycling pump is controlled to decrease the recycling flowrate in order to compensate the increase in the neutron fluxes accompanying the reactor power up. In this way, transient changes in the reactor core pressure and the neutron fluxes are kept within a setting point for the rapid reactor shutdown operation thereby enabling to continue the plant operation. (Horiuchi, T.)

Reactor core of nuclear reactor

International Nuclear Information System (INIS)

Sasagawa, Masaru; Masuda, Hiroyuki; Mogi, Toshihiko; Kanazawa, Nobuhiro.

1994-01-01

In a reactor core, a fuel inventory at an outer peripheral region is made smaller than that at a central region. Fuel assemblies comprising a small number of large-diameter fuel rods are used at the central region and fuel assemblies comprising a great number of smalldiameter fuel rods are used at the outer peripheral region. Since a burning degradation rate of the fuels at the outer peripheral region can be increased, the burning degradation rate at the infinite multiplication factor of fuels at the outer region can substantially be made identical with that of the fuels in the inner region. As a result, the power distribution in the direction of the reactor core can be flattened throughout the entire period of the burning cycle. Further, it is also possible to make the degradation rate of fuels at the outer region substantially identical with that of fuels at the inner side. A power peak formed at the outer circumferential portion of the reactor core of advanced burning can be lowered to improve the fuel integrity, and also improve the reactor safety and operation efficiency. (N.H.)

O Barão do Rio Branco opina sobre o Marechal Deodoro

Directory of Open Access Journals (Sweden)

E. Bradford Burns

1967-06-01

Full Text Available O Barão do Rio Branco era partidário dedicado da monarquia. Herdou essa convicção de seu ilustre pai, um dos maiores estadistas do Império; e êle mesmo serviu com muito zêlo e dedicação ao Imperador quando na Europa.

Características de repositório educacional aberto para usuários de língua brasileira de sinais

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Romario Antunes da Silva

Full Text Available O objetivo desse artigo é identificar as características que um repositório educacional aberto deve apresentar para atender as necessidade de informação dos alunos surdos e ouvintes do curso Letras Libras na modalidade a distância da Universidade Federal de Santa Catarina. Os objetivos específicos foram: a descrever o perfil dos alunos surdos e ouvintes; b examinar o uso das tecnologias da informação por esses alunos; e c identificar os documentos que um repositório deve apresentar para atender as necessidades de informação desses alunos. A pesquisa é exploratória, descritiva e qualitativo-quantitativa, e a análise foi realizada com estatística descritiva e análise de conteúdo. Conclui-se que os alunos utilizam o e-mail, as listas de discussão, o Messenger, ferramentas para compartilhamento de vídeos e os sites para surdos. Os alunos consideram muito importantes os processadores de texto, Messenger, Movie Maker, Media Player e planilhas para cálculo. Os alunos surdos consideram como documentos mais relevantes as videoaulas, dicionários e apostilas, e os alunos ouvintes, as videoaulas, os livros e as apostilas. O tipo de conteúdo requisitado são notícias sobre surdos, língua brasileira de sinais, tradução, tecnologia, linguística, aprendizagem do português, interpretação médico-jurídica e cultura surda. Os suportes requisitados para acesso à informação são os dicionários, vídeos, livros digitais e artigos. Os alunos preferem acessar as informações no repositório por meio de língua de sinais, legendas e em português.

Território e Rede da União do Vegetal

OpenAIRE

Morales Arteaga, Pamela Elizabeth

2016-01-01

Esta pesquisa trata do território e das redes geográficas da religião ayahusaqueira União do Vegetal, em Brasília. Busca-se interpretar os objetivos da pesquisa que foram; a construção do território da União do Vegetal, diferençando elementos relevantes do território; debatendo a hierarquização do grupo na sua atuação territorial e relacionando as percepções dos adeptos com suas práticas territoriais em rede. As hipóteses que nortearam o trabalho foram; A construção do território sagrado da U...

High-temperature and breeder reactors - economic nuclear reactors of the future

International Nuclear Information System (INIS)

Djalilzadeh, A.M.

1977-01-01

The thesis begins with a review of the theory of nuclear fission and sections on the basic technology of nuclear reactors and the development of the first generation of gas-cooled reactors applied to electricity generation. It then deals in some detail with currently available and suggested types of high temperature reactor and with some related subsidiary issues such as the coupling of different reactor systems and various schemes for combining nuclear reactors with chemical processes (hydrogenation, hydrogen production, etc.), going on to discuss breeder reactors and their application. Further sections deal with questions of cost, comparison of nuclear with coal- and oil-fired stations, system analysis of reactor systems and the effect of nuclear generation on electricity supply. (C.J.O.G.)

The passage from Rio.

Science.gov (United States)

Strong, M F

1992-01-01

The Secretary-General of the UN Conference on Environment and Development notes that after the Earth Summit in Rio de Janeiro discussions about the environment and development will differ from those prior to the Summit. These discussions must now incorporate problems of developing countries, poverty, inequalities, flow of resources to developing countries, and terms of trade. The Rio Declaration on Environment and Development consists of important tenets, but it must evolve into an Earth Charter to be endorsed on the 50th anniversary of the UN in 1965. The Summit's Plan of Action, Agenda 21, must also continue to evolve and, despite its shortcomings, is the most extensive and, if implemented, most effective international action ever approved by the international community. Financing the Agenda 21 initiatives remains to be decided. New possible sources of funding must be based n the polluter pays principle and may include new taxes, user charges, emission permits, and citizen funding. Even though the most serious problem in the 1990s is stabilization of atmospheric gases, the Rio agreement does not include targets or timetables. Governments must take united action immediately to reduce carbon dioxide emissions by at least 60%. 1 nation has not yet approved the convention on biological diversity. Governments also need to move forward on conventions on decertification and deforestation. They need to incorporate the global objectives of Agenda 21 into their own national policies and practices. This must also be done at the global, regional, organizational, local, and individual levels. The global community must also begin technology capacity building. The participatory process should also include nongovernmental organizations. Population growth must also slow dramatically to achieve sustainable development. The various participatory levels must consider elimination of poverty.

Heterogeneous reactors

International Nuclear Information System (INIS)

Moura Neto, C. de; Nair, R.P.K.

1979-08-01

The microscopic study of a cell is meant for the determination of the infinite multiplication factor of the cell, which is given by the four factor formula: K(infinite) = n(epsilon)pf. The analysis of an homogeneous reactor is similar to that of an heterogeneous reactor, but each factor of the four factor formula can not be calculated by the formulas developed in the case of an homogeneous reactor. A great number of methods was developed for the calculation of heterogeneous reactors and some of them are discussed. (Author) [pt

Nuclear reactor neutron shielding

Science.gov (United States)

Speaker, Daniel P; Neeley, Gary W; Inman, James B

2017-09-12

A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.

O aniversário do Pasquim: 22 anos em 5

Directory of Open Access Journals (Sweden)

Márcia Neme Buzalaf

2009-04-01

Full Text Available Resenha: Pasquim 40 anos: Edição Comemorativa. Rio de Janeiro: Desiderata, 2009, 40 p. e Antologia do Pasquim - volume III:1973-1974, de Jaguar e Sérgio Augusto (Org.. Rio de Janeiro: Desiderata, 2009, 376 p.

Bases epidemiológicas do Fator Acidentário Previdenciário Epidemiological foundations of the Accident Insurance Factor

Directory of Open Access Journals (Sweden)

Vilma Sousa Santana

2005-12-01

Full Text Available ANTECEDENTES: O Conselho Nacional de Previdência Social, por meio da Resolução No. 1.236 de 28/4/2004, aprovou uma nova metodologia para definição do valor das alíquotas de contribuição devidas por empresas para o financiamento de benefícios previdenciários relacionados aos riscos do trabalho. Esta metodologia baseia-se em um indicador denominado de Fator Acidentário Previdenciário, FAP, construído a partir do risco epidemiológico, estimado para cada ramo de atividade econômica. Como parte da sua estratégia de validação, o Ministério da Previdência Social decidiu pela avaliação da sua consistência epidemiológica. OBJETIVOS: Nesse estudo analisaram-se os propósitos, as fontes de informação, a natureza das medidas epidemiológicas empregadas e a metodologia da construção desse indicador, identificando-se as suas vantagens e limitações, aplicabilidade e impactos potenciais futuros. MÉTODOS: Análise documental da Resolução No. 1236 e do documento anexo. RESULTADOS: O FAP avança ao se pautar por critérios científicos transparentes que poderão permitir a redução das alíquotas quando houver efetiva melhoria das condições de trabalho, e conseqüentemente, da morbimortalidade entre trabalhadores. Supera as dificuldades relacionadas à definição e registro do nexo causal das doenças do trabalho ao considerá-las em sua totalidade, não se restringido às ocupacionais. Como prevê a redução de alíquotas com a melhoria das condições de saúde dos trabalhadores poderá contribuir para uma mais efetiva atuação dos empregadores na prevenção. CONCLUSÕES: É necessário o acompanhamento contínuo e sistemático da aplicação do FAP, com ampla participação da sociedade, revisando-o e ajustando-o aos diferentes cenários econômicos, sociais e de saúde do País, atentando-se para o seu impacto sobre a arrecadação e contas da Previdência Social.BACKGROUND: The Brazilian National Social Insurance

Fast breeder reactors

International Nuclear Information System (INIS)

Heinzel, V.

1975-01-01

The author gives a survey of 'fast breeder reactors'. In detail the process of breeding, the reasons for the development of fast breeders, the possible breeder reactors, the design criteria, fuels, cladding, coolant, and safety aspects are reported on. Design data of some experimental reactors already in operation are summarized in stabular form. 300 MWe Prototype-Reactors SNR-300 and PFR are explained in detail and data of KWU helium-cooled fast breeder reactors are given. (HR) [de

Reactor container

International Nuclear Information System (INIS)

Shibata, Satoru; Kawashima, Hiroaki

1984-01-01

Purpose: To optimize the temperature distribution of the reactor container so as to moderate the thermal stress distribution on the reactor wall of LMFBR type reactor. Constitution: A good heat conductor (made of Al or Cu) is appended on the outer side of the reactor container wall from below the liquid level to the lower face of a deck plate. Further, heat insulators are disposed to the outside of the good heat conductor. Furthermore, a gas-cooling duct is circumferentially disposed at the contact portion between the good heat conductor and the deck plate around the reactor container. This enables to flow the cold heat from the liquid metal rapidly through the good heat conductor to the cooling duct and allows to maintain the temperature distribution on the reactor wall substantially linear even with the abrupt temperature change in the liquid metal. Further, by appending the good heat conductor covered with inactive metals not only on the outer side but also on the inside of the reactor wall to introduce the heat near the liquid level to the upper portion and escape the same to the cooling layer below the roof slab, the effect can be improved further. (Ikeda, J.)

Reactor technology: power conversion systems and reactor operation and maintenance

International Nuclear Information System (INIS)

Powell, J.R.

1977-01-01

The use of advanced fuels permits the use of coolants (organic, high pressure helium) that result in power conversion systems with good thermal efficiency and relatively low cost. Water coolant would significantly reduce thermal efficiency, while lithium and salt coolants, which have been proposed for DT reactors, will have comparable power conversion efficiencies, but will probably be significantly more expensive. Helium cooled blankets with direct gas turbine power conversion cycles can also be used with DT reactors, but activation problems will be more severe, and the portion of blanket power in the metallic structure will probably not be available for the direct cycle, because of temperature limitations. A very important potential advantage of advanced fuel reactors over DT fusion reactors is the possibility of easier blanket maintenance and reduced down time for replacement. If unexpected leaks occur, in most cases the leaking circuit can be shut off and a redundant cooling curcuit will take over the thermal load. With the D-He 3 reactor, it appears practical to do this while the reactor is operating, as long as the leak is small enough not to shut down the reactor. Redundancy for Cat-D reactors has not been explored in detail, but appears feasible in principle. The idea of mobile units operating in the reactor chamber for service and maintenance of radioactive elements is explored

Fusion-fission hybrid reactors

International Nuclear Information System (INIS)

Greenspan, E.

1984-01-01

This chapter discusses the range of characteristics attainable from hybrid reactor blankets; blanket design considerations; hybrid reactor designs; alternative fuel hybrid reactors; multi-purpose hybrid reactors; and hybrid reactors and the energy economy. Hybrid reactors are driven by a fusion neutron source and include fertile and/or fissile material. The fusion component provides a copious source of fusion neutrons which interact with a subcritical fission component located adjacent to the plasma or pellet chamber. Fissile fuel and/or energy are the main products of hybrid reactors. Topics include high F/M blankets, the fissile (and tritium) breeding ratio, effects of composition on blanket properties, geometrical considerations, power density and first wall loading, variations of blanket properties with irradiation, thermal-hydraulic and mechanical design considerations, safety considerations, tokamak hybrid reactors, tandem-mirror hybrid reactors, inertial confinement hybrid reactors, fusion neutron sources, fissile-fuel and energy production ability, simultaneous production of combustible and fissile fuels, fusion reactors for waste transmutation and fissile breeding, nuclear pumped laser hybrid reactors, Hybrid Fuel Factories (HFFs), and scenarios for hybrid contribution. The appendix offers hybrid reactor fundamentals. Numerous references are provided

Reactor protection systems for the Replacement Research Reactor, ANSTO

International Nuclear Information System (INIS)

Morris, C.R.

2003-01-01

The 20-MW Replacement Research Reactor Project which is currently under construction at ANSTO will have a combination of a state of the art triplicated computer based reactor protection system, and a fully independent, and diverse, triplicated analogue reactor protection system, that has been in use in the nuclear industry, for many decades. The First Reactor Protection System (FRPS) consists of a Triconex triplicated modular redundant system that has recently been approved by the USNRC for use in the USA?s power reactor program. The Second Reactor Protection System is a hardwired analogue system supplied by Foxboro, the Spec 200 system, which is also Class1E qualified. The FRPS is used to drop the control rods when its safety parameter setpoints have been reached. The SRPS is used to drain the reflector tank and since this operation would result in a reactor poison out due to the time it would take to refill the tank the FRPS trip setpoints are more limiting. The FRPS and SRPS have limited hardwired indications on the control panels in the main control room (MCR) and emergency control centre (ECC), however all FRPS and SRPS parameters are capable of being displayed on the reactor control and monitoring system (RCMS) video display units. The RCMS is a Foxboro Series I/A control system which is used for plant control and monitoring and as a protection system for the cold neutron source. This paper will provide technical information on both systems, their trip logics, their interconnections with each other, and their integration into the reactor control and monitoring system and control panels. (author)

Motivações de candidatos e voluntários na Cidade Viva

Directory of Open Access Journals (Sweden)

Jéssika Kadidja de Oliveira Medeiros

2017-07-01

Full Text Available O trabalho voluntário é a força das organizações da sociedade civil. Existem diferenças entre o trabalho voluntário e o formal, como a remuneração e o tempo destinado ao desempenho das atividades. Ao contrário de trabalhadores formais, voluntários não recebem pagamento para o desempenho de funções. Logo, teorias motivacionais desenvolvidas numa perspectiva de trabalho formal não devem ser aplicadas a este grupo. Esse estudo identificou motivações apresentadas pelos candidatos a voluntários e atuais voluntários da Fundação Cidade Viva em João Pessoa. Quanto aos resultados, verifica-se predominância do perfil altruísta em ambas as fases utilizadas do modelo. Ainda, o perfil egoísta, foi o menos apresentado pelos respondentes da pesquisa. Outros resultados, relativos ao desligamento da atividade voluntária na Fundação, foram bastante inconclusivos.

Reactor container

International Nuclear Information System (INIS)

Fukazawa, Masanori.

1991-01-01

A system for controlling combustible gases, it has been constituted at present such that the combustible gases are controlled by exhausting them to the wet well of a reactor container. In this system, however, there has been a problem, in a reactor container having plenums in addition to the wet well and the dry well, that the combustible gases in such plenums can not be controlled. In view of the above, in the present invention, suction ports or exhaust ports of the combustible gas control system are disposed to the wet well, the dry well and the plenums to control the combustible gases in the reactor container. Since this can control the combustible gases in the entire reactor container, the integrity of the reactor container can be ensured. (T.M.)

A multi-purpose reactor

International Nuclear Information System (INIS)

Changwen Ma

2000-01-01

An integrated natural circulation self pressurized reactor can be used for sea water desalination, electrogeneration, ship propulsion and district or process heating. The reactor can be used for ship propulsion because it has following advantages: it is a integrated reactor. Whole primary loop is included in a size limited pressure vessel. For a 200 MW reactor the diameter of the pressure vessel is about 5 m. It is convenient to arranged on a ship. Hydraulic driving facility of control rods is used on the reactor. It notably decreases the height of the reactor. For ship propulsion, smaller diameter and smaller height are important. Besides these, the operation reliability of the reactor is high enough, because there is no rotational machine (for example, circulating pump) in safety systems. Reactor systems are simple. There are no emergency water injection system and boron concentration regulating system. These features for ship propulsion reactor are valuable. Design of the reactor is based on existing demonstration district heating reactor design. The mechanic design principles are the same. But boiling is introduced in the reactor core. Several variants to use the reactor as a movable seawater desalination plant are presented in the paper. When the sea water desalination plant is working to produce fresh water, the reactor can supply electricity at the same time to the local electricity network. Some analyses for comprehensive application of the reactor have been done. Main features and parameters of the small (Thermopower 200 MW) reactor are given in the paper. (author)

Prevalência, distribuição geográfica e sazonal de protozoários e mixozoários parasitos de jaú (Zungaro jahu no Pantanal Matogrossense

Directory of Open Access Journals (Sweden)

Edson A. Adriano

2012-12-01

Full Text Available Estudo realizado no Pantanal Matogrossense, avaliou a prevalência, a distribuição geográfica e sazonal de protozoários e mixozoários parasitos de jaú (Zungaro jahu. Os peixes foram capturados no Sul do Pantanal, na região dos rios Aquidauana, Miranda e Paraguai, em 2001, 2002 e 2003, na região Central (Parque Nacional do Pantanal - PARNA Pantanal em 2003, 2004, 2005 e 2008, e na região Norte (rios Cuiabá e Manso, no município de Nobres em 2003, 2004 e 2005. Foi identificado Trichodina sp. parasitando pele e brânquias de jaú nas três regiões estudadas. Ocorrência de Epistylis sp. na pele e Cryptobia sp. nas brânquias foram restritas às coletas da região Central, enquanto Ichthyophthirius multifiliis foi identificado parasitando a pele nas três regiões estudadas. Também foi observada a ocorrência de mixozoários, Myxobolus cordeiroi parasitando vários órgãos e Henneguya sp. parasitando brânquias de jaú das três regiões estudadas.

TU Electric reactor physics model verification: Power reactor benchmark

International Nuclear Information System (INIS)

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

1988-01-01

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

Do documentário histórico ao imaginário antropológico do regime militar brasileiro: uma leitura simbólica sobre o golpe de 1964

Directory of Open Access Journals (Sweden)

Eduardo Portanova Barros

2017-09-01

Full Text Available Este artigo oferece uma leitura simbólica sobre o imaginário que movimenta seis filmes documentários relativos ao regime militar brasileiro. Elegemos os Estudos do Imaginário como heurística apropriada à revelação de imagens simbólicas, simbolismos e narrativas míticas estimuladas pelas representações fílmicas tanto do governo de João Goulart quanto do golpe civil-militar que o tirou da Presidência da República. A partir de documentação audiovisual, acessamos os elementos constitutivos do imaginário que move as obras. Assim, esperamos proporcionar uma complementação ao entendimento sobre esse período obscuro da sociedade brasileira, bem como oferecer uma abordagem alternativa à pesquisa em Comunicação sobre documentários históricos.

BRIQUETAGEM DE FINOS DE CALCÁRIO

Directory of Open Access Journals (Sweden)

Mariana Rezende Barros

2015-12-01

Full Text Available Aplicação da tecnologia na agricultura dentro do sistema de produção é realidade principalmente com a abertura de mercados através da globalização. Em diversas áreas da indústria moderna, o calcário é utilizado como corretor da acidez do solo. A calagem é uma prática barata, porém ainda é negligenciada quanto ao seu uso, na adoção da técnica, à definição das doses e às formas de aplicação. A briquetagem consiste na aglomeração de partículas finas através de pressão, auxiliada ou não por aglomerantes, permitindo obtenção de produtos compactados, com forma, tamanho e parâmetros mecânicos adequados. A redução de volume do material, além dos benefícios tecnológicos, permite que materiais finos possam ser transportados e armazenados de forma mais econômica. A recente preocupação ambiental, resultando em leis mais rígidas, além da necessidade de aproveitar economicamente os resíduos e as partículas finas geradas no beneficiamento de minérios fez com que a briquetagem voltasse a ser uma importante alternativa para aglomerar valor econômico. O objetivo deste trabalho foi aglomerar finos de calcário através da briquetagem (92% abaixo de 500# ou 25 µm gerados no processamento do mesmo, variando as dosagens de água (utilizada como agente aglomerante de 0; 5; 7,5; 10; 12,5 e 15%. O calcário, originário de Lagamar (MG, foi classificado quimicamente como dolomítico tipo D. Os briquetes foram submetidos a testes de queda a 30, 60, 90, 120 e 150 cm de altura. Os melhores resultados encontrados para ensaios de queda foram obtidos com 7,5% de umidade, com médias de 21 quedas para 30 cm e 10 quedas para 60 cm de altura. Tais resultados apresentaram-se favoráveis quando comparados à literatura, a qual cita que para briquetes sem cura, considera-se 3 quedas a 0,3 m como valor razoável.

Supercritical Water Reactors

International Nuclear Information System (INIS)

Bouchter, J.C.; Dufour, P.; Guidez, J.; Latge, C.; Renault, C.; Rimpault, G.

2014-01-01

The supercritical water reactor (SCWR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. SCWR is a new concept, it is an attempt to optimize boiling water reactors by using the main advantages of supercritical water: only liquid phase and a high calorific capacity. The SCWR requires very high temperatures (over 375 C degrees) and very high pressures (over 22.1 MPa) to operate which allows a high conversion yield (44% instead of 33% for a PWR). Low volumes of coolant are necessary which makes the neutron spectrum shift towards higher energies and it is then possible to consider fast reactors operating with supercritical water. The main drawbacks of supercritical water is the necessity to use very high pressures which has important constraints on the reactor design, its physical properties (density, calorific capacity) that vary strongly with temperatures and pressures and its very high corrosiveness. The feasibility of the concept is not yet assured in terms of adequate materials that resist to corrosion, reactor stability, reactor safety, and reactor behaviour in accidental situations. (A.C.)

Tank type reactor

International Nuclear Information System (INIS)

Otsuka, Fumio.

1989-01-01

The present invention concerns a tank type reactor capable of securing reactor core integrity by preventing incorporation of gases to an intermediate heat exchanger, thgereby improving the reliability. In a conventional tank type reactor, since vortex flows are easily caused near the inlet of an intermediate heat exchanger, there is a fear that cover gases are involved into the coolant main streams to induce fetal accidents. In the present invention, a reactor core is suspended by way of a suspending body to the inside of a reactor vessel and an intermediate heat exchanger and a pump are disposed between the suspending body and the reactor vessel, in which a vortex current preventive plate is attached at the outside near the coolant inlet on the primary circuit of the intermediate heat exchanger. In this way vortex or turbulence near the inlet of the intermediate heata exchanger or near the surface of coolants can be prevented. Accordingly, the cover gases are no more involved, to insure the reactor core integrity and obtain a tank type nuclear reactor of high reliability. (I.S.)

New about research reactors

International Nuclear Information System (INIS)

Egorenkov, P.M.

2001-01-01

The multi-purpose research reactor MAPLE (Canada) and concept of new reactor MAPLE-CNF as will substitute the known Canadian research reactor NRU are described. New reactor will be used as contributor for investigations into materials, neutron beams and further developments for the CANDU type reactor. The Budapest research reactor (BRR) and its application after the last reconstruction are considered also [ru

Evaluation of Pressure Changes in HANARO Reactor Hall after a Reactor Shutdown

International Nuclear Information System (INIS)

Han, Geeyang; Han, Jaesam; Ahn, Gukhoon; Jung, Hoansung

2013-01-01

The major objective of this work is intended to evaluate the characteristics of the thermal behavior regarding how the decay heat will be affected by the reactor hall pressure change and the increase of pool water temperature induced in the primary coolant after a reactor shutdown. The particular reactor pool water temperature at the surface where it is evaporated owing to the decay heat resulting in the local heat transfer rate is related to the pressure change response in the reactor hall associated with the primary cooling system because of the reduction of the heat exchanger to remove the heat. The increase in the pool water temperature is proportional to the heat transfer rate in the reactor pool. Consequently, any limit on the reactor pool water temperature imposes a corresponding limit on the reactor hall pressure. At HANARO, the decay heat after a reactor shutdown is mainly removed by the natural circulation cooling in the reactor pool. This paper is written for the safety feature of the pressure change related leakage rate from the reactor hall. The calculation results show that the increase of pressure in the reactor hall will not cause any serious problems to the safety limits although the reactor hall pressure is slightly increased. Therefore, it was concluded that the pool water temperature increase is not so rapid as to cause the pressure to vary significantly in the reactor hall. Furthermore, the mathematical model developed in this work can be a useful analytical tool for scoping and parametric studies in the area of thermal transient analysis, with its proper representation of the interaction between the temperature and pressure in the reactor hall

Ensino religioso e assistência religiosa no Rio Grande do Sul: quadros exploratórios = Religious education and religious assistance in Rio Grande do Sul: exploratory frameworks

Directory of Open Access Journals (Sweden)

Giumbelli, Emerson

2011-01-01

Full Text Available Partindo de uma perspectiva que se interessa pelas configurações geradas pela relação entre sociedade e religião, o texto aborda dois temas: ensino religioso em escolas públicas e assistência religiosa em instituições destinadas à internação de adolescentes que cumprem medida socioeducativa. A maior parte dos dados refere-se ao Rio Grande do Sul, procurando-se apresentar um quadro exploratório para ambos os temas. Mais especificamente, os resultados incidem sobre as formas que caracterizam o modo de relação entre determinadas instituições públicas e a religião e o modo pelo qual se definem configurações de diversidade religiosa

Design guide for Category III reactors: pool type reactors

International Nuclear Information System (INIS)

Brynda, W.J.; Lobner, P.R.; Powell, R.W.; Straker, E.A.

1978-11-01

The Department of Energy (DOE) in the ERDA Manual requires that all DOE-owned reactors be sited, designed, constructed, modified, operated, maintained, and decommissioned in a manner that gives adequate consideration to health and safety factors. Specific guidance pertinent to the safety of DOE-owned reactors is found in Chapter 0540 of the ERDA Manual. The purpose of this Design Guide is to provide additional guidance to aid the DOE facility contractor in meeting the requirement that the siting, design, construction, modification, operation, maintenance, and decommissioning of DOE-owned reactors be in accordance with generally uniform standards, guides, and codes which are comparable to those applied to similar reactors licensed by the Nuclear Regulatory Commission (NRC). This Design Guide deals principally with the design and functional requirement of Category III reactor structures, components, and systems

The computerized reactor period measurement system for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1996-01-01

The article simply introduces the hardware, principle, and software of the computerized reactor period measurement system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between fission yield and pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computerized measurement system makes the reactor period measurement into automatical and intelligent and also improves the speed and precision of period data on-line process

Computer measurement system of reactor period for China fast burst reactor-II

International Nuclear Information System (INIS)

Zhao Wuwen; Jiang Zhiguo

1997-01-01

The author simply introduces the hardware, principle, and software of the reactor period computer measure system for China Fast Burst Reactor-II (CFBR-II). It also gives the relation between Fission yield and Pre-reactivity of CFBR-II reactor system of bared reactor with decoupled-component and system of bared reactor with multiple light-material. The computer measure system makes the reactor period measurement into automation and intellectualization and also improves the speed and precision of period data process on-line

Reactor safety method

International Nuclear Information System (INIS)

Vachon, L.J.

1980-01-01

This invention relates to safety means for preventing a gas cooled nuclear reactor from attaining criticality prior to start up in the event the reactor core is immersed in hydrogenous liquid. This is accomplished by coating the inside surface of the reactor coolant channels with a neutral absorbing material that will vaporize at the reactor's operating temperature

A new species of Microglanis (Siluriformes: Pseudopimelodidae from upper rio Paraná basin, Brazil

Directory of Open Access Journals (Sweden)

Oscar Akio Shibatta

Full Text Available Microglanis garavelloi, new species, collected in tributaries of rio Paranapanema and rio Tietê, is the first species of the genus described from upper rio Paraná basin. The new species can be distinguished from other species of Microglanis on morphometric characters, color pattern, caudal-fin shape, pectoral-spine morphology and lateral line development. Characters used specifically to distinguish M. garavelloi from M. cottoides (laguna dos Patos and rio Uruguay basins and M. parahybae (rio Paraíba do Sul basin include morphometrics, color pattern and pectoral-spine serration.

Small propulsion reactor design based on particle bed reactor concept

International Nuclear Information System (INIS)

Ludewig, H.; Lazareth, O.; Mughabghab, S.; Perkins, K.; Powell, J.R.

1989-01-01

In this paper Particle Bed Reactor (PBR) designs are discussed which use 233 U and /sup 242m/Am as fissile materials. A constant total power of 100MW is assumed for all reactors in this study. Three broad aspects of these reactors is discussed. First, possible reactor designs are developed, second physics calculations are outlined and discussed and third mass estimates of the various candidates reactors are made. It is concluded that reactors with a specific mass of 1 kg/MW can be envisioned of 233 U is used and approximately a quarter of this value can be achieved if /sup 242m/Am is used. If this power level is increased by increasing the power density lower specific mass values are achievable. The limit will be determined by uncertainties in the thermal-hydraulic analysis. 5 refs., 5 figs., 6 tabs

Visualization of crust in metallic piping through real-time neutron radiography obtained with low intensity thermal neutron flux

Energy Technology Data Exchange (ETDEWEB)

Luiz, Leandro C.; Crispim, Verginia R. [Nuclear Engineering Program, Federal University of Rio de Janeiro, Rio de Janeiro (Brazil); Ferreira, Francisco J. O. [National Nuclear Energy Commission, CNEN/IEN, Division Reactors, Rio de Janeiro (Brazil)

2017-06-15

The presence of crust on the inner walls of metallic ducts impairs transportation because crust completely or partially hinders the passage of fluid to the processing unit and causes damage to equipment connected to the production line. Its localization is crucial. With the development of the electronic imaging system installed at the Argonauta/Nuclear Engineering Institute (IEN)/National Nuclear Energy Commission (CNEN) reactor, it became possible to visualize crust in the interior of metallic piping of small diameter using real-time neutron radiography images obtained with a low neutron flux. The obtained images showed the resistance offered by crust on the passage of water inside the pipe. No discrepancy of the flow profile at the bottom of the pipe, before the crust region, was registered. However, after the passage of liquid through the pipe, images of the disturbances of the flow were clear and discrepancies in the flow profile were steep. This shows that this technique added the assembled apparatus was efficient for the visualization of the crust and of the two-phase flows.

Visualization of crust in metallic piping through real-time neutron radiography obtained with low intensity thermal neutron flux

International Nuclear Information System (INIS)

Luiz, Leandro C.; Crispim, Verginia R.; Ferreira, Francisco J. O.

2017-01-01

The presence of crust on the inner walls of metallic ducts impairs transportation because crust completely or partially hinders the passage of fluid to the processing unit and causes damage to equipment connected to the production line. Its localization is crucial. With the development of the electronic imaging system installed at the Argonauta/Nuclear Engineering Institute (IEN)/National Nuclear Energy Commission (CNEN) reactor, it became possible to visualize crust in the interior of metallic piping of small diameter using real-time neutron radiography images obtained with a low neutron flux. The obtained images showed the resistance offered by crust on the passage of water inside the pipe. No discrepancy of the flow profile at the bottom of the pipe, before the crust region, was registered. However, after the passage of liquid through the pipe, images of the disturbances of the flow were clear and discrepancies in the flow profile were steep. This shows that this technique added the assembled apparatus was efficient for the visualization of the crust and of the two-phase flows

Physics of nuclear reactors

International Nuclear Information System (INIS)

Baeten, Peter

2006-01-01

This course gives an introduction to Nuclear Reactor Physics. The first chapter explains the most important parameters and concepts in nuclear reactor physics such as fission, cross sections and the effective multiplication factor. Further on, in the second chapter, the flux distributions in a stationary reactor are derived from the diffusion equation. Reactor kinetics, reactor control and reactor dynamics (feedback effects) are described in the following three chapters. The course concludes with a short description of the different types of existing and future reactors. (author)

Generation III+ Reactor Portfolio

International Nuclear Information System (INIS)

2010-03-01

While the power generation needs of utilities are unique and diverse, they are all faced with the double challenge of meeting growing electricity needs while curbing CO 2 emissions. To answer these diverse needs and help tackle this challenge, AREVA has developed several reactor models which are briefly described in this document: The EPR TM Reactor: designed on the basis of the Konvoi (Germany) and N4 (France) reactors, the EPRTM reactor is an evolutionary model designed to achieve best-in-class safety and operational performance levels. The ATMEA1 TM reactor: jointly designed by Mitsubishi Heavy Industries and AREVA through ATMEA, their common company. This reactor design benefits from the competencies and expertise of the two mother companies, which have commissioned close to 130 reactor units. The KERENA TM reactor: Designed on the basis of the most recent German BWR reactors (Gundremmingen) the KERENA TM reactor relies on proven technology while also including innovative, yet thoroughly tested, features. The optimal combination of active and passive safety systems for a boiling water reactor achieves a very low probability of severe accident

Upper Rio Grande water operations model: A tool for enhanced system management

Science.gov (United States)

Gail Stockton; D. Michael Roark

1999-01-01

The Upper Rio Grande Water Operations Model (URGWOM) under development through a multi-agency effort has demonstrated capability to represent the physical river/reservoir system, to track and account for Rio Grande flows and imported San Juan flows, and to forecast flows at various points in the system. Testing of the Rio Chama portion of the water operations model was...

Guide to power reactors

Energy Technology Data Exchange (ETDEWEB)

NONE

1959-07-15

The IAEA's major first scientific publication is the Directory of Power Reactors now in operation or under construction in various parts of the world. The purpose of the directory is to present important details of various power projects in such a way as to provide a source of easy reference for anyone interested in the development of the peaceful uses of atomic energy, either at the technical or management level. Six pages have been devoted to each reactor the first of which contains general information, reactor physics data and information about the core. The second and third contain sketches of the fuel element or of the fuel element assembly, and of the horizontal and vertical sections of the reactor. On the fourth page information is grouped under the following heads: fuel element, core heat transfer, control, reactor vessel and over-all dimensions, and fluid flow. The fifth page shows a simplified flow diagram, while the sixth provides information on reflector and shielding, containment and turbo generator. Some information has also been given, when available, on cost estimates and operating staff requirements. Remarks and a bibliography constitute the last part of the description of each reactor. Reactor projects included in this directory are pressurized light water cooled power reactors. Boiling light water cooled power reactors, heavy water cooled power reactors, gas cooled power reactors, organic cooled power reactors liquid metal cooled power reactors and liquid metal cooled power reactors

Analysis of dynamic stability and safety of reactor system by reactor simulator

International Nuclear Information System (INIS)

Raisic, N.

1963-11-01

In order to enable qualitative analysis of dynamic properties of reactors RA and RB, mathematical models of these reactors were formulated and adapted for solution on analog computer. This report contains basic assessments for creating the model and complete equations for each reactor. Model was used to analyse three possible accidents at the RA reactor and possible hypothetical accidents at the RB reactor

Nuclear reactor physics

CERN Document Server

Stacey, Weston M

2010-01-01

Nuclear reactor physics is the core discipline of nuclear engineering. Nuclear reactors now account for a significant portion of the electrical power generated worldwide, and new power reactors with improved fuel cycles are being developed. At the same time, the past few decades have seen an ever-increasing number of industrial, medical, military, and research applications for nuclear reactors. The second edition of this successful comprehensive textbook and reference on basic and advanced nuclear reactor physics has been completely updated, revised and enlarged to include the latest developme

Inteligência emocional: estudo exploratório

OpenAIRE

Seabra, Diana Catarina Lopes

2013-01-01

A presente dissertação tem como objetivo esclarecer e refletir sobre a inteligência emocional e explorar se existe uma influência entre a atividade que o grupo exerce, o tempo de pertença e o tempo de vida do mesmo, ao nível da inteligência emocional grupal e das suas dimensões. Para tal, foi desenvolvido um estudo exploratório. A recolha dos dados realizou-se através do Questionário de Inteligência Emocional Grupal traduzido e adaptado por Correia (2010) do Group Emotional Intelligence Quest...

Comentários e Notícias

OpenAIRE

BAD, Cadernos

2004-01-01

• Disposições que regulam o exame de admissão ao curso de Bibliotecário-Arquivistas• Júri do exame de aptidão ao Curso de Bibliotecário-Arquivista• Actividade da Comissão Técnica Portuguesa de Normalização (CT-7).• Estágios no CDCU. (1) Regulamento• O complexo problema do livro português. O Instituto Nacional do Livro e da Bibliografia Portuguesa• Criação da «Casa-Biblioteca Tomaz da Fonseca»• Novas bibliotecas municipais em Lisboa• Arquivo Distrital de Aveiro• Fichas de Documentação - um ser...

Sodium-cooled nuclear reactor

International Nuclear Information System (INIS)

Hammers, H.W.

1982-01-01

The invention concerns a sodium-cooled nuclear reactor, whose reactor tank contains the primary circuit, shielding surrounding the reactor core and a primary/secondary heat exchanger, particularly a fast breeder reactor on the module principle. In order to achieve this module principle it is proposed to have electromagnetic circulating pumps outside the reactor tank, where the heat exchanger is accomodated in an annular case above the pumps. This case has several openings at the top end to the space above the reactor core, some smaller openings in the middle to the same space and is connected at the bottom to an annular space between the tank wall and the reactor core. As a favoured variant, it is proposed that the annular electromagnetic pumps should be arranged concentrically to the reactor tank, where there is an annual duct on the inside of the reactor tank. In this way the sodium-cooled nuclear reactor is made suitable as a module with a large number of such elements. (orig.) [de

Atomic reactor thermal engineering

International Nuclear Information System (INIS)

Kim, Gwang Ryong

1983-02-01

This book starts the introduction of atomic reactor thermal engineering including atomic reaction, chemical reaction, nuclear reaction neutron energy and soon. It explains heat transfer, heat production in the atomic reactor, heat transfer of fuel element in atomic reactor, heat transfer and flow of cooler, thermal design of atomic reactor, design of thermodynamics of atomic reactor and various. This deals with the basic knowledge of thermal engineering for atomic reactor.

Diagnóstico da floricultura no Rio Grande do Sul Diagnosis of floriculture in Rio Grande do Sul, Brazil

Directory of Open Access Journals (Sweden)

Atelene Normann Kämpf

1999-09-01

Full Text Available O objetivo deste trabalho foi avaliar o segmento da produção de flores e plantas ornamentais no Rio Grande do Sul, Brasil, por meio de um levantamento a campo. O estudo faz parte de um projeto global, apoiado pelo Instituto Brasileiro de Floricultura (IBRAFLOR e pelo Ministério da Agricultura e do Abastecimento (MAARA, através do Departamento Nacional de Cooperativismo (DENACOOP. Com base nos formulários preenchidos nas propriedades, foi elaborado um cadastro dos floricultores, com seus endereços e produções. A floricultura gaúcha conta com 257 produtores, que cultivam o total de 304ha em 65 municípios; 30% dessa área é ocupada com flores de corte, 33% com mudas para jardim, 29% com outros produtos da floricultura e 8% com plantas envasadas. O sistema de cultivo predominante é a céu aberto (89%, com baixos investimentos tecnológicos.A survey was conducted to quantify flower and ornamental plant production in the State of Rio Grande do Sul State, Brazil. The Brazilian Floriculture Institute (IBRAFLOR and the Agriculture Ministry (MAARA - DENACOOP granted this research. Based on an inventory formulary a catalog including the nurseries, addresses and main crops was elaborated. There are 257 growers in this State with an area of 304ha distributed among 65 counties; 30% of this area are cultivated with cut flowers, 33% with annuals and perennials for garden, 29% with other floriculture products and 8% with potted plants. The main system of cultivation is not protected with low technological investments.

Argentinean integrated small reactor design and scale economy analysis of integrated reactor

International Nuclear Information System (INIS)

Florido, P. C.; Bergallo, J. E.; Ishida, M. V.

2000-01-01

This paper describes the design of CAREM, which is Argentinean integrated small reactor project and the scale economy analysis results of integrated reactor. CAREM project consists on the development, design and construction of a small nuclear power plant. CAREM is an advanced reactor conceived with new generation design solutions and standing on the large experience accumulated in the safe operation of Light Water Reactors. The CAREM is an indirect cycle reactor with some distinctive and characteristic features that greatly simplify the reactor and also contribute to a highly level of safety: integrated primary cooling system, self pressurized, primary cooling by natural circulation and safety system relying on passive features. For a fully doupled economic evaluation of integrated reactors done by IREP (Integrated Reactor Evaluation Program) code transferred to IAEA, CAREM have been used as a reference point. The results shows that integrated reactors become competitive with power larger than 200MWe with Argentinean cheapest electricity option. Due to reactor pressure vessel construction limit, low pressure drop steam generator are used to reach power output of 200MWe for natural circulation. For forced circulation, 300MWe can be achieved. (author)

76 FR 6517 - San Luis & Rio Grande Railroad-Petition for a Declaratory Order

Science.gov (United States)

2011-02-04

... DEPARTMENT OF TRANSPORTATION Surface Transportation Board [Docket No. FD 35380] San Luis & Rio... petition filed by San Luis & Rio Grande Railroad (SLRG), the Board instituted a declaratory order... proposed operation of a truck-to-rail transload facility in Antonito, Colorado. See San Luis & Rio Grande R...

Electromagnetically Inferred Structure of the Caja del Rio Plateau, New Mexico

Science.gov (United States)

Layton, M. E.; Speed, C.; Shukla, M.; Vila, A.; Chon, E.; Kitamikado, C.; Feucht, D. W.; Bedrosian, P.; Pellerin, L.

2016-12-01

Magnetotelluric (MT) and transient electromagnetic (TEM) data were acquired by students from the Summer of Applied Geophysical Experience (SAGE) to construct structural models in and around the Caja del Rio Plateau, New Mexico. The Caja del Rio is located on the La Bajada-Jemez constriction that separates the Española and Santa Domingo basins in the Rio Grande Rift. The Rio Grande Rift, the result of tectonic extensional forces, extends approximately north-south across northern New Mexico. MT data collected in 2016 were merged with that from previous years to make up an 11 km north line and a 16 km south line extending from the west side of the Caja Del Rio to the east off the plateau in the Old Buckman Road area. The resistivity distributions revealed in one-dimensional (1-D) and two-dimensional (2-D) inverse models show some robust features. Models of the north are interpreted as a top resistive layer (convention) point in the northwest direction towards the conductive Valles Caldera. The MT models are consistent with geologic interpretations of the stratigraphic units. In addition, models disclose an additional conductive layer below the basement that we interpret as the mid-crustal conductor. Transient electromagnetic (TEM) data were collected in seven locations atop the Caja del Rio plateau in an attempt to identify the basal contact of the Cerros del Rio volcanic field, which, in turn, allow for the thickness of these basaltic and andesitic deposits to be mapped across the plateau. One-dimensional inverse models produced from the TEM data were aligned and interpreted geologically. A resistive ( 1000 ohm-m) unit, interpreted to represent the Cerros del Rio volcanics, thickens from 70m to 175m from southeast to northwest. The volcanics are overlain by a thin conductor, interpreted as weathered material. The resistive body is underlain by a thicker conductor, interpreted as sedimentary rocks of the Tertiary-aged Santa Fe Group.

Fast reactors

International Nuclear Information System (INIS)

Vasile, A.

2001-01-01

Fast reactors have capacities to spare uranium natural resources by their breeding property and to propose solutions to the management of radioactive wastes by limiting the inventory of heavy nuclei. This article highlights the role that fast reactors could play for reducing the radiotoxicity of wastes. The conversion of 238 U into 239 Pu by neutron capture is more efficient in fast reactors than in light water reactors. In fast reactors multi-recycling of U + Pu leads to fissioning up to 95% of the initial fuel ( 238 U + 235 U). 2 strategies have been studied to burn actinides: - the multi-recycling of heavy nuclei is made inside the fuel element (homogeneous option); - the unique recycling is made in special irradiation targets placed inside the core or at its surroundings (heterogeneous option). Simulations have shown that, for the same amount of energy produced (400 TWhe), the mass of transuranium elements (Pu + Np + Am + Cm) sent to waste disposal is 60,9 Kg in the homogeneous option and 204.4 Kg in the heterogeneous option. Experimental programs are carried out in Phenix and BOR60 reactors in order to study the feasibility of such strategies. (A.C.)

Crescimento pessoal, mediação e sacrifício: itinerários sociais de estudantes beneficiários do Prouni

Directory of Open Access Journals (Sweden)

Andrea Bayerl Mongim

2015-12-01

Full Text Available Resumo: Este artigo analisa itinerários sociais de estudantes oriundos de famílias consideradas de classes populares e beneficiários do ProUni. Discute o processo de constituição de significados e de incorporação prática de princípios que concorreram para construção e objetivação do projeto de aquisição do título universitário. Tal projeto é construído de forma não naturalizada, efetivando-se pela interação com agentes mediadores, posicionados em quadros institucionais que ultrapassam os limites das redes de relações da família nuclear. A conclusão do curso superior representa a possibilidade de exercer profissão melhor remunerada e valorizada e de incluir-se em grupo de maior prestígio e status.

Reactor power measuring device

International Nuclear Information System (INIS)

Izumi, Mikio; Sano, Yuji; Seki, Eiji; Yoshida, Toshifumi; Ito, Toshiaki.

1993-01-01

The present invention provides a self-powered long detector having a sensitivity over the entire length of a reactor core as an entire control rod withdrawal range of a BWR type reactor, and a reactor power measuring device using a gamma ray thermometer which scarcely causes sensitivity degradation. That is, a hollow protection pipe is disposed passing through the reactor core from the outside of a reactor pressure vessel. The self-powered long detectors and the gamma ray thermometers are inserted and installed in the protection pipe. An average reactor power in an axial direction of the reactor relative to a certain position in the horizontal cross section of the reactor core is determined based on the power of the self-powered long detector over the entire length of the reactor core. Since the response of the self-powered detector relative to a local power change is rapid, the output is used as an input signal to a safety protection device of the reactor core. Further, a gamma ray thermometer secured in the reactor and having scarce sensitivity degradation is used instead of an incore travelling neutron monitor used for relative calibration of an existent neutron monitor secured in the reactor. (I.S.)

Reactor container

International Nuclear Information System (INIS)

Kojima, Yoshihiro; Hosomi, Kenji; Otonari, Jun-ichiro.

1997-01-01

In the present invention, a catalyst for oxidizing hydrogen to be disposed in a reactor container upon rupture of pipelines of a reactor primary coolant system is prevented from deposition of water droplets formed from a reactor container spray to suppress elevation of hydrogen concentration in the reactor container. Namely, a catalytic combustion gas concentration control system comprises a catalyst for oxidizing hydrogen and a support thereof. In addition, there is also disposed a water droplet deposition-preventing means for preventing deposition of water droplets in a reactor pressure vessel on the catalyst. Then, the effect of the catalyst upon catalytic oxidation reaction of hydrogen can be kept high. The local elevation of hydrogen concentration can be prevented even upon occurrence of such a phenomenon that various kinds of mobile forces in the container such as dry well cooling system are lost. (I.S.)

Study on Reactor Performance of Online Power Monitoring in PUSPATI TRIGA Reactor (RTP)

International Nuclear Information System (INIS)

Zareen Khan Abdul Jalil Khan; Ridzuan Abdul Mutalib; Mohd Sabri Minhat

2014-01-01

The Reactor TRIGA PUSPATI (RTP) at Malaysia Nuclear Agency is a TRIGA Mark II type reactor and pool type cooled by natural circulation of light water. This paper describe on reactor performance of online power monitoring based on various parameter of reactor such as log power, linear power, period, Fuel and coolant temperature and reactivity parameter with using neutronic and other instrumentation system of reactor. Methodology of online power estimation and monitoring is to evaluate and analysis of reactor power which is important of reactor safety and control. Neutronic instrumentation system will use to estimate power measurement, differential of log and linear power and period during reactor operation .This study also focus on noise fluctuation from fission chamber during reactor operation .This work will present result of online power monitoring from RTP which indicated the safety parameter identification and initiate safety action on crossing the threshold set point trip. Conclude that optimization of online power monitoring will improved the reactor control and safety parameter of reactor during operation. (author)

A satisfação do usuário em hospital universitário User satisfaction at a university hospital

Directory of Open Access Journals (Sweden)

Antonio C. Lemme

1991-02-01

Full Text Available São apresentados resultados de uma pesquisa exploratória da satisfação/insatisfação de 158 pacientes que recorreram a um Hospital Universitário (HUPE para consulta inicial. As entrevistas foram feitas por alunos do primeiro ano, como parte de projeto de inserção precoce do mesmo com a prática médica, acompanhando pacientes como observadores. Foi utilizado questionário que cobriu os vários aspectos do problema: variáveis sócio-demográficas, arte do cuidado, resolutividade da consulta médica, sugestões de melhoria dos serviços. Tanto alunos/observadores como os usuários conseguiram perceber com precisão os problemas do processo do atendimento (recepção, matrícula, consulta, enfermagem, serviço social, farmácia, exames complementares mas houve divergência de opinião entre vários aspectos da satisfação/insatisfação entre alunos e usuários, provavelmente devido às origens sociais diferentes e expectativas diversas.The results of a research project into the level of satisfaction/dissatisfaction of 158 first-time patients attending by an University hospital, Brazil, are presented. The interviews were carried out by first year medical students as part of a comprehensive project concerned with the restructuring of the Medical Curriculum. Its prime objective was to expose the students to patients/consumers as early as possible in their studies. After an introductory training program, the students asked the patients arriving at the hospital out-patient clinic for permission to observe them throughout the attendance given. A questionnaire was used which covered the various aspects of the consumers relationship with a medical institution (socio-economic variables, "art of care", outcome of the medical encounter and suggestions for improvement. Both patients and students were able to perceive the different problems that patients confront in the course of their dealings with a medical institution (reception, registration

Metazoários parasitos de seis espécies de peixes do Reservatório de Lajes, Estado do Rio de Janeiro, Brasil Metazoan parasites of six fishes species from Lajes Reservoir in the State of Rio de Janeiro, Brazil

Directory of Open Access Journals (Sweden)

Aline R. Paraguassú

2007-09-01

Full Text Available Entre abril de 2002 e julho de 2003, foram necropsiados 231 espécimes de peixes: 39 Astyanax bimaculatus (Linnaeus, 1758, 79 A. fasciatus (Cuvier, 1819, 23 Hypostomus affinis (Steindachner, 1877, 26 Hoplias malabaricus (Bloch, 1794, 30 Loricariichthys castaneus (Castelnau, 1855 e 34 Trachelyopterus striatulus (Steindachner, 1876 provenientes do Reservatório de Lajes (22º42' - 22º50'S, 43º53' 44º05'O, Estado do Rio de Janeiro, Brasil, para estudo das suas comunidades parasitárias. A maioria dos espécimes de H. affinis (95,6% e H. malabaricus (84,6% estavam parasitados por pelo menos uma espécie de metazoário. Em A. bimaculatus, A. fasciatus, L. castaneus e T. striatulus 41%, 39,2%, 56,7% e 14,7% dos espécimes estavam parasitados, respectivamente. Foram coletadas oito diferentes espécies de metazoários parasitos: 2 em A. bimaculatus, 3 em A. fasciatus, 3 em H. affinis, 4 em H. malabaricus, 4 em L. castaneus e 1 em T. striatulus. As comunidades de metazoários parasitos das seis espécies de peixes estudadas apresentaram típico padrão de distribuição agregada. Foram observados dois casos de correlação negativa entre a abundância e a prevalência parasitárias e o comprimento total dos hospedeiros. A comunidade parasitária de L. castaneus apresentou os maiores valores de intensidade média, índice de dispersão e diversidade. As comunidades parasitárias dos peixes estudados apresentaram escassez de correlação entre a abundância, riqueza parasitária e diversidade com o comprimento total dos hospedeiros. Os baixos valores de riqueza e diversidade das comuni-dades parasitárias podem ser atribuídos as características oligotróficas do Reservatório de Lajes.From April 2002 to July 2003, 231 freshwater fishes from Lajes Reservoir in the State of Rio de Janeiro, Brazil (22º42' - 22º50'S, 43º53' - 44º05'W were necropsied to study their community metazoan parasites: 39 Astyanax bimaculatus (Linnaeus, 1758, 79 A. fasciatus

Nuclear power reactors: reactor safety and military and civil defence

International Nuclear Information System (INIS)

Hvinden, T.

1976-01-01

The formation of fission products and plutonium in reactors is briefly described, followed by a short general discussion of reactor safety. The interaction of reactor safety and radioactive release considerations with military and civil defence is thereafter discussed. Reactors and other nuclear plants are factors which must be taken into account in the defence of the district around the site, and as potential targets of both conventional and guerilla attacks and sabotage, requiring special defence. The radiological hazards arising from serious damage to a power reactor by conventional weapons are briefly discussed, and the benefits of underground siting evaluated. Finally the author discusses the significance of the IAEA safeguards work as a preventive factor. (JIW)

SEDIMENTAÇÃO FLUVIAL QUATERNÁRIA NO VALE DO ALTO CURSO DO RIO MACAÉ, ESTADO DO RIO DE JANEIRO, BRASIL.

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Mônica dos Santos Marçal

2015-09-01

Full Text Available O trabalho foi desenvolvido no vale do alto curso do rio Macaé, norte do estado do Rio de Janeiro, e tem como objetivo apresentar as análises geomorfológicas e estratigráficas, além das idades obtidas com o método da luminescência (LOE, realizadas em feições sedimentares de terraços fluviais. Foram selecionadas duas áreas de sedimentação denominadas AS-1, localizada mais a montante do vale, e AS-2 mais a jusante. As feições ocorrem em quatro níveis, sendo três níveis de terraço fluvial, denominados Nível Superior (T1, Nível Intermediário (T2 e Nível Inferior (T3, e um Nível de Planície de Inundação atual (PI. Estão distribuídos de forma descontínua, predominantemente na margem esquerda do rio Macaé, sendo que a planície de inundação (PI ocorre em níveis diferentes em cada margem do vale. Os resultados obtidos das datações por LOE para os sedimentos dos três níveis de terraços (T1, T2 e T3 apresentam boa correspondência às evidências geomorfológicas e estratigráficas utilizadas na definição dos níveis deposicionais aluviais.

Infecções do trato urinário

OpenAIRE

Barros, Susana; Cambão, Marta; Vieira, Sandra; Estevinho, Leticia M.

2005-01-01

O sistema urinário é uma das quatro vias de excreção existentes no corpo humano. A sua exposição a factores exteriores e/ou interiores torna-o sensível a diversas infecções, pelo que, actualmente, em termos de quadro clínico. as patologias relacionadas com as infecções do tracto urinário (ITU), nomeadamente, a uretrite, cistite, síndroma uretral agudo e pielonefrite, são bastantes comuns.

Research reactors in Argentina

International Nuclear Information System (INIS)

Carlos Ruben Calabrese

1999-01-01

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

To the analysis of reactor noise in boiling water reactors

International Nuclear Information System (INIS)

Seifritz, W.

1972-01-01

The paper contains some basic thoughts on the problem of neutron flux oscillations in power reactors. The advantages of self-powered detectors and their function are explained. In addition, noise measurements of the boiling water reactors at Lingen and Holden are described, and the possibilities of an employment of vanadium detectors for the analysis of reactor noise are discussed. The final pages of the paper contain a complete list of the author's publications in the field of reactor noise analysis. (RW/AK) [de

The CEA research reactors

International Nuclear Information System (INIS)

Schwartz, J.P.

1993-01-01

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

State space modeling of reactor core in a pressurized water reactor

Energy Technology Data Exchange (ETDEWEB)

Ashaari, A.; Ahmad, T.; M, Wan Munirah W. [Department of Mathematical Science, Faculty of Science, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Shamsuddin, Mustaffa [Institute of Ibnu Sina, Universiti Teknologi Malaysia, 81310 Skudai, Johor (Malaysia); Abdullah, M. Adib [Swinburne University of Technology, Faculty of Engineering, Computing and Science, Jalan Simpang Tiga, 93350 Kuching, Sarawak (Malaysia)

2014-07-10

The power control system of a nuclear reactor is the key system that ensures a safe operation for a nuclear power plant. However, a mathematical model of a nuclear power plant is in the form of nonlinear process and time dependent that give very hard to be described. One of the important components of a Pressurized Water Reactor is the Reactor core. The aim of this study is to analyze the performance of power produced from a reactor core using temperature of the moderator as an input. Mathematical representation of the state space model of the reactor core control system is presented and analyzed in this paper. The data and parameters are taken from a real time VVER-type Pressurized Water Reactor and will be verified using Matlab and Simulink. Based on the simulation conducted, the results show that the temperature of the moderator plays an important role in determining the power of reactor core.

Brazilian Social Psychology in the international context: a commentary A Psicologia Social brasileira no cenário internacional: um comentário

Directory of Open Access Journals (Sweden)

Joaquim Pires Valentim

2013-03-01

Full Text Available The present paper is a commentary on the talks given by Torres and Álvaro and by Krüger regarding Brazilian Social Psychology in the international context. Starting with a brief contrast with the situation in Portugal, this commentary next approaches, in a synthetic way, questions that cut across social psychology in the international setting, namely, those related with the recurrent dichotomy individual/collective, the great advances in social neuroscience, the study of minorities, the scarcity of psychosocial research about colonialism, and lastly, contemporary issues of science and educational policy.Faz-se aqui um comentário às intervenções de Torres e Álvaro e de Krüger sobre a Psicologia Social brasileira no cenário internacional. Começando por estabelecer um breve contraste com a situação em Portugal, de seguida este comentário aborda, de forma sintética, questões transversais à psicologia social no cenário internacional, designadamente as que se relacionam com a recorrente dicotomia individual/coletivo, os enormes avanços na neurociência social, o estudo das minorias, a escassez de estudos psicossociais sobre o colonialismo e, por último, questões contemporâneas de política científica e de ensino.

A new species of Hemigrammus Gill, 1858 (Characiformes: Characidae from the rio Madeira and rio Paraguai basins, with a redescription of H. lunatus

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Rafaela P. Ota

Full Text Available A new Hemigrammusis described from the rio Paraguai and rio Madeira basins, Mato Grosso and Rondônia States, Brazil. The new species is characterized by possessing a wide dark horizontal stripe across the eye, a vertically elongated humeral blotch, and 4-5 gill-rakers on upper branch and 9-10 on lower. The new species can be easily diagnosed from H. lunatus, the sympatric and morphologically most similar congener, by the shape of humeral blotch and the number of gill rakers. Data of the type material of both Hemigrammus lunatus and H. maxillaris, as well as extensive examination of specimens, allowed us to conclude that H. maxillarisis a junior subjective synonym of H. lunatus. A redescription of H. lunatus, as well as a formal restriction of its type locality, is provided. A putative monophyletic group within Hemigrammus, composed by H. barrigonae, Hemigrammus lunatus, H. machadoi new species, and H. ulreyi, named Hemigrammus lunatus group, is proposed based on overall body morphology and color pattern. Additionally, a discussion on the biogeographical relationships between the rio Paraguai and rio Guaporé basins is provided.

Avaliação do controle externo da qualidade nos laboratórios clínicos do Rio de Janeiro de 2006 a 2008

OpenAIRE

Chaves,Josefa Sieira Caamaño; Marin,Victor Augustus

2010-01-01

INTRODUÇÃO: O Controle Externo da Qualidade (CEQ) é uma ferramenta importante para a garantia da qualidade das análises laboratoriais, auxiliando o laboratório a avaliar a eficiência da fase analítica de seus processos. Um resultado errôneo de uma análise prejudica a conclusão do diagnóstico de uma enfermidade e a indicação correta do tratamento a ser tomado. As inspeções sanitárias em laboratórios clínicos (LCs) no estado do Rio de Janeiro são feitas com base no roteiro de inspeção sanitária...

Controlo dos acessórios de elevação

OpenAIRE

Costa, Ana Luisa Nogueira da

2016-01-01

Relatório de Estágio apresentado para cumprimento dos requisitos necessários à obtenção do grau de Mestre em Segurança e Higiene no Trabalho O relatório é o trabalho final da 8ª Edição do Mestrado de Segurança e Higiene no Trabalho, da Escola Superior de Ciências Empresariais em parceria com a Escola Superior de Tecnologia de Setúbal, do Instituto Politécnico de Setúbal. O estágio desenrolou-se nas instalações da empresa LUSOSIDER, sob a orientação da Técnica Superior em SHST Eng....

Virtual nuclear reactor for education of nuclear reactor physics

International Nuclear Information System (INIS)

Tsuji, Masashi; Narabayashi, Takashi; Shimazu, Youichiro

2008-01-01

As one of projects that were programmed in the cultivation program for human resources in nuclear engineering sponsored by the Ministry of Economy, Trade and Industry, the development of a virtual reactor for education of nuclear reactor physics started in 2007. The purpose of the virtual nuclear reactor is to make nuclear reactor physics easily understood with aid of visualization. In the first year of this project, the neutron slowing down process was visualized. The data needed for visualization are provided by Monte Carlo calculations; The flights of the respective neutrons generated by nuclear fissions are traced through a reactor core until they disappear by neutron absorption or slow down to a thermal energy. With this visualization and an attached supplement textbook, it is expected that the learners can learn more clearly the physical implication of neutron slowing process that is mathematically described by the Boltzmann neutron transport equation. (author)

Plants, arthropods, and birds of the Rio Grande [chapter 7

Science.gov (United States)

Deborah M. Finch; Gale L. Wolters; Wang Yong; Mary Jean Mund

1995-01-01

Human populations have increased dramatically along the Rio Grande since European settlement. Human use of water for irrigation and consumption, and human use of land for agriculture, urban centers, livestock grazing, and recreation have changed Rio Grande ecosystems by altering flood cycles, channel geomorphology, upslope processes, and water quality and quantity....

Reactor physics and reactor strategy investigations into the fissionable material economy of the thorium and uranium cycle in fast breeder reactors and high temperature reactors

International Nuclear Information System (INIS)

Schikorr, W.M.

In this work the properties governing the fissionable material economy of the uranium and thorium cycles are investigated for the advanced reactor types currently under development - the fast breeder reactor (FBR) and the high temperature reactor (HTR) - from the point of view of the optimum utilization of the available nuclear fuel reserves and the continuance of supply of these reserves. For this purpose, the two reactor types are first of all considered individually and are subsequently discussed as a complementary overall system

Reactor core

International Nuclear Information System (INIS)

Azekura, Kazuo; Kurihara, Kunitoshi.

1992-01-01

In a BWR type reactor, a great number of pipes (spectral shift pipes) are disposed in the reactor core. Moderators having a small moderating cross section (heavy water) are circulated in the spectral shift pipes to suppress the excess reactivity while increasing the conversion ratio at an initial stage of the operation cycle. After the intermediate stage of the operation cycle in which the reactor core reactivity is lowered, reactivity is increased by circulating moderators having a great moderating cross section (light water) to extend the taken up burnup degree. Further, neutron absorbers such as boron are mixed to the moderator in the spectral shift pipe to control the concentration thereof. With such a constitution, control rods and driving mechanisms are no more necessary, to simplify the structure of the reactor core. This can increase the fuel conversion ratio and control great excess reactivity. Accordingly, a nuclear reactor core of high conversion and high burnup degree can be attained. (I.N.)

Breves comentários sobre as teorias marxistas de imigração

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Raul Felix Barbosa

2017-10-01

Full Text Available Sabe-se que o capitalismo possui sua parcela de responsabilidade nos movimentos migratórios, voluntários ou forçados, do período pós-revolução industrial. Apesar de Karl Marx não ter abordado diretamente a questão migratório, a teoria marxista e neomarxista se ocupa de explicar os processos migratórios. Esse artigo realiza um levantamento das teorias migratórias de origem marxista apresentando-as, bem como as críticas recebidas.

Nuclear reactor

International Nuclear Information System (INIS)

Batheja, P.; Huber, R.; Rau, P.

1985-01-01

Particularly for nuclear reactors of small output, the reactor pressure vessel contains at least two heat exchangers, which have coolant flowing through them in a circuit through the reactor core. The circuit of at least one heat exchanger is controlled by a slide valve, so that even for low drive forces, particularly in natural circulation, the required even loading of the heat exchanger is possible. (orig./HP) [de

Crianças em situação de violência de um ambulatório do Rio de Janeiro: conhecendo seu perfil Niños en situación de violencia de un ambulatorio en Rio de Janeiro: conociendo su perfil Children under violence situation followed-up in the outpatient setting at Rio de Janeiro: knowing their profile

OpenAIRE

Lucia Martins de Magalhães Pierantoni; Ivone Evangelista Cabral

2009-01-01

Buscou-se caracterizar as crianças envolvidas em situação de violência e seus familiares, e analisar o papel social do agressor/protetor no círculo da violência. Estudo quantitativo descritivo foi desenvolvido no Ambulatório da Família de um Hospital do Rio de Janeiro, entre 2006 e 2007. Dados do prontuário de 44 crianças demonstraram intensa relação entre pobreza, baixa escolaridade e gênero na matriz social da violência. Houve maior registro de meninos (64%) expostos a violência do que meni...

Saúde reprodutiva e mulheres indígenas do Alto Rio Negro

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Marta Azevedo

Full Text Available O presente artigo descreve e analisa as concepções próprias das mulheres indígenas do Alto Rio Negro sobre saúde reprodutiva, relacionando-as a indicadores de fecundidade. As informações qualitativas apontam para um conhecimento detalhado e complexo que as mulheres indígenas dessa região possuem sobre seu corpo e os cuidados com sua saúde. Os níveis e padrões etários da fecundidade estão relacionados com a etnia das mulheres, portanto, aos sistemas tradicionais de cuidados com a saúde desses povos. A pesquisa foi desenvolvida entre 1997 e 2003, na região de Iauaretê, Terra Indígena Alto Rio Negro (AM, e teve como primeira fonte de dados o Censo Indígena Autônomo do Rio Negro - CIARN-, levado a efeito pela Federação das Organizações Indígenas do Rio Negro - FOIRN - em 1992.

Performance improvement of the Annular Core Pulse Reactor for reactor safety experiments

International Nuclear Information System (INIS)

Reuscher, J.A.; Pickard, P.S.

1976-01-01

The Annular Core Pulse Reactor (ACPR) is a TRIGA type reactor which has been in operation at Sandia Laboratories since 1967. The reactor is utilized in a wide variety of experimental programs which include radiation effects, neutron radiography, activation analysis, and fast reactor safety. During the past several years, the ACPR has become an important experimental facility for the United States Fast Reactor Safety Research Program and questions of interest to the safety of the LMFBR are being addressed. In order to enhance the capabilities of the ACPR for reactor safety experiments, a project to improve the performance of the reactor was initiated. It is anticipated that the pulse fluence can be increased by a factor of 2.0 to 2.5 utilizing a two-region core concept with high heat capacity fuel elements around the central irradiation cavity. In addition, the steady-state power of the reactor will be increased by about a factor of two. The new features of the improvements are described

Identification of nuclear reactor characteristics by the reactor noise analysis

International Nuclear Information System (INIS)

Yashima, Hideyuki

1980-01-01

Reactor noise analysis method was applied to TRIGA II Research Reactor (Atomic Research Laboratory, Musashi Institute of Technology) and computed power spectral density (PSD) from the CIC current record. PSD has provided many valuable informations regarding to the reactor kinetics, including the effect of control rods vibration. Another information of neutron physics parameters were obtained and this result was compared with the parameter which was formerly measured by the Feynman-α experiment. Through these experiments we could find overall frequency characteristics of TRIGA II Reactor. (author)

Plantas medicinais em quintais urbanos de Rio Branco, Acre Medicinal plants in urban backyards in Rio Branco, Acre

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A. Siviero

2012-01-01

Full Text Available Este trabalho teve como objetivo realizar levantamento das espécies vegetais de uso medicinal cultivadas em quintais urbanos da cidade de Rio Branco. Foram realizadas entrevistas presenciais com aplicação de questionário especifico registrando as espécies vegetais de uso medicinal e dados sócio-econômicos dos moradores em 132 quintais urbanos de Rio Branco entre 2009 e 2010. Os bairros selecionados para o estudo foram: Aeroporto Velho, Placas, e Novo Horizonte, todos situados na periferia do município. Foram detectadas 83 espécies vegetais de uso medicinal pertencente a 50 famílias botânicas com destaque para Lamiaceae (12,0% e Asteraceae (6,0%, sendo 66,2% exóticas, e 28,9% e 16,8%, associadas ao uso alimentar e ornamental, respectivamente. A decocção das folhas visando à obtenção do chá foi o principal modo de preparo das plantas. A análise de regressão logística entre a riqueza de espécies e diversos fatores socioeconômicos dos entrevistados mostrou que a probabilidade de ocorrência de espécies é três vezes maior em quintais manejados por moradores com idade superior a 50 anos de idade. A análise de correlação não paramétrica de fatores quantitativos mostrou que a variável tempo de moradia está mais correlacionada com a riqueza de plantas medicinais do que a variável idade. O cultivo das plantas medicinais em quintais urbanos de Rio Branco auxilia no combate a doenças e promove a conservação ex situ da agrobiodiversidade agroflorestal, bem estar aos moradores pela melhoria da paisagem, ambiência microclimática e espaço de lazer.This study aimed to survey the medicinal plant species grown in urban backyards in the city of Rio Branco. Personal interviews were conducted by applying a specific questionnaire recording the plant species of medicinal use and the socioeconomic data of residents in 132 urban backyards in Rio Branco between 2009 and 2010. The districts selected for the study were "Aeroporto

Research on the reactor physics and reactor safety of VVER reactors. AER Symposium 2016

Energy Technology Data Exchange (ETDEWEB)

Kliem, S.

2017-09-15

The selected paperscan be attributed to the following main subjects: Reactor start-up tests and use of corresponding data for code validation, code development and application, approaches for safety analyses, closure of nuclear fuel cycle, prospective reactor concepts.

The fast breeder reactor

International Nuclear Information System (INIS)

Collier, J.

1990-01-01

The arguments for and against the fast breeder reactor are debated. The case for the fast reactor is that the world energy demand will increase due to increasing population over the next forty years and that the damage to the global environment from burning fossil fuels which contribute to the greenhouse effect. Nuclear fission is the only large scale energy source which can achieve a cut in the use of carbon based fuels although energy conservation and renewable sources will also be important. Fast reactors produce more energy from uranium than other types of (thermal) reactors such as AGRs and PWRs. Fast reactors would be important from about 2020 onwards especially as by then many thermal reactors will need to be replaced. Fast reactors are also safer than normal reactors. The arguments against fast reactors are largely economic. The cost, especially the capital cost is very high. The viability of the technology is also questioned. (UK)

Reactor feedwater system

International Nuclear Information System (INIS)

Kagaya, Hiroyuki; Tominaga, Kenji.

1993-01-01

In a simplified water type reactor using a gravitationally dropping emergency core cooling system (ECCS), the present invention effectively prevents remaining high temperature water in feedwater pipelines from flowing into the reactor upon occurrence of abnormal events. That is, (1) upon LOCA, if a feedwater pipeline injection valve is closed, boiling under reduced pressure of the remaining high temperature water occurs in the feedwater pipelines, generated steams prevent the remaining high temperature water from flowing into the reactor. Accordingly, the reactor is depressurized rapidly. (2) The feedwater pipeline injection valve is closed and a bypassing valve is opened. Steams generated by boiling under reduced pressure of the remaining high temperature water in the feedwater pipelines are released to a condensator or a suppression pool passing through bypass pipelines. As a result, the remaining high temperature water is prevented from flowing into the reactor. Accordingly, the reactor is rapidly depressurized and cooled. It is possible to accelerate the depressurization of the reactor by the method described above. Further, load on the depressurization valve disposed to a main steam pipe can be reduced. (I.S.)

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

International Nuclear Information System (INIS)

Bussac, J.; Reuss, P.

1985-01-01

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

Monitorização da ponte sobre o rio Kwanza na Cabala

OpenAIRE

Oliveira Santos, L.; Santos, J.; Xu, Min

2011-01-01

A presente comunicação visa divulgar os trabalhos de monitorização da nova ponte sobre o rio Kwanza, na localidade da Cabala, levados a cabo pelo Laboratório Nacional de Engenharia Civil e pelo Laboratório de Engenharia de Angola. Para além da apresentação do plano geral de observação e da descrição dos ensaios estáticos e dinâmicos realizados no final da construção, é dada uma ênfase particular a aspectos inovadores, como a monitorização do nível do rio e da evolução morfol...

ESD and the Rio Conventions

Science.gov (United States)

Sarabhai, Kartikeya V.; Ravindranath, Shailaja; Schwarz, Rixa; Vyas, Purvi

2012-01-01

Chapter 36 of Agenda 21, a key document of the 1992 Earth Summit, emphasised reorienting education towards sustainable development. While two of the Rio conventions, the Convention on Biological Diversity (CBD) and the United Nations Framework Convention on Climate Change (UNFCCC), developed communication, education and public awareness (CEPA)…

Ulysse, mentor reactor

International Nuclear Information System (INIS)

Bouquin, B.; Rio, I.; Safieh, J.

1997-01-01

On July 23, 1961, the ULYSSE reactor began its first power rise. Designed at that time to train nuclear engineering students and reactor operators, this reactor still remains an indispensable tool for nuclear teaching and a choice instrument for scientists. (author)

Siting of research reactors

International Nuclear Information System (INIS)

1987-01-01

The purpose of this document is to develop criteria for siting and the site-related design basis for research reactors. The concepts presented in this document are intended as recommendations for new reactors and are not suggested for backfitting purposes for facilities already in existence. In siting research reactors serious consideration is given to minimizing the effects of the site on the reactor and the reactor on the site and the potential impact of the reactor on the environment. In this document guidance is first provided on the evaluation of the radiological impact of the installation under normal reactor operation and accident conditions. A classification of research reactors in groups is then proposed, together with a different approach for each group, to take into account the relevant safety problems associated with facilities of different characteristics. Guidance is also provided for both extreme natural events and for man-induced external events which could affect the safe operation of the reactor. Extreme natural events include earthquakes, flooding for river or coastal sites and extreme meteorological phenomena. The feasibility of emergency planning is finally considered for each group of reactors

Leishmaniose tegumentar americana: casuística hospitalar no Rio de Janeiro American tegumentary Leishmaniasis: hospitalized cases in Rio de Janeiro

Directory of Open Access Journals (Sweden)

Nurimar C. Fernandes

2004-08-01

Full Text Available FUNDAMENTOS: A leishmaniose tegumentar americana distribui-se amplamente no Brasil, e o Estado do Rio de Janeiro (capital e interior constitui área endêmica onde o vetor é encontrado dentro e ao redor das habitações. OBJETIVOS: Análise prospectiva de 48 casos de leishmaniose tegumentar americana atendidos no Hospital Universitário Clementino Fraga Filho/UFRJ, no período de 1990 a 2002. MÉTODOS: Todos os pacientes foram submetidos à biópsia de pele ou mucosa, teste de Montenegro e exame otorrinolaringológico; SbV (10 a 20mg/kg, no total de 10, 30 e 90 doses. foi empregado em 44 pacientes; em quatro casos, anfotericina B (0,5mg/kg/dose até dose cumulativa de 30mg/kg. RESULTADOS: 28 homens e 20 mulheres na faixa etária de 10 a 89 anos, dos quais 38 (79,1% infectados no Rio de Janeiro, apresentaram úlcera de membro inferior e comprometimento de mucosa nasal como manifestações mais freqüentes; 41 casos (85,4% foram reatores à intradermorreação de Montenegro (5mm; 17 casos (35,4% foram positivos para o achado de amastigotas em macrófagos no infiltrado inflamatório dérmico; predominou o processo inflamatório crônico granulomatoso; cura clínica foi observada em 47 casos; um caso evoluiu para óbito no décimo dia de tratamento. CONCLUSÕES: O estudo da leishmaniose tegumentar (HUCFF/UFRJ no período 1990/2002 evidenciou padrão conhecido nos aspectos epidemiológicos, clínicos e de resposta terapêutica ao antimonial (SbV e anfotericina B.BACKGROUND: American tegumentary Leishmaniasis is widely found in Brazil; the state of Rio de Janeiro (capital and hinterland is an endemic area where the vector is found inside and outside houses. OBJECTIVES: prospective study of 48 cases attended at the Teaching Hospital Clementino Fraga Filho - UFRJ, between 1990 - 2002. METHODS: All patients were submitted to skin or mucosa biopsy, Montenegro skin test and otorhinolaryngologic examination; SbV (10 - 20 mg/kg with 10, 30 and 90 doses was

Experience in using a research reactor for the training of power reactor operators

International Nuclear Information System (INIS)

Blotcky, A.J.; Arsenaut, L.J.

1972-01-01

A research reactor facility such as the one at the Omaha Veterans Administration Hospital would have much to offer in the way of training reactor operators. Although most of the candidates for the course had either received previous training in the Westinghouse Reactor Operator Training Program, had operated nuclear submarine reactors or had operated power reactors, they were not offered the opportunity to perform the extensive manipulations of a reactor that a small research facility will allow. In addition the AEC recommends 10 research reactor startups per student as a prerequisite for a cold operator?s license and these can easily be obtained during the training period

Reactor transients tests for SNR fuel elements in HFR reactor

International Nuclear Information System (INIS)

Plitz, H.

1989-01-01

In HFR reactor, fuel pins of LMFBR reactors are putted in irradiation specimen capsules cooled with sodium for reactor transients tests. These irradiation capsules are instrumented and the experiences realized until this day give results on: - Fuel pins subjected at a continual variation of power - melting fuel - axial differential elongation of fuel pins

Fisioterapia respiratória no pré-operatório de colecistectomia

Directory of Open Access Journals (Sweden)

Lucas Lima Ferreira

2013-05-01

Full Text Available Introdução: As cirurgias abdominais altas causam alterações da função pulmonar caracterizadas por redução da capacidade vital, relacionada à presença de hipoxemia e atelectasia, e pela  redução do volume expiratório forçado no primeiro segundo. Relato do caso: Paciente do sexo feminino, 29 anos, diagnóstico médico de cálculos biliares e hérnia hiatal, diagnóstico funcional de baixo desempenho cardiorrespiratório, a três meses de préoperatório de colecistectomia. Foi realizada avaliação composta por dados antropométricos, espirometria, teste de caminhada de seis minutos (TC6, mensuração das pressões respiratórias pIntrodução: As cirurgias abdominais altas causam alterações da função pulmonar caracterizadas por redução da capacidade vital, relacionada à presença de hipoxemia e atelectasia, e pela redução do volume expiratório forçado no primeiro segundo. Relato do caso: Paciente do sexo feminino, 29 anos, diagnóstico médico de cálculos biliares e hérnia hiatal, diagnóstico funcional de baixo desempenho cardiorrespiratório, a três meses de préoperatório de colecistectomia. Foi realizada avaliação composta por dados antropométricos, espirometria, teste de caminhada de seis minutos (TC6, mensuração das pressões respiratórias por meio da manovacuometria e do nível de qualidade de vida mediante o questionário SF-36. A seguir foi aplicado um protocolo de fisioterapia respiratória e reavaliação após o tratamento. Na avaliação inicial foi verificado que a paciente encontravase com sobrepeso (IMC=27,40 kg/m2, baixo desempenho cardiorrespiratório e fraqueza da musculatura respiratória. Conclusão: O protocolo aplicado mostrou-se eficaz, pois auxiliou na redução de peso corporal e melhorou o desempenho cardiorrespiratório por meio dos exercícios aeróbicos, e proporcionou ganho de força aos músculos respiratórios.

Nuclear reactor coolant channels

International Nuclear Information System (INIS)

Macbeth, R.V.

1978-01-01

A nuclear reactor coolant channel is described that is suitable for sub-cooled reactors as in pressurised water reactors as well as for bulk boiling, as in boiling water reactors and steam generating nuclear reactors. The arrangement aims to improve heat transfer between the fuel elements and the coolant. Full constructional details are given. See also other similar patents by the author. (U.K.)

Tipos do Herbário Prisco Bezerra - EAC

Directory of Open Access Journals (Sweden)

Maria Stela Bezerra da Silva

1990-01-01

Full Text Available Com o presente trabalho pretende-se contribuir para a divulgação dos tipos do Herbário Prisco Bezerra - EAC. Um levantamento realizado no acervo do Herbário revelou o registro de dez tipos. Sete deles pertencentes à família Leguminosae distribuídas entre as subfamilias Caesalpinioideae: Peltogyne crenulata, Sentia dardanoi, Moldenhawera acuminata, Chamaecrista duckeana, Papilionoideae: Aeschynomene monteiroi, Cranocarpus gracilis e Mimosoideae: Mimosa niomarlei; dois, pertencentes à família Erythroxylaceae. As espécies Erythroxylum tianguanum e Erythroxylum bezerrae e um à família Euphorbiaceae: Dalechampia fernandesii recentemente descrita por G. Webster. Os tipos são apresentados na seqüência das indicações: nome das famílias, seguido do epíteto específico, habitat, com a transferência de todas as informações mencionadas na ficha de exsicata do material, bem como, a fotografia correspondente. Citam-se também alguns aspectos característicos das espécies, para melhor visualização dos detalhes fotográficos.The present paper repasts the type specimens in the Herbário Prisco Bezerra (University of Ceará. The Herbário has ten type, of which seven are Leguminosae: Peltoqyne crenulata, Senna dardanoi, Moldenhawera acuminata Chamaecrista duckeana, Aeschynomene monteiroi, Cranocarpus gracilis, Mimosa niomarlei, two the Erythroxylaceae: Erythroxylum tianquanum and Erythroxylum bezerrae and one Euphorbiaceae: Dalechampia fernandesii. Additional informations for these exsicata is presented.

Agentes Comunitários de Saúde: agenciadores de encontros entre territórios Community Health Workers: promoters of interaction between territories

Directory of Open Access Journals (Sweden)

Samira Lima da Costa

2012-11-01

Full Text Available O artigo apresenta reflexões produzidas a partir de uma série de encontros com Agentes Comunitários de Saúde, ao longo de dez anos. Identifica-se a consolidação de dois territórios existenciais, que ora se aproximam, ora se afastam: o do saber técnico em saúde e o do saber popular em saúde. A partir da análise de algumas falas de ACS e de reflexões que dialogam com o referencial teórico da área, o texto discute alguns dos dilemas e impasses do acesso e da adesão na ótica desses Agentes, bem como as estratégias cotidianamente inventadas a partir dos encontros que se dão entre esses dois territórios. Identifica-se o lugar do Agente Comunitário de Saúde como agenciador de fronteiras, atuando em alguns momentos como um inventor ou potencializador de zonas de contato entre territórios e, em outros, como um representante de um dos territórios no outro.This article presents reflections originating from a series of meetings with community health workers over a period of ten years. It identifies the consolidation of two existential territories, which are sometimes closer and at other times more distant from each other, namely the territory of technical knowledge about health and the territory of popular knowledge about health. Starting with the analysis of some quotes from health workers and reflections which tally with the theoretical reference in the area, this paper discusses some of the dilemmas and deadlocks of access and affiliation from the perspective of some of these health workers, as well as the strategies devised on a day-to-day basis from the crossovers that take place between these two territories. It identifies the function of community health workers as frontier agents, at times acting as inventors or motivators of contact zones between the territories, and at other times acting as a representative by one territory inside the other.

Training reactor deployment. Advanced experimental course on designing new reactor cores

International Nuclear Information System (INIS)

Skoda, Radek

2009-01-01

Czech Technical University in Prague (CTU) operating its training nuclear reactor VR1, in cooperation with the North West University of South Africa (NWU), is applying for accreditation of the experimental training course ''Advanced experimental course on designing the new reactor core'' that will guide the students, young nuclear engineering professionals, through designing, calculating, approval, and assembling a new nuclear reactor core. Students, young professionals from the South African nuclear industry, face the situation when a new nuclear reactor core is to be build from scratch. Several reactor core design options are pre-calculated. The selected design is re-calculated by the students, the result is then scrutinized by the regulator and, once all the analysis is approved, physical dismantling of the current core and assembling of the new core is done by the students, under a close supervision of the CTU staff. Finally the reactor is made critical with the new core. The presentation focuses on practical issues of such a course, desired reactor features and namely pedagogical and safety aspects. (orig.)

Three-dimensional reactor dynamics code for VVER type nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Kyrki-Rajamaeki, R. [VTT Energy, Espoo (Finland)

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.).

Three-dimensional reactor dynamics code for VVER type nuclear reactors

International Nuclear Information System (INIS)

Kyrki-Rajamaeki, R.

1995-10-01

A three-dimensional reactor dynamics computer code has been developed, validated and applied for transient and accident analyses of VVER type nuclear reactors. This code, HEXTRAN, is a part of the reactor physics and dynamics calculation system of the Technical Research Centre of Finland, VTT. HEXTRAN models accurately the VVER core with hexagonal fuel assemblies. The code uses advanced mathematical methods in spatial and time discretization of neutronics, heat transfer and the two-phase flow equations of hydraulics. It includes all the experience of VTT from 20 years on the accurate three-dimensional static reactor physics as well as on the one-dimensional reactor dynamics. The dynamic coupling with the thermal hydraulic system code SMABRE also allows the VVER circuit-modelling experience to be included in the analyses. (79 refs.)

Reactor performances and microbial communities of biogas reactors: effects of inoculum sources.

Science.gov (United States)

Han, Sheng; Liu, Yafeng; Zhang, Shicheng; Luo, Gang

2016-01-01

Anaerobic digestion is a very complex process that is mediated by various microorganisms, and the understanding of the microbial community assembly and its corresponding function is critical in order to better control the anaerobic process. The present study investigated the effect of different inocula on the microbial community assembly in biogas reactors treating cellulose with various inocula, and three parallel biogas reactors with the same inoculum were also operated in order to reveal the reproducibility of both microbial communities and functions of the biogas reactors. The results showed that the biogas production, volatile fatty acid (VFA) concentrations, and pH were different for the biogas reactors with different inocula, and different steady-state microbial community patterns were also obtained in different biogas reactors as reflected by Bray-Curtis similarity matrices and taxonomic classification. It indicated that inoculum played an important role in shaping the microbial communities of biogas reactor in the present study, and the microbial community assembly in biogas reactor did not follow the niche-based ecology theory. Furthermore, it was found that the microbial communities and reactor performances of parallel biogas reactors with the same inoculum were different, which could be explained by the neutral-based ecology theory and stochastic factors should played important roles in the microbial community assembly in the biogas reactors. The Bray-Curtis similarity matrices analysis suggested that inoculum affected more on the microbial community assembly compared to stochastic factors, since the samples with different inocula had lower similarity (10-20 %) compared to the samples from the parallel biogas reactors (30 %).

The fast reactor

International Nuclear Information System (INIS)

1980-02-01

The subject is discussed as follows: brief description of fast reactors; advantage in conserving uranium resources; experience, in UK and elsewhere, in fast reactor design, construction and operation; safety; production of plutonium, security aspects; consideration of future UK fast reactor programme. (U.K.)

Impacto do uso de microrganismos em caixas sifonadas de ambientes sanitários

Directory of Open Access Journals (Sweden)

Verena Soares Fernandes

Full Text Available Resumo A preocupação com a qualidade de operação dos sistemas prediais de esgoto sanitário tem motivado empresas especializadas em biotecnologia a investir em produtos compostos por misturas de microrganismos vivos que atuam no pré-tratamento de efluentes de sistemas prediais para combater odores desagradáveis em ambientes sanitários. O objetivo deste artigo é avaliar o uso de misturas concentradas de microrganismos em caixas sifonadas para eliminar o mau cheiro em ambientes sanitários e o impacto em estações de tratamento de esgotos sanitários. O método consiste em diagnosticar o mau cheiro de um dos sanitários de um edifício escolar de nível superior, que é alvo de constantes reclamações por parte dos usuários. Em seguida, introduzir tabletes de microrganismos nas caixas sifonadas e, por fim, avaliar o impacto do uso desse produto em dois sanitários e em estações de tratamento de esgoto por meio de análises de demanda bioquímica de oxigênio e de testes de respirometria. Os resultados indicam que nestes ambientes sanitários o mau cheiro não foi reduzido com o emprego de tabletes de microrganismos e em Estações de Tratamento de Esgoto, na concentração indicada pelo fabricante, o produto não produziu alterações significativas nas características analisadas do esgoto.

PUSPATI TRIGA Reactor

International Nuclear Information System (INIS)

Masood, Z.

2016-01-01

The PUSPATI TRIGA Reactor is the only research reactor in Malaysia. This 1 MW TRIGA Mk II reactor first reached criticality on 28 June 1982 and is located at the Malaysian Nuclear Agency premise in Bangi, Malaysia. This reactor has been mainly utilised for research, training and education and isotope production. Over the years several systems have been refurbished or modernised to overcome ageing and obsolescence problems. Major achievements and milestones will also be elaborated in this paper. (author)

Fast Spectrum Reactors

CERN Document Server

Todd, Donald; Tsvetkov, Pavel

2012-01-01

Fast Spectrum Reactors presents a detailed overview of world-wide technology contributing to the development of fast spectrum reactors. With a unique focus on the capabilities of fast spectrum reactors to address nuclear waste transmutation issues, in addition to the well-known capabilities of breeding new fuel, this volume describes how fast spectrum reactors contribute to the wide application of nuclear power systems to serve the global nuclear renaissance while minimizing nuclear proliferation concerns. Readers will find an introduction to the sustainable development of nuclear energy and the role of fast reactors, in addition to an economic analysis of nuclear reactors. A section devoted to neutronics offers the current trends in nuclear design, such as performance parameters and the optimization of advanced power systems. The latest findings on fuel management, partitioning and transmutation include the physics, efficiency and strategies of transmutation, homogeneous and heterogeneous recycling, in addit...

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1985-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1984 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, reactor physics experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, safeguards technology, and activities of the Committee on Reactor Physics. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

Matsuura, Shojiro; Nakahara, Yasuaki; Takano, Hideki

1982-09-01

Research and development activities in the Division of Reactor Engineering in fiscal 1981 are described. The work of the Division is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committee on Reactor Physics. (author)

Request for Naval Reactors Comment on Proposed PROMETHEUS Space Flight Nuclear Reactor High Tier Reactor Safety Requirements and for Naval Reactors Approval to Transmit These Requirements to Jet Propulsion Laboratory

International Nuclear Information System (INIS)

D. Kokkinos

2005-01-01

The purpose of this letter is to request Naval Reactors comments on the nuclear reactor high tier requirements for the PROMETHEUS space flight reactor design, pre-launch operations, launch, ascent, operation, and disposal, and to request Naval Reactors approval to transmit these requirements to Jet Propulsion Laboratory to ensure consistency between the reactor safety requirements and the spacecraft safety requirements. The proposed PROMETHEUS nuclear reactor high tier safety requirements are consistent with the long standing safety culture of the Naval Reactors Program and its commitment to protecting the health and safety of the public and the environment. In addition, the philosophy on which these requirements are based is consistent with the Nuclear Safety Policy Working Group recommendations on space nuclear propulsion safety (Reference 1), DOE Nuclear Safety Criteria and Specifications for Space Nuclear Reactors (Reference 2), the Nuclear Space Power Safety and Facility Guidelines Study of the Applied Physics Laboratory

Multi-purpose reactor

International Nuclear Information System (INIS)

1991-05-01

The Multi-Purpose-Reactor (MPR), is a pool-type reactor with an open water surface and variable core arrangement. Its main feature is plant safety and reliability. Its power is 22MW t h, cooled by light water and moderated by beryllium. It has platetype fuel elements (MTR type, approx. 20%. enriched uranium) clad in aluminium. Its cobalt (Co 60 ) production capacity is 50000 Ci/yr, 200 Ci/gr. The distribution of the reactor core and associated control and safety systems is essentially based on the following design criteria: - upwards cooling flow, to waive the need for cooling flow inversion in case the reactor is cooled by natural convection if confronted with a loss of pumping power, and in order to establish a superior heat transfer potential (a higher coolant saturation temperature); - easy access to the reactor core from top of pool level with the reactor operating at full power, in order to facilitate actual implementation of experiments. Consequently, mechanisms associated to control and safety rods s,re located underneath the reactor tank; - free access of reactor personnel to top of pool level with the reactor operating at full power. This aids in the training of personnel and the actual carrying out of experiments, hence: - a vast water column was placed over the core to act as radiation shielding; - the core's external area is cooled by a downwards flow which leads to a decay tank beyond the pool (for N 16 to decay); - a small downwards flow was directed to stream downwards from above the reactor core in order to drag along any possibly active element; and - a stagnant hot layer system was placed at top of pool level so as to minimize the upwards coolant flow rising towards pool level

Mirror reactor studies

International Nuclear Information System (INIS)

Moir, R.W.; Barr, W.L.; Bender, D.J.

1977-01-01

Design studies of a fusion mirror reactor, a fusion-fission mirror reactor, and two small mirror reactors are summarized. The fusion reactor uses 150-keV neutral-beam injectors based on the acceleration of negative ions. The injectors provide over 1 GW of continuous power at an efficiency greater than 80%. The fusion reactor has three-stage, modularized, Venetian blind, plasma direct converter with a predicted efficiency of 59% and a new concept for removal of the lune-shaped blanket: a crane is brought between the two halves of the Yin-Yang magnet, which are separated by a float. The design has desirable features such as steady-state operation, minimal impurity problems, and low first-wall thermal stress. The major disadvantage is low Q resulting in high re-circulating power and hence high cost of electrical power. However, the direct capital cost per unit of gross electrical power is reasonable [$1000/kW(e)]. By contrast, the fusion-fission reactor design is not penalized by re-circulating power and uses relatively near-term fusion technology being developed for the fusion power program. New results are presented on the Th- 233 U and the U- 239 Pu fuel cycles. The purpose of this hybrid is fuel production, with projected costs at $55/g of Pu or $127/g of 233 U. Blanket and cooling system designs, including an emergency cooling system, by General Atomic Company, lead us to the opinion that the reactor can meet expected safety standards for licensing. The smallest mirror reactor having only a shield between the plasma and the coil is the 4.2-m long fusion engineering research facility (FERF) designed for material irradiation. The smallest mirror reactor having both a blanket and shield is the 7.5-m long experimental power reactor (EPR), which has both a fusion and a fusion-fission version. (author)

Reactor Simulations for Safeguards with the MCNP Utility for Reactor Evolution Code

International Nuclear Information System (INIS)

Shiba, T.; Fallot, M.

2015-01-01

To tackle nuclear material proliferation, we conducted several proliferation scenarios using the MURE (MCNP Utility for Reactor Evolution) code. The MURE code, developed by CNRS laboratories, is a precision, open-source code written in C++ that automates the preparation and computation of successive MCNP (Monte Carlo N-Particle) calculations and solves the Bateman equations in between, for burnup or thermal-hydraulics purposes. In addition, MURE has been completed recently with a module for the CHaracterization of Radioactive Sources, called CHARS, which computes the emitted gamma, beta and alpha rays associated to any fuel composition. Reactor simulations could allow knowing how plutonium or other material generation evolves inside reactors in terms of time and amount. The MURE code is appropriate for this purpose and can also provide knowledge on associated particle emissions. Using MURE, we have both developed a cell simulation of a typical CANDU reactor and a detailed model of light water PWR core, which could be used to analyze the composition of fuel assemblies as a function of time or burnup. MURE is also able to provide, thanks to its extension MURE-CHARTS, the emitted gamma rays from fuel assemblies unloaded from the core at any burnup. Diversion cases of Generation IV reactors have been also developed; a design of Very High Temperature Reactor (a Pebble Bed Reactor (PBR), loaded with UOx, PuOx and ThUOx fuels), and a Na-cooled Fast Breeder Reactor (FBR) (with depleted Uranium or Minor Actinides in the blanket). The loading of Protected Plutonium Production (P3) in the FBR was simulated. The simulations of various reactor designs taking into account reactor physics constraints may bring valuable information to inspectors. At this symposium, we propose to show the results of these reactor simulations as examples of the potentiality of reactor simulations for safeguards. (author)

Reactor Sharing Program

International Nuclear Information System (INIS)

Tehan, Terry

2002-01-01

Support utilization of the RINSC reactor for student and faculty instructions and research. The Department of Energy award has provided financial assistance during the period 9/29/1995 to 5/31/2001 to support the utilization of the Rhode Island Nuclear Science Center (RINSC) reactor for student and faculty instruction and research by non-reactor owning educational institutions within approximately 300 miles of Narragansett, Rhode Island. Through the reactor sharing program, the RINSC (including the reactor and analytical laboratories) provided reactor services and laboratory space that were not available to the other universities and colleges in the region. As an example of services provided to the users: Counting equipment, laboratory space, pneumatic and in-pool irradiations, demonstrations of sample counting and analysis, reactor tours and lectures. Funding from the Reactor Sharing Program has provided the RINSC to expand student tours and demonstration programs that emphasized our long history of providing these types of services to the universities and colleges in the area. The funding have also helped defray the cost of the technical assistance that the staff has routinely provided to schools, individuals and researchers who have called on the RINSC for resolution of problems relating to nuclear science. The reactor has been featured in a Public Broadcasting System documentary on Pollution in the Arctic and how a University of Rhode Island Professor used Neutron Activation Analysis conducted at the RINSC to discover the sources of the ''Arctic Haze''. The RINSC was also featured by local television on Earth Day for its role in environmental monitoring

NUCLEAR REACTOR

Science.gov (United States)

Miller, H.I.; Smith, R.C.

1958-01-21

This patent relates to nuclear reactors of the type which use a liquid fuel, such as a solution of uranyl sulfate in ordinary water which acts as the moderator. The reactor is comprised of a spherical vessel having a diameter of about 12 inches substantially surrounded by a reflector of beryllium oxide. Conventionnl control rods and safety rods are operated in slots in the reflector outside the vessel to control the operation of the reactor. An additional means for increasing the safety factor of the reactor by raising the ratio of delayed neutrons to prompt neutrons, is provided and consists of a soluble sulfate salt of beryllium dissolved in the liquid fuel in the proper proportion to obtain the result desired.

EKA urbanistika osakond / Lilia del Rio

Index Scriptorium Estoniae

Rio, Lilia del

2006-01-01

Lilia del Rio magistritöö "Beyond the player's manual / Mänguõpetus edasijõudnutele. Experiencing the world (and the city) as a playground / Kogedes maailma (ja linna) mänguväljakuna". Juhendaja Andres Kurg

Technological status of reactor coolant pumps in generation III+ pressurized nuclear reactors

Energy Technology Data Exchange (ETDEWEB)

Brecht, Bernhard; Bross, Stephan [KSB Aktiengesellschaft, Frankenthal (Germany)

2016-05-15

KSB has been developing and producing pumps for thermal power plants for nearly 90 years. Consequently, KSB also started to develop and manufacture pumps for all kinds of nuclear power plants from the very beginning of the civil use of nuclear energy. This is especially true for reactor coolant pumps for pressurized water reactors. For the generation of advanced evolutionary reactors (Generation III+ reactors), KSB developed an advanced shaft seal system which is also able to fulfill the requirements of station blackout conditions. The tests in the KSB test rigs, which were successfully completed in December 2015, proved the full functionality of the new design. For generation III+ passive plant reactors KSB developed a new reactor coolant pump type called RUV, which is based on the experience of classic reactor coolant pumps and reactor internal pumps. It is a very compact, hermetically sealed vertical pump-motor unit with a wet winding motor. A full scale prototype successfully passed the 1st stage qualification test program in October 2015.

Reactor control device

International Nuclear Information System (INIS)

Fukami, Haruo; Morimoto, Yoshinori.

1981-01-01

Purpose: To operate a reactor always with safety operation while eliminating the danger of tripping. Constitution: In a reactor control device adapted to detect the process variants of a reactor, control a control rod drive controlling system based on the detected signal to thereby control the driving the control rods, control the reactor power and control the electric power generated from an electric generator by the output from the reactor, detection means is provided for the detection of the electric power from said electric generator, and a compensation device is provided for outputting control rod driving compensation signals to the control rod driving controlling system in accordance with the amount of variation in the detected value. (Seki, T.)

Research reactor DHRUVA

International Nuclear Information System (INIS)

Veeraraghaven, N.

1990-01-01

DHRUVA, a 100 MWt research reactor located at the Bhabha Atomic Research Centre, Bombay, attained first criticality during August, 1985. The reactor is fuelled with natural uranium and is cooled, moderated and reflected by heavy water. Maximum thermal neutron flux obtained in the reactor is 1.8 X 10 14 n/cm 2 /sec. Some of the salient design features of the reactor are discussed in this paper. Some important features of the reactor coolant system, regulation and protection systems and experimental facilities are presented. A short account of the engineered safety features is provided. Some of the problems that were faced during commissioning and the initial phase of power operation are also dealt upon

A fragilidade do Ministério da Defesa brasileiro

Directory of Open Access Journals (Sweden)

Jorge Zaverucha

2005-11-01

Full Text Available O presente artigo apresenta os diversos momentos por que passou o Ministério da Defesa, desde sua criação no segundo mandato presidencial de Fernando Henrique Cardoso (1999-2002 até o atual governo de Luís Inácio Lula da Silva (2003-2006, com os respectivos ministros da Defesa. Visto como uma etapa importante na reconstitucionalização do país, na medida em que prevê a submissão dos comandantes das Forças Armadas a um ministro civil, e embora alguns analistas considerem que essa submissão de fato ocorre, procuramos indicar as resistências e as insubordinações militares ao poder civil, provenientes de um legado autoritário. Na medida em que o Ministério da Defesa não consegue implementar uma política própria, em que os militares seguiriam as orientações dos civis, o artigo conclui considerando a fragilidade política e institucional do Ministro da Defesa, civil, ante o os comandos militares, que conservam alto grau de autonomia decisória em relação à estrutura do Ministério.

Produtos e serviços bancários

OpenAIRE

Álvaro Modernell

2009-01-01

Guia com informações sobre produtos e serviços bancários que estão à disposição dos cidadãos brasileiros com a finalidade de facilitar o seu dia-a-dia. O documento é uma cartilha educativa preparada para clientes da CAIXA, uma instituição pública de poupança e crédito. O guia foi produzido como parte do "Programa de Remessas e Capacitação para Emigrantes Brasileiros e seus Beneficiários no Brasil".

Fully integrated analysis of reactor kinetics, thermalhydraulics and the reactor control system in the MAPLE-X10 research reactor

International Nuclear Information System (INIS)

Shim, S.Y.; Carlson, P.A.; Baxter, D.K.

1992-01-01

A prototype research reactor, designated MAPLE-X10 (Multipurpose Applied Physics Lattice Experimental - X 10MW), is currently being built at AECL's Chalk River Laboratories. The CATHENA (Canadian Algorithm for Thermalhydraulic Network Analysis) two-fluid code was used in the safety analysis of the reactor to determine the adequacy of core cooling during postulated reactivity and loss-of-forced-flow transients. The system responses to a postulated transient are predicted including the feedback between reactor kinetics, thermalhydrauilcs and the reactor control systems. This paper describes the MAPLE-X10 reactor and the modelling methodology used. Sample simulations of postulated loss-of-heat-sink and loss-of-regulation transients are presented. (author)

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

International Nuclear Information System (INIS)

Lee, Byeonghee; Yang, Soohyung

2013-01-01

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

Investigation of the basic reactor physics characteristics of the Dalat Nuclear Research Reactor

Energy Technology Data Exchange (ETDEWEB)

Huy, Ngo Quang [Centre for Nuclear Technique Application, Ho Chi Minh City (Viet Nam); Thong, Ha Van; Khang, Ngo Phu [Nuclear Research Inst., Da Lat (Viet Nam)

1994-10-01

The Dalat nuclear research reactor was reconstructed from TRIGA MARK II reactor, built in 1963 with nominal power of 250 KW, and reached its planned nominal power of 500 kW for the first time in Feb. 1984. The Dalat reactor has some characteristics distinct from the former TRIGA reactor. Investigation of its characteristics is carried out by the determination of the reactor physics parameters. This paper represents the experimental results obtained for the effective fraction of the delayed photoneutrons, the extraneous neutron source left after the reactor is shut down, the lowest power levels of reactor critical states, the relative axial and radial distributions of thermal neutrons, the safe positive reactivity inserted into the reactor at deep subcritical state, the reactivity temperature coefficient of water, the temperature on the surface of the fuel elements, etc. (author). 10 refs., 10 figs., 2 tabs.

The Transport of Gmelina Logs on the Rio Dulce

Energy Technology Data Exchange (ETDEWEB)

Ensminger, J.T.; Martines, R.; Perlack, B.; Ranney, J.

1997-02-01

The Rio Dulce National Park is one of Guatemala's major environmental assets. The park contains the remaining remnants of an eastern Guatemalan tropical rainforest which has good but fast deteriorating value for the development of the ecotourism industry. The governmenial objective for the region as stated in the Master Plan for the park is ecotourism development and protection of biodiversity. The decisions to be made concerning the long-term, sustainable use of the natural resources of the Rio Dulce region appear to be directed by existing environmental laws and the Rio Dulce Master Plan. However, the wording of these instruments is ambiguous and lacks specific definitions and criteria for making necessary determinations. This, in combination with lack of enforcement in the region, has led to extensive disparity in interpretation of the laws and uncontrolled, conflicting actions by individuals and organizations.

Avaliação do controle externo da qualidade nos laboratórios clínicos do Rio de Janeiro de 2006 a 2008 Evaluation of external quality assessment in clinical laboratories from Rio de Janeiro in the years 2006-2008

Directory of Open Access Journals (Sweden)

Josefa Sieira Caamaño Chaves

2010-10-01

Full Text Available INTRODUÇÃO: O Controle Externo da Qualidade (CEQ é uma ferramenta importante para a garantia da qualidade das análises laboratoriais, auxiliando o laboratório a avaliar a eficiência da fase analítica de seus processos. Um resultado errôneo de uma análise prejudica a conclusão do diagnóstico de uma enfermidade e a indicação correta do tratamento a ser tomado. As inspeções sanitárias em laboratórios clínicos (LCs no estado do Rio de Janeiro são feitas com base no roteiro de inspeção sanitária publicado pela Portaria SES/CVS 743, de junho de 2006, na RDC 302/2005 e legislação vigente. Os resultados observados quanto ao CEQ, do total de 347 inspeções realizadas pelo Setor de Laboratórios de Análises Clínicas da Secretaria de Saúde e Defesa Civil (LAC-SESDEC no decorrer dos anos pesquisados, são apresentados a seguir: em 2006, entre as 133 inspeções realizadas em Laboratórios de Análises Clínicas, 44% dos estabelecimentos não possuíam contrato com provedor de ensaios de proficiência (EPs; em 2007, entre as 95 inspeções realizadas em Laboratórios de Análises Clínicas, 38% não possuíam contrato com provedor de EPs; em 2008, entre as 119 inspeções realizadas em Laboratórios de Análises Clínicas, 35% não possuíam contrato com provedor de EPs. Dos 214 laboratórios clínicos inspecionados nos anos de 2007 e 2008, 62% (134 estabelecimentos possuíam CEQ, entretanto, desses 134 estabelecimentos, 65% não registravam as ações corretivas relacionadas com as não conformidades detectadas em relatório emitido pelo provedor de EPs. MÉTODO: No presente estudo, foi avaliada a distribuição percentual dos resultados das inspeções sanitárias realizadas em LCs no estado do Rio de Janeiro de 2006 a 2008, cadastrados na Secretaria Estadual de Saúde e Defesa Civil (SESDEC, relacionando o número de LCs que não atendem às exigências sanitárias, item: "Controle Externo da Qualidade - CEQ da Portaria 743

Reactor safety device

International Nuclear Information System (INIS)

Okada, Yasumasa.

1987-01-01

Purpose: To scram control rods by processing signals from a plurality of temperature detectors and generating abnormal temperature warning upon occurrence of abnormal temperature in a nuclear reactor. Constitution: A temperature sensor comprising a plurality of reactors each having a magnetic body as the magnetic core having a curie point different from each other and corresponding to the abnormal temperature against which reactor core fuels have to be protected is disposed in an identical instrumentation well near the reactor core fuel outlet/inlet of a reactor. A temperature detection device actuated upon detection of an abnormal temperature by the abrupt reduction of the reactance of each of the reactors is disposed. An OR circuit and an AND circuit for conducting OR and AND operations for each of the abnormal temperature detection signals from the temperature detection device are disposed. The output from the OR circuit is used as the abnormal temperature warning signal, while the output from the AND circuit is utilized as a signal for actuating the scram operation of control rod drive mechanisms. Accordingly, it is possible to improve the reliability of the reactor scram system, particularly, improve the reliability under a high temperature atmosphere. (Kamimura, M.)

Ajustamento EstratÃgico do Setor BancÃrio ao Plano Real

OpenAIRE

Maria Elisangela Rodrigues dos Santos

2004-01-01

Este estudo evendicia as transformaÃÃes ocorridas no setor bancÃrio apÃs o Plano Real, originado em 01 de Julho de 1994. Essas transformaÃÃes proporcionaram impactos no sistema bancÃrio, dando inÃcio a um amplo processo de reforma estrutural ocasionado por modificaÃÃes de aÃÃes exÃgenas macroeconÃmicas. Com inÃcio do Plano, sabia-se que o novo ambiente de estabilizaÃÃo econÃmico do paÃs nÃo seria condizente com a dimensÃo que o sistema bancÃrio havia alcanÃado, fruto de vÃrios anos de inflaÃÃ...

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1980-09-01

Research activities in the Division of Reactor Engineering in fiscal 1979 are described. The work of the Division is closely related to development of multi-purpose Very High Temperature Gas Cooled Reactor and fusion reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and fusion reactor technology, and activities of the Committees on Reactor Physics and on Decomissioning of Nuclear Facilities. (author)

Reactor scram device for FBR type reactor

International Nuclear Information System (INIS)

Kumasaka, Katsuyuki; Arashida, Genji; Itooka, Satoshi.

1991-01-01

In a control rod attaching structure in a reactor scram device of an FBR type reactor, an anti-rising mechanism proposed so far against external upward force upon occurrence of earthquakes relies on the engagement of a mechanical structure but temperature condition is not taken into consideration. Then, in the present invention, a material having curie temperature characteristics and which exhibits ferromagnetism only under low temperature condition and a magnet device are disposed to one of a movable control rod and a portion secured to the reactor. Alternatively, a bimetal member or a shape memory alloy which actuates to fix to the mating member only under low temperature condition is secured. The fixing device is adapted to operate so as to secure the control rods when the low temperature state is caused depending on the temperature condition. With such a constitution, when the control rods are separated from a driving device, they are prevented from rising even if they undergo external upward force due to earthquakes and so on, which can improve the reactor safety. (N.H.)

Nuclear reactor engineering: Reactor systems engineering. Fourth edition, Volume Two

International Nuclear Information System (INIS)

Glasstone, S.; Sesonske, A.

1994-01-01

This new edition of this classic reference combines broad yet in-depth coverage of nuclear engineering principles with practical descriptions of their application in the design and operation of nuclear power plants. Extensively updated, the fourth edition includes new materials on reactor safety and risk analysis, regulation, fuel management, waste management and operational aspects of nuclear power. This volume contains the following: the systems concept, design decisions, and information tools; energy transport; reactor fuel management and energy cost considerations; environmental effects of nuclear power and waste management; nuclear reactor safety and regulation; power reactor systems; plant operations; and advanced plants and the future

Refuelling nuclear reactors

International Nuclear Information System (INIS)

Stacey, J.; Webb, J.; White, W.P.; McLaren, N.H.

1981-01-01

An improved nuclear reactor refuelling machine is described which can be left in the reactor vault to reduce the off-load refuelling time for the reactor. The system comprises a gripper device rangeable within a tubular chute, the gripper device being movable by a pantograph. (U.K.)

Compilation of reactor physics data of the year 1984, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-12-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1984 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Compilation of reactor physics data of the year 1983, AVR reactor

International Nuclear Information System (INIS)

Werner, H.; Bergerfurth, A.; Thomas, F.; Geskes, B.

1985-06-01

The 'AVR reactor physics data' is a documentation published once a year, the data presented being obtained by a simulation of reactor operation using the AVR-80 numerical model. This model is constantly updated and improved in response to new results and developments in the field of reactor theory and thermohydraulics, and in response to theoretical or practical modifications of reactor operation or in the computer system. The large variety of measured data available in the AVR reactor simulation system also makes it an ideal testing system for verification of the computing programs presented in the compilation. A survey of the history of operations in 1983 and a short explanation of the computerized simulation methods are followed by tables and graphs that serve as a source of topical data for readers interested in the physics of high-temperature pebble-bed reactors. (orig./HP) [de

Reactor containment

International Nuclear Information System (INIS)

Kawabe, Ryuhei; Yamaki, Rika.

1990-01-01

A water vessel is disposed and the gas phase portion of the water vessel is connected to a reactor container by a pipeline having a valve disposed at the midway thereof. A pipe in communication with external air is extended upwardly from the liquid phase portion to a considerable height so as to resist against the back pressure by a waterhead in the pipeline. Accordingly, when the pressure in the container is reduced to a negative level, air passes through the pipeline and uprises through the liquid phase portion in the water vessel in the form of bubbles and then flows into the reactor container. When the pressure inside of the reactor goes higher, since the liquid surface in the water vessel is forced down, water is pushed up into the pipeline. Since the waterhead pressure of a column of water in the pipeline and the pressure of the reactor container are well-balanced, gases in the reactor container are not leaked to the outside. Further, in a case if a great positive pressure is formed in the reactor container, the inner pressure overcomes the waterhead of the column of water, so that the gases containing radioactive aerosol uprise in the pipeline. Since water and the gases flow being in contact with each other, this can provide the effect of removing aerosol. (T.M.)

Multipurpose research reactors

International Nuclear Information System (INIS)

1988-01-01

The international symposium on the utilization of multipurpose research reactors and related international co-operation was organized by the IAEA to provide for information exchange on current uses of research reactors and international co-operative projects. The symposium was attended by about 140 participants from 36 countries and two international organizations. There were 49 oral presentations of papers and 24 poster presentations. The presentations were divided into 7 sessions devoted to the following topics: neutron beam research and applications of neutron scattering (6 papers and 1 poster), reactor engineering (6 papers and 5 posters), irradiation testing of fuel and material for fission and fusion reactors (6 papers and 10 posters), research reactor utilization programmes (13 papers and 4 posters), neutron capture therapy (4 papers), neutron activation analysis (3 papers and 4 posters), application of small reactors in research and training (11 papers). A separate abstract was prepared for each of these papers. Refs, figs and tabs

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1978-10-01

Research activities in the Division of Reactor Engineering in fiscal 1977 are described. Works of the Division are development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and development of Liquid Metal Fast Breeder Reactor for Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and Committee on Reactor Physics. (Author)

An internally illuminated monolith reactor: Pros and cons relative to a slurry reactor

NARCIS (Netherlands)

Carneiro, Joana T.; Carneiro, J.T.; Berger, Rob; Moulijn, Jacob A.; Mul, Guido

2009-01-01

In the present study, kinetic models for the photo-oxidation of cyclohexane in two different photoreactor systems are discussed: a top illumination reactor (TIR) representative of a slurry reactor, and the so-called internally illuminated monolith reactor (IIMR) representing a reactor containing

Undergraduate reactor control experiment

International Nuclear Information System (INIS)

Edwards, R.M.; Power, M.A.; Bryan, M.

1992-01-01

A sequence of reactor and related experiments has been a central element of a senior-level laboratory course at Pennsylvania State University (Penn State) for more than 20 yr. A new experiment has been developed where the students program and operate a computer controller that manipulates the speed of a secondary control rod to regulate TRIGA reactor power. Elementary feedback control theory is introduced to explain the experiment, which emphasizes the nonlinear aspect of reactor control where power level changes are equivalent to a change in control loop gain. Digital control of nuclear reactors has become more visible at Penn State with the replacement of the original analog-based TRIGA reactor control console with a modern computer-based digital control console. Several TRIGA reactor dynamics experiments, which comprise half of the three-credit laboratory course, lead to the control experiment finale: (a) digital simulation, (b) control rod calibration, (c) reactor pulsing, (d) reactivity oscillator, and (e) reactor noise

Advances in reactor physics education: Visualization of reactor parameters

International Nuclear Information System (INIS)

Snoj, L.; Kromar, M.; Zerovnik, G.

2012-01-01

Modern computer codes allow detailed neutron transport calculations. In combination with advanced 3D visualization software capable of treating large amounts of data in real time they form a powerful tool that can be used as a convenient modern educational tool for reactor operators, nuclear engineers, students and specialists involved in reactor operation and design. Visualization is applicable not only in education and training, but also as a tool for fuel management, core analysis and irradiation planning. The paper treats the visualization of neutron transport in different moderators, neutron flux and power distributions in two nuclear reactors (TRIGA type research reactor and a typical PWR). The distributions are calculated with MCNP and CORD-2 computer codes and presented using Amira software. (authors)

Exploratory Practice: Work at the Cultural Inglesa, Rio de Janeiro, Brazil.

Science.gov (United States)

Allwright, Dick; Lenzuen, Rosa

1997-01-01

Focuses on the aim of the Cultural Inglesa, Rio de Janeiro, Brazil, which is the development of a new, fully sustainable concept for classroom-based research--exploratory practice--and its assimilation into the normal working and professional-development practices of Rio Cultura teachers. (Author/VWL)

Heating effects in Rio Blanco rock

International Nuclear Information System (INIS)

Taylor, R.W.; Bowen, D.W.; Rossler, P.E.

1975-01-01

Samples of ''sandstone'' from near the site of the upper Rio Blanco nuclear explosion were heated in the laboratory at temperatures between 600 and 900 0 C. The composition and amount of noncondensable (dry) gas released were measured and compared to the amount and composition of gas found underground following the explosion. The gas released from the rock heated in the laboratory contained approximately 80 percent CO 2 and 10 percent H 2 ; the balance was CO and CH 4 . With increasing temperature, the amounts of CO 2 , CO, and H 2 released increased. The composition of gas released by heating Rio Blanco rock in the laboratory is similar to the composition of gas found after the nuclear explosion except that it contains less natural gas (CH 4 , C 2 H 6 . . .). The amount of noncondensable gas released by heating the rock increases from approximately 0.1 mole/kg of rock at 600 0 C to 0.9 mole/kg at 900 0 C. Over 90 percent of the volatile components of the rock are released in less than 10 h at 900 0 C. A comparison of the amount of gas released by heating rock in the laboratory to the amount of gas released by the heat of the Rio Blanco nuclear explosion suggests that the explosion released the volatile material from about 0.42 mg of rock per joule of explosive energy (1700 to 1800 tonnes per kt). (auth)

A new species of Hisonotus (Siluriformes, Loricariidae from rio São Francisco basin, Brazil

Directory of Open Access Journals (Sweden)

Fábio Roxo

2015-04-01

Full Text Available A new species of Hisonotus is described from the rio São Francisco basin. The new species can be distinguished from congeners by having (1 a unique coloration pattern of caudal fin with one black spot extending from its origin to the ventral lobe and two dark spots at the end of the lobe’s rays; (2 odontodes forming longitudinally aligned rows on head and trunk; (3 a functional V-shaped spinelet; (4 a single rostral plate at the tip of the snout; (5 by lacking contrasting dark geometric spots on the anterodorsal region of the body; (6 a lower caudal-peduncle depth; and (7 lower counts of the lateral median plates and (8 higher premaxillary and dentary teeth. The new species is the second described species of the genus Hisonotus in the rio São Francisco basin. It was found inhabiting the marginal vegetation of the rio São Francisco and three of its tributary, rio das Velhas, rio Paraopeba and rio Formoso.

Reactor feedwater system

International Nuclear Information System (INIS)

Hikabe, Katsumi.

1978-01-01

Purpose: In order to prevent thermal stresses of a core of PWR type reactor, described has been a method for feeding heated recirculating water to the core in the case of the reactor start-up or shut-down. Constitution: A recirculating water is degassed, cleaned up and heated in the steam condensers, and then feeds the water to the reactor, characterized in that heaters are provided in the bypasses of the turbine, so that heated water is constantly supplied to the reactor. (Nakamura, S.)

New reactor concepts

International Nuclear Information System (INIS)

Meskens, G.; Govaerts, P.; Baugnet, J.-M.; Delbrassine, A.

1998-11-01

The document gives a summary of new nuclear reactor concepts from a technological point of view. Belgium supports the development of the European Pressurized-Water Reactor, which is an evolutionary concept based on the European experience in Pressurized-Water Reactors. A reorientation of the Belgian choice for this evolutionary concept may be required in case that a decision is taken to burn plutonium, when the need for flexible nuclear power plants arises or when new reactor concepts can demonstrate proved benefits in terms of safety and cost

Nuclear reactor design

CERN Document Server

2014-01-01

This book focuses on core design and methods for design and analysis. It is based on advances made in nuclear power utilization and computational methods over the past 40 years, covering core design of boiling water reactors and pressurized water reactors, as well as fast reactors and high-temperature gas-cooled reactors. The objectives of this book are to help graduate and advanced undergraduate students to understand core design and analysis, and to serve as a background reference for engineers actively working in light water reactors. Methodologies for core design and analysis, together with physical descriptions, are emphasized. The book also covers coupled thermal hydraulic core calculations, plant dynamics, and safety analysis, allowing readers to understand core design in relation to plant control and safety.

Fission reactors and materials

International Nuclear Information System (INIS)

Frost, B.R.T.

1981-12-01

The American-designed boiling water reactor and pressurized water reactor dominate the designs currently in use and under construction worldwide. As in all energy systems, materials problems have appeared during service; these include stress-corrosion of stainless steel pipes and heat exchangers and questions regarding crack behavior in pressure vessels. To obtain the maximum potential energy from our limited uranium supplies is is essential to develop the fast breeder reactor. The materials in these reactors are subjected to higher temperatures and neutron fluxes but lower pressures than in the water reactors. The performance required of the fuel elements is more arduous in the breeder than in water reactors. Extensive materials programs are in progress in test reactors and in large test rigs to ensure that materials will be available to meet these conditions

Morphological diversity of fish along the rio das Velhas, Minas Gerais, Brazil

Directory of Open Access Journals (Sweden)

Nara Tadini Junqueira

2012-01-01

Full Text Available The rio das Velhas, located in central Minas Gerais State (Brazil, is a major tributary of the rio São Francisco. Despite several anthropogenic pressures, this basin supports more than 115 fish species. The aim of this study was to compare the morphological space occupied by fish assemblages in four regions (headwaters, upper, middle, and lower course along the channel of the rio das Velhas. We try to answer the following question: Is there a change in the morphological organization of the fish along the longitudinal gradient of the river? Individuals from 67 species, collected at several sites in the basin from 1999 to 2008, were measured for 11 morphological attributes related to swimming behavior and habitat use. Through the graphs, the first two dimensions of the PCA suggest that the morphological volume occupied by the headwaters region is smaller than the other sections, because of the low richness of the site. However, morphological hypervolumes of the four reaches analyzed by Euclidean distances were not statistically different. The results indicated that only the density of morphological types increases along the rio das Velhas, and there is no difference between the headwaters and upper courses. Therefore, in order to use functional groups related to the morphology of the species as tools to take measures for the conservation and revitalization of the rio das Velhas, it is necessary analyze the density of species within these groups, as well as their composition.O rio das Velhas, localizado na região central do estado de Minas Gerais (Brasil, é o mais extenso tributário do rio São Francisco. Apesar dos inúmeros impactos antrópicos que sofre, sua bacia abriga uma rica ictiofauna, com mais de 115 espécies conhecidas. O objetivo deste estudo foi comparar o espaço morfológico ocupado pelas assembleias de peixes em quatro regiões (cabeceira, alto curso, médio curso e baixo curso ao longo da calha do rio das Velhas. Procuramos

Spectral shift reactor control method

International Nuclear Information System (INIS)

Impink, A.J. Jr.

1981-01-01

A method of operating a nuclear reactor having a core and coolant displacer elements arranged in the core wherein is established a reator coolant temperature set point at which it is desired to operate said reactor and first reactor coolant temperature band limits are provided within which said set point is located and it is desired to operate said reactor charactrized in that said reactor coolant displacer elements are moved relative to the reactor core for adjusting the volume of reactor coolant in said core as said reactor coolant temperature approaches said first band limits thereby to maintain said reactor coolant temperature near said set point and within said first band limits

Method of operating a reactor

International Nuclear Information System (INIS)

Oosumi, Katsumi; Yamamoto, Michiyoshi.

1980-01-01

Purpose: To prevent stress corrosion cracking in the structural material of a reactor pressure vessel. Method: Prior to the starting of a reactor, the reactor pressure vessel is evacuated to carry out degassing of reactor water, and, at the same time, reactor water is heated. After reactor water is heated to a predetermined temperature, control rods are extracted to start nuclear heating. While the temperature of the reactor water is in a temperature range where elution of a metal which is a structural material of the reactor pressure vessel becomes vigorous and the sensitivity to the stress corrosion cracks increases, the reactor is operated at the maximum permissible temperature raising speed or maximum permissible cooling speed. (Aizawa, K.)

Reactor container

International Nuclear Information System (INIS)

Abe, Yoshihito; Sano, Tamotsu; Ueda, Sabuo; Tanaka, Kazuhisa.

1987-01-01

Purpose: To improve the liquid surface disturbance in LMFBR type reactors. Constitution: A horizontal flow suppressing mechanism mainly comprising vertical members is suspended near the free liquid surface of coolants in the upper plenum. The horizontal flow of coolants near the free liquid surface is reduced by the suppressing mechanism to effectively reduce the surface disturbance. The reduction in the liquid surface disturbance further prevails to the entire surface region with no particular vertical variations to the free liquid surface to remarkably improve the preventive performance for the liquid surface disturbance. Accordingly, it is also possible to attain the advantageous effects such as prevention for the thermal fatigue in reactor vessel walls, reactor upper mechanisms, etc. and prevention of burning damage to the reactor core due to the reduction of envolved Ar gas. (Kamimura, M.)

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1993-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1992 (April 1, 1992-March 31, 1993). The major Department's programs promoted in the year are the assessment of the high conversion light water reactor, the design activities of advanced reactor system and development of a high energy proton linear accelerator for the engineering applications including TRU incineration. Other major tasks of the Department are various basic researches on the nuclear data and group constants, the developments of theoretical methods and codes, the reactor physics experiments and their analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project were also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reactor engineering department annual report

International Nuclear Information System (INIS)

1990-09-01

This report summarizes the research and development activities in the Department of Reactor Engineering during the fiscal year of 1989 (April 1, 1989 - March 31, 1990). One of major Department's programs is the assessment of the high conversion light water reactor and the design activities of advanced reactor system. Development of a high energy proton linear accelerator for the nuclear engineering including is also TRU incineration promoted. Other major tasks of the Department are various basic researches on nuclear data and group constants, theoretical methods and code development, on reactor physics experiments and analyses, fusion neutronics, radiation shielding, reactor instrumentation, reactor control/diagnosis, thermohydraulics, technology assessment of nuclear energy and technology developments related to the reactor physics facilities. The cooperative works to JAERI's major projects such as the high temperature gas cooled reactor or the fusion reactor and to PNC's fast reactor project also progressed. The activities of the Research Committee on Reactor Physics are also summarized. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

Hirota, Jitsuya; Asaoka, Takumi; Suzuki, Tomoo; Mitani, Hiroshi; Akino, Fujiyoshi

1977-09-01

Research activities in the Division of Reactor Engineering in fiscal 1976 are described. Works of the division concern mainly the development of multi-purpose Very High Temperature Gas Cooled Reactor, fusion reactor engineering, and the development of Liquid Metal Fast Breeder Reactor in Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology, and activities of the Committee on Reactor Physics. (auth.)

Reactor Engineering Department annual report

International Nuclear Information System (INIS)

1984-08-01

Research and development activities in the Department of Reactor Engineering in fiscal 1983 are described. The work of the Department is closely related to development of multipurpose Very High Temperature Gas Cooled Reactor and Fusion Reactor, and development of Liquid Metal Fast Breeder Reactor carried out by Power Reactor and Nuclear Fuel Development Corporation. Contents of the report are achievements in fields such as nuclear data and group constants, theoretical method and code development, integral experiment and analysis, fusion neutronics, shielding, reactor and nuclear instrumentation, reactor control and diagnosis, and safeguards technology, and activities of the Committee on Reactor Physics. (author)

Reactor Engineering Division annual report

International Nuclear Information System (INIS)

1976-09-01

Research activities conducted in Reactor Engineering Division in fiscal 1975 are summarized in this report. Works in the division are closely related to the development of multi-purpose High-temperature Gas Cooled Reactor, the development of Liquid Metal Fast Breeder Reactor by Power Reactor and Nuclear Fuel Development Corporation, and engineering research of thermonuclear fusion reactor. Many achievements are described concerning nuclear data and group constants, theoretical method and code development, integral experiment and analysis, shielding, heat transfer and fluid dynamics, reactor and nuclear instrumentation, dynamics analysis and control method development, fusion reactor technology and activities of the Committee on Reactor Physics. (auth.)

Department of reactor technology

International Nuclear Information System (INIS)

1980-01-01

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

ANÁLISE DE CONTEÚDO DOS ITENS OBRIGATÓRIOS OU RECOMENDADOS E DE DIVULGAÇÃO ESPONTÂNEA NO RELATÓRIO DA ADMINISTRAÇÃO DAS COMPANHIAS ABERTAS

Directory of Open Access Journals (Sweden)

ALESSANDRA VASCONCELOS GALLON

2008-04-01

Full Text Available O artigo descreve a análise de conteúdo da evidenciação nos Relatórios da Administração das empresas participantes dos níveis de governança da Bovespa, relacionada aos itens obrigatórios pela Lei nº 6.404/76, recomendados pela CVM através do Parecer de Orientação nº 15/87 e outros itens de divulgação espontânea. A pesquisa caracteriza-se como descritiva, realizada por meio de análise documental, com análise de clusters. Os resultados mostram que as 55 companhias abertas brasileiras, participantes do nível 1 e 2 de governança e novo mercado da Bovespa, segundo o BDI nº 190/2005, independente do nível de governança, evidenciaram no Relatório de Administração de 2004 mais sentenças do tipo declarativa. Comparando-se o número de sentenças evidenciadas de itens obrigatórios e recomendados e de itens de divulgação espontânea, nota-se que a maior evidenciação é referente aos itens obrigatórios e recomendados. Conclui-se que os Relatórios da Administração das companhias abertas brasileiras apresentam níveis relativamente baixos de evidenciação voluntária.

Material test reactor fuel research at the BR2 reactor

Energy Technology Data Exchange (ETDEWEB)

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

2012-03-15

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

TERRITÓRIOS ALTERNATIVOS: ESPAÇOS FRONTEIRIÇOS E TRANSFRONTEIRIÇOS

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Jurany Leite Rueda

2017-06-01

Full Text Available O livro (Territórios Alternativos é uma coletânea resultante da trajetória do autor pelas trilhas da Geografia, e cobre o período de 1987 a 1998, promovendo um panorama sobre as discussões à volta do espaço geográfico e do território em suas diferentes dimensões.

Mortalidade por tuberculose e indicadores sociais no município do Rio de Janeiro Tuberculosis mortality and social indicatory in Rio de Janeiro city

Directory of Open Access Journals (Sweden)

Genésio Vicentin

2002-01-01

Full Text Available Este artigo estuda a mortalidade por tuberculose no município do Rio de Janeiro ocorrida no ano de 1991 em comparação com indicadores sociais. Utilizou-se o software SPSS 8.0 - 1997 na análise estatística dos dados, que mostrou a existência de correlação entre a maioria dos indicadores socioeconômicos estudados e o coeficiente de mortalidade por tuberculose por 100 mil habitantes/ano. Apresentaram correlação significativa e direta os indicadores: índice de Robin Hood, razão de renda entre os 10% mais ricos e os 40% mais pobres e proporção de chefes de família com renda média entre um e dois salários mínimos. A correlação foi inversa e significativa com os indicadores: proporção de residentes com mais de 10 anos com curso superior, área média por domicílio, número de cômodos por domicílio, renda média em salários mínimos, e proporção de chefes de família com rendas entre 10-15, 16-20 e acima de 20 salários mínimos. Para a apresentação destes indicadores usou-se mapas do município, categorizados e distribuídos por Regiões Administrativas, revelando distintos Rios de Janeiro, quando este é visto sob o ângulo social: da doença, ou de vários outros indicadores.Regional tuberculosis mortality levels and their Rio de Janeiro City principals social indicatories at year 1991 have been compared in this study. Software SPSS 8.0 - 1997 was applied on making statistical data analysis, and have disclosed a present correlation among most indicative socioeconomics trends and the annual tuberculosis mortality coeficient/100 thousand inhabitants. Others social indicatives than Robin Hood index, 10% more rich to 40% more poor reason, head of family proportion wich 1-2 minimum wage monthly gain, disclosed imediate and significative statistical assurance level. In reverse and significative statistical assurance level, resident proportion with more 10 years old that have superior course, house área average, room average

Reactor Safety Commission Code of Practice for Pressurized Water Reactors

International Nuclear Information System (INIS)

1990-01-01

The Reactor Safety Commission of the Federal German Republic has summarized in the form of Official Guidelines the safety requirements which, in the Commission's view, have to be met in the design, construction and operation of a nuclear power station equipped with a pressurized water reactor. The Third Edition of the RSK Guidelines for pressurized water reactors dated 14.10.81. is a revised and expanded version of the Second Edition dated 24.1.79. The Reactor Safety Commission will with effect from October 1981 use these Guidelines in consultations on the siting of and safety concept for the installation approval of future pressurized water reactors and will assess these nuclear power stations during their erection in the light of these Guidelines. They have not however been immediately conceived for the adaptation of existing nuclear power stations, whether under construction or in operation. The scope of application of these Guidelines to such nuclear power stations will have to be examined for each individual case. The main aim of the Guidelines is to simplify the consultation process within the reactor Safety Commission and to provide early advice on the safety requirements considered necessary by the Commission. (author)

Remote Reactor Monitoring

Energy Technology Data Exchange (ETDEWEB)

Bernstein, Adam [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dazeley, Steve [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Dobie, Doug [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Marleau, Peter [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Brennan, Jim [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Gerling, Mark [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sumner, Matthew [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sweany, Melinda [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2014-10-21

The overall goal of the WATCHMAN project is to experimentally demonstrate the potential of water Cerenkov antineutrino detectors as a tool for remote monitoring of nuclear reactors. In particular, the project seeks to field a large prototype gadolinium-doped, water-based antineutrino detector to demonstrate sensitivity to a power reactor at ~10 kilometer standoff using a kiloton scale detector. The technology under development, when fully realized at large scale, could provide remote near-real-time information about reactor existence and operational status for small operating nuclear reactors out to distances of many hundreds of kilometers.

The program of reactors and nuclear power plants; Programa de reactores y centrales nucleares

Energy Technology Data Exchange (ETDEWEB)

Calabrese, Carlos R [Comision Nacional de Energia Atomica, General San Martin (Argentina). Centro Atomico Constituyentes

2001-07-01

Into de framework of the program of research reactors and nuclear power plants, the operating Argentine reactors are described. The uses of the research reactors in Argentina are summarized. The reactors installed by Argentina in other countries (Peru, Algeria, Egypt) are briefly described. The CAREM project for the design and construction of an innovator small power reactor (27 MWe) is also described in some detail. The next biennial research and development program for reactor is briefly outlined.

Canada-India Reactor (CIR)

Energy Technology Data Exchange (ETDEWEB)

None

1960-12-15

Design information on the Canada-India Reactor is presented. Data are given on reactor physics, the core, fuel elements, core heat transfer, control, reactor vessel, fluid flow, reflector and shielding, containment, cost estimates, and research facilities. Drawings of vertical and horizontal sections of the reactor and fluid flow are included. (M.C.G.)

REACTOR: an expert system for diagnosis and treatment of nuclear reactor accidents

International Nuclear Information System (INIS)

Nelson, W.R.

1982-01-01

REACTOR is an expert system under development at EG and G Idaho, Inc., that will assist operators in the diagnosis and treatment of nuclear reactor accidents. This paper covers the background of the nuclear industry and why expert system technology may prove valuable in the reactor control room. Some of the basic features of the REACTOR system are discussed, and future plans for validation and evaluation of REACTOR are presented. The concept of using both event-oriented and function-oriented strategies for accident diagnosis is discussed. The response tree concept for representing expert knowledge is also introduced

Repositórios institucionais de acesso livre no Brasil: estudo Delfos

Directory of Open Access Journals (Sweden)

Ernani Rufino dos Santos Junior

2015-06-01

Full Text Available A filosofia do acesso livre ao conhecimento científico surgiu da dificuldade das bibliotecas universitárias de todo mundo em manter atualizadas as assinaturas das coleções de periódicos científicos. Os repositórios institucionais são uma das ferramentas que se mostram como alternativa para a comunicação da Ciência livre de barreiras de acesso. A pesquisa tem por objetivo verificar quais são as perspectivas futuras das atuais políticas de implementação de repositórios institucionais de acesso livre no Brasil na opinião de especialistas na área, tendo como base a análise do estado da arte das implementações de Repositórios Institucionais no Brasil. Neste trabalho, a pesquisa é dividida em três etapas: a primeira consiste na coleta de dados descritivos dos repositórios institucionais da Universidade de Brasília (RIUnB e do Superior Tribunal de Justiça (BDJur-STJ; já na segunda etapa de pesquisa, procede-se à consulta aos especialistas indagando-os acerca da situação atual das implementações de repositórios institucionais no Brasil; e, por fim, na terceira etapa de pesquisa consultamos estes mesmos especialistas sobre os desdobramentos futuros destas políticas no País. Utilizamos da técnica Delfos de pesquisa, onde os especialistas são consultados através de questionários constituídos de perguntas abertas, possibilitando assim chegar a um consenso das opiniões no final da pesquisa. Como resultado da pesquisa, é elaborado um quadro com a tabulação das respostas dos especialistas consultados revelando o panorama das perspectivas futuras das implementações de repositórios institucionais no Brasil na opinião dos especialistas que fazem parte da nossa amostra de pesquisa.

One piece reactor removal

International Nuclear Information System (INIS)

Chia, Wei-Min; Wang, Song-Feng

1993-01-01

The strategy of Taiwan Research Reactor Renewal plan is to remove the old reactor block with One Piece Reactor Removal (OPRR) method for installing a new research reactor in original building. In this paper, the engineering design of each transportation works including the work method, the major equipments, the design policy and design criteria is described and discussed. In addition, to ensure the reactor block is safety transported for storage and to guarantee the integrity of reactor base mat is maintained for new reactor, operation safety is drawn special attention, particularly under seismic condition, to warrant safe operation of OPRR. ALARA principle and Below Regulatory Concern (BRC) practice were also incorporated in the planning to minimize the collective dose and the total amount of radioactive wastes. All these activities are introduced in this paper. (J.P.N.)

Analysis of the time dependence of the tritium concentration in the Embalse Rio Tercero lake

International Nuclear Information System (INIS)

Lopez, F.O.; Bruno, H.A.

1998-01-01

In natural uranium and heavy water reactors, tritium is produced mainly as the activation product of the deuterium in the moderator and cooling medium. About 75% of the liquid effluents discharged by nuclear power plants in Argentina correspond to tritium. In the case of the Embalse nuclear power plant, the liquid effluents are discharged into the Rio Tercero reservoir. As its water is used for drinking, 98% of the dose received by the critical group is due to these discharges. A simple mathematical model was developed which predicts the variation in the tritium concentration in the reservoir. It is a complete mixture type model and the entry parameters are the lake volume, entrance volume and discharge volume. The model was solved by means of a Runge-Kutta method of second order. The chosen method is a modified Euler. A good correlation is observed when the values obtained by means of the numeric resolution of the developed model are compared with the values obtained by the tritium measurement made during the 1996 and 1997 environmental monitoring program. (author) [es

Nuclear reactors

International Nuclear Information System (INIS)

Middleton, J.E.

1977-01-01

Reference is made to water cooled reactors and in particular to the cooling system of steam generating heavy water reactors (SGHWR). A two-coolant circuit is described for the latter. Full constructural details are given. (U.K.)

Reactor decommissioning

International Nuclear Information System (INIS)

Lawton, H.

1984-01-01

A pioneering project on the decommissioning of the Windscale Advanced Gas-cooled Reactor, by the UKAEA, is described. Reactor data; policy; waste management; remote handling equipment; development; and recording and timescales, are all briefly discussed. (U.K.)

Status of advanced technology and design for water cooled reactors: Heavy water reactors

International Nuclear Information System (INIS)

1989-07-01

In 1987 the IAEA established the International Working Group on Advanced Technologies for Water-Cooled Reactors (IWGATWR). Within the framework of the IWGATWR the IAEA Technical Report on Status of Advanced Technology and Design for Water Cooled Reactors, Part I: Light Water Reactors and Part II: Heavy Water Reactors, has been undertaken to document the major current activities and trends of technological improvement and development for future water reactors. Part I of the report dealing with Light Water Reactors (LWRs) was published in 1988 (IAEA-TECDOC-479). Part II of the report covers Heavy Water Reactors (HWRs) and has now been prepared. This report is based largely upon submissions from Member States. It has been supplemented by material from the presentations at the IAEA Technical Committee and Workshop on Progress in Heavy Water Reactor Design and Technology held in Montreal, Canada, December 6-9, 1988. It is hoped that this part of the report, containing the status of advanced heavy water reactor technology up to 1988 and ongoing development programmes will aid in disseminating information to Member States and in stimulating international cooperation. Refs, figs and tabs

Compact torsatron reactors

International Nuclear Information System (INIS)

Lyon, J.F.; Carreras, B.A.; Lynch, V.E.; Tolliver, J.S.; Sviatoslavsky, I.N.

1988-05-01

Low-aspect-ratio torsatron configurations could lead to compact stellarator reactors with R 0 = 8--11m, roughly one-half to one-third the size of more conventional stellarator reactor designs. Minimum-size torsatron reactors are found using various assumptions. Their size is relatively insensitive to the choice of the conductor parameters and depends mostly on geometrical constraints. The smallest size is obtained by eliminating the tritium breeding blanket under the helical winding on the inboard side and by reducing the radial depth of the superconducting coil. Engineering design issues and reactor performance are examined for three examples to illustrate the feasibility of this approach for compact reactors and for a medium-size (R 0 ≅ 4 m,/bar a/ /approx lt/ 1 m) copper-coil ignition experiment. 26 refs., 11 figs., 7 tabs

RA Reactor applications, Annex A

International Nuclear Information System (INIS)

Cupac, S.; Vukadin, Z.

2000-01-01

Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

RA Reactor applications, Annex A

International Nuclear Information System (INIS)

Cupac, S.; Vukadin, Z.

1998-01-01

Full text: In 1998 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

RA Reactor applications, Annex A

International Nuclear Information System (INIS)

Cupac, S.; Vukadin, Z.

1996-01-01

Full text: In 2000 Ra reactor was not operated. New instrumentation is not complete, without it, it is not possible to think about reactor start-up. Since 1985, when reactor operation was forbidden, there are 480 fuel elements left in 48 fuel channels in the reactor core. Heavy water was removed from the reactor core because of the repair of the heavy water pumps in 1986. The old instrumentation was removed. Eleven years after being left to its own destiny, it would be difficult to imagine that anybody would think of reactor restart without examining the state of reactor vessel and other vital reactor components. Maintaining the reactor under existing conditions without final decision about restart or permanent shutdown is destructive for this nuclear facility. The existing state that pertains for more than 10 years would have only one result, destruction of the RA reactor [sr

Gas-cooled fast breeder reactor

International Nuclear Information System (INIS)

Yoshida, Hiroyuki

1982-07-01

Almost all the R D works of gas-cooled fast breeder reactor in the world were terminated at the end of the year 1980. In order to show that the R D termination was not due to technical difficulties of the reactor itself, the present paper describes the reactor plant concept, reactor performances, safety, economics and fuel cycle characteristics of the reactor, and also describes the reactor technologies developed so far, technological problems remained to be solved and planned development schedules of the reactor. (author)

FBR type reactor core

International Nuclear Information System (INIS)

Tamiya, Tadashi; Kawashima, Katsuyuki; Fujimura, Koji; Murakami, Tomoko.

1995-01-01

Neutron reflectors are disposed at the periphery of a reactor core fuel region and a blanket region, and a neutron shielding region is disposed at the periphery of them. The neutron reflector has a hollow duct structure having a sealed upper portion, a lower portion opened to cooling water, in which a gas and coolants separately sealed in the inside thereof. A driving pressure of a primary recycling pump is lowered upon reduction of coolant flow rate, then the liquid level of coolants in the neutron reflector is lowered due to imbalance between the driving pressure and a gas pressure, so that coolants having an effect as a reflector are eliminated from the outer circumference of the reactor core. Therefore, the amount of neutrons leaking from the reactor core is increased, and negative reactivity is charged to the reactor core. The negative reactivity of the neutron reflector is made greater than a power compensation reactivity. Since this enables reactor scram by using an inherent performance of the reactor core, the reactor core safety of an LMFBR-type reactor can be improved. (I.N.)

A prova no processo administrativo tributário

Directory of Open Access Journals (Sweden)

Adriano Ribeiro Caldas

2014-12-01

Full Text Available O objetivo deste trabalho é discutir o papel da prova no âmbito do processo administrativo tributário, assim como os limites para a sua apresentação e a distribuição do ônus de sua produção. Para tanto, serão analisados os institutos da preclusão e da presunção, partindo-se sempre dos princípios aplicáveis ao processo administrativo tributário, notadamente os princípios do devido processo legal, da verdade material e do formalismo moderado.

Interactieve ontwerpmethodieken voor integrale duurzaamheid Toepassing van RIO in een aantal niet-veehouderij-gebonden cases

NARCIS (Netherlands)

Bos, A.P.; Annevelink, E.; Bos, H.L.; Keijsers, E.R.P.; Maas, van der M.P.; Poot, E.H.; Vermeulen, T.; Raaphorst, M.G.M.; Maas, van der A.A.; Schoorlemmer, H.B.; Dijk, van S.M.

2013-01-01

RIO (Reflexief Interactief Ontwerpen) bestaat uit drie hoofdonderdelen: de (systeem)analysefase, de ontwerpfase en de verankeringsfase. RIO is ontstaan in een veehouderijcontext. Die context heeft een aantal specifieke eigenschappen, die toepassing van RIO in andere sectoren niet volledig

Reactor operation method

International Nuclear Information System (INIS)

Osumi, Katsumi; Miki, Minoru.

1979-01-01

Purpose: To prevent stress corrosion cracks by decreasing the dissolved oxygen and hydrogen peroxide concentrations in the coolants within a reactor container upon transient operation such as at the start-up or shutdown of bwr type reactors. Method: After a condensate has been evacuated, deaeration operation is conducted while opening a main steam drain line, as well as a main steam separation valve and a by-pass valve in a turbine by-pass line connecting the main steam line and the condenser without by way of a turbine, and the reactor is started-up by the extraction of control rods after the concentration of dissolved oxygen in the cooling water within a pressure vessel has been decreased below a predetermined value. Nuclear heating is started after the reactor water has been increased to about 150 0 C by pump heating after the end of the deaeration operation for preventing the concentration of hydrogen peroxide and oxygen in the reactor water from temporarily increasing immediately after the start-up. The corrosive atmosphere in the reactor vessel can thus be moderated. (Horiuchi, T.)

Nuclear reactor buildings

International Nuclear Information System (INIS)

Nagashima, Shoji; Kato, Ryoichi.

1985-01-01

Purpose: To reduce the cost of reactor buildings and satisfy the severe seismic demands in tank type FBR type reactors. Constitution: In usual nuclear reactor buildings of a flat bottom embedding structure, the flat bottom is entirely embedded into the rock below the soils down to the deck level of the nuclear reactor. As a result, although the weight of the seismic structure can be decreased, the amount of excavating the cavity is significantly increased to inevitably increase the plant construction cost. Cross-like intersecting foundation mats are embedded to the building rock into a thickness capable withstanding to earthquakes while maintaining the arrangement of equipments around the reactor core in the nuclear buildings required by the system design, such as vertical relationship between the equipments, fuel exchange systems and sponteneous drainings. Since the rock is hard and less deformable, the rigidity of the walls and the support structures of the reactor buildings can be increased by the embedding into the rock substrate and floor responsivity can be reduced. This enables to reduce the cost and increasing the seismic proofness. (Kamimura, M.)