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Sample records for dos reis reactor

  1. Determination of the stability classes in Angra dos Reis

    International Nuclear Information System (INIS)

    Nicolli, D.; Miranda, I. de.

    1980-01-01

    The applicability of the methods for the calculation of atmospheric dispersion used in Angra dos Reis, (site of Angra I - reactor) is discussed. A review is made of the main meteorological parameters indicating turbulence, as well as of the methods presently em ployed for doing dispersion estimates. The turbulence indicator measured in Angra dos Reis and their utilization in the categorization of the stability conditions are discussed. The methods of the rate of vertical temperature variation and the fluctuation of the wind direction to calculate the concentration in the air, are used. The correlations existing between these two methods and their temporal and spacial variation are analysed. The analysis of one-year data allows the conclusion, that, due to the low wind velocity; in Angra dos Reis the fluctuation method is a good indicator of horizontal dispersion, but it does not allow the Knowledge of vertical stability which is better determined by the vertical gradient of temperature. Due to the local condition between the mountains and the sea, only experiments on atmospheric diffusion may indicate the better method for the calculation of local dispersion. (E.G.) [pt

  2. Isotopic and chemical investigations on Angra dos Reis

    International Nuclear Information System (INIS)

    Wasserburg, G.J.; Tera, F.; Papanastassiou, D.A.; Huneke, J.C.

    1977-01-01

    Extensive isotopic studies of Pb, Sr and Xe and chemical abundance measurements of K, Rb, Sr, Ba, Nd, Sm, U and Th for total meteorite and mineral separates of the Angra dos Reis achondrite are reported on. U-Pb, Th-Pb and Pb-Pb ages are concordant at 4.54 AE for the total meteorite and for high-purity whitlockite in Angra dos Reis. This establishes Angra dos Reis as an early planetary differentiate which has not been disturbed for these systems since 4.54 AE ago. Measured 87 Sr/ 86 Sr in pyroxene and whitlockite for Angra dos Reis (ADOR) are distinctly below BABI by two parts in 10 4 and only one part in 10 4 above the lowest 87 Sr/ 86 Sr (ALL) measured in an Allende inclusion. The difference in ADOR-ALL corresponds to an interval of condensation in the solar nebula of approximately 3 m.y. If 26 Al was the heat source for the magmatism on the parent planets of Angra dos Reis and the basaltic achondrites (BABI) then the relatively large difference in 87 Sr/ 86 Sr, BABI - ALL, must be the result of planetary evolution rather than condensation over approximately 10 m.y. Xe isotopic measurements confirm the presence of large amounts of 244 Pu-produced fission Xe and show that 244 Pu was enriched in the whitlockite relative to the pyroxene by a factor of approximately 18. Chemical element enrichment factors between the whitlockite and the fassaitic pyroxene in Angra dos Reis are presented. The enrichment factors demonstrate close analogy between the rare earth elements and their actinide analogs. The enrichment factor for Pu is intermediate to the enrichment factors of Nd and Sm. (Auth.)

  3. CASEMIRO DOS REIS FILHO E A EDUCAÇÃO BRASILEIRA CASEMIRO DOS REIS FILHO AND THE BRAZILIAN EDUCATION

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    Dermeval Saviani

    2001-12-01

    Full Text Available O presente artigo procura traçar a trajetória do Prof. Casemiro dos Reis Filho a partir da origem de seus pais, em Portugal, passando pela sua escolarização no interior de São Paulo, sua formação em pedagogia na USP, o doutorado na PUC-SP, sua atuação destacada no magistério do ensino fundamental, médio e superior, na produção científica, na administração universitária e na divulgação de pesquisas educacionais, evidenciando sua relevante contribuição ao desenvolvimento da educação brasileira.The present paper seeks to trace the itinerary of Prof. Casemiro dos Reis Filho from his parent's origins, in Portugal, passing by his school years in inland São Paulo, his formation in pedagogy at USP and his doctor's degree at PUC-SP. It also stresses his highly praised activities as a teacher in the primary, secondary and higher education, not to mention his scientific production, university administration and eforts to spread educational research, thus highlighting his crucial contribution to develop Brazilian education.

  4. Persistency of atmospheric diffusion conditions in Angra dos Reis - Brazil

    International Nuclear Information System (INIS)

    Nicolli, D.

    1981-12-01

    Based on a 2 year observation period, the diffusion conditions at the Almirante Alvaro Alberto N.P.P. site, in Angra dos Reis, are analized with respect to persistency as a function of the wind direction, the Pasquill stability class and the time of the day. The Pasquill stability class relates to the bulk vertical temperature gradient measured between 2m and 50m in the atmosphere; the wind direction is measured at 50m height. The persistency is defined in this report as the probability that the wind direction will remain longer than a given time in a sector without change in the diffusion category by more than a certain stage. During the day the persistency is mostly affected by the sea breeze with predominance of the unstable and neutral categories. At night the stable categories dominate. The alternating sea and land breezes disturb daily the trade wind field resulting in low persistency of the diffusion conditions. (Author) [pt

  5. Periods of high intensity rainfall and the safety of the Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Nicolli, D.

    1993-01-01

    The high precipitation rates aggravate the consequences of hypothetical accidental releases of radioactive material from the Angra dos Reis Nuclear Power Plant (NPP), as determined by probabilistic risk assessment. A 30-year rainfall series was analysed, aiming at calculating the probability of occurring a given amount q of precipitation during a certain period of n days. The nine highest precipitation amounts have also been determined. The results show there was a rainier climate in the '50 s and '60 s than in the '70 s and '80 s. The risk of catastrophic landslide has been enhanced as an environmental impact of the construction of the Rio-Santos highway and NPP which have not yet gone through an abnormal rainfall period. It has been suggested that criteria should be established to reduce the nuclear power and shut down the reactor when the precipitation accumulates to a dangerous limit. (author)

  6. Study of the influencies of Angra-1 nuclear power plant construction in Angra dos Reis

    International Nuclear Information System (INIS)

    Ferreira Netto, L.

    1982-01-01

    The report presents a comprehensive evaluation of the influence caused by Angra-1 Nuclear Power Plants (Central Nuclear Almirante Alvaro Alberto) construction on the Angra dos Reis City - Rio de Janeiro - Brazil. The analysis performed adopts a multi-dimensional methodology with four analysis dimensions: political-institutional, physical-territorial, social-economic and temporal. (author)

  7. Socio-environmental impacts of Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Rosa, L.P.; Hesles, J.B.S.

    1984-01-01

    Technological aspects and the social problematic inherent to implementation of nuclear power plants in Brazil are studied. it is showed the study in two levels: one of them, attacks aspects linked to nuclear energy and their risks in Brazil; the other one, treats of impacts of the Angra dos Reis nuclear power plants on the local comunity. (M.C.K.) [pt

  8. Electronuclear Medical Assistance Foundation: medical preparedness and response in Angra dos Reis / Brazil

    International Nuclear Information System (INIS)

    Leite, Teresa C.S.B.; Maurmo, Alexandre M.

    2009-01-01

    This paper relates the health's experience in training and response to accidents involving ionizing radiation at Almirante Alvaro Alberto's Nuclear Power Plant in Angra dos Reis. The response system is organized in the same way of others health's system with pre-hospital attendance, local hospital and referential hospital .We also discussing how we training health workers about this kid of special response. (author)

  9. Crystal-field spectra of fassaite from the Angra dos Reis meteorite

    Energy Technology Data Exchange (ETDEWEB)

    Mao, H K; Bell, P M; Virgo, D [Carnegie Institution of Washington, D.C. (USA)

    1977-06-01

    Fassaitic pyroxene from the Angra dos Reis meteorite has striking spectral properties. The /sup 57/Fe Moessbauer spectra show no Fe/sup 3 +/, and thus the absorption is thought to originate from a complex charge-transfer process. Intense absorption at 480 nm dominates the spectrum of the meteorite and may be important in the interpretation of telescope spectra of objects in space.

  10. Moraceae da Ilha Grande, Angra dos Reis, Rio de Janeiro, Brasil. Moraceae of Ilha Grande, Angra dos Reis, Rio de Janeiro, Brazil.

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    Leandro Cardoso PEDERNEIRAS

    2012-06-01

    Full Text Available Este trabalho apresenta o levantamento florístico das espécies nativas de Moraceae ocorrentes na Ilha Grande, município de Angra dos Reis, Estado do Rio de Janeiro, Brasil. Com base na análise de coleções científicas, revisão da literatura e excursões a campo, foram registradas 11 espécies nativas: Brosimum guianense, Dorstenia arifolia, Ficus adhatodifolia, F. arpazusa, F. cyclophylla, F. gomelleira, F. nevesiae, F. organensis, F. pulchella, Sorocea hilarii, S. guilleminiana. Apresentamos, também, a chave de identificação para os táxons, descrições, ilustrações, informações sobre a distribuição geográfica e comentários sobre as espécies. This work presents a floristic survey of native species of Moraceae occurring in Ilha Grande, municipality of Angra dos Reis, Rio de Janeiro state, Brazil. It was based on analysis of herbarium collections, literature review and the field excursions, resulting in 11 native species: Brosimum guianense, Dorstenia arifolia, Ficus adhatodifolia, F. arpazusa, F. cyclophylla, F. gomelleira, F. nevesiae, F. organensis, F. pulchella, Sorocea hilarii, S. guilleminiana. We also present the identification key to the taxa, descriptions, illustrations, information about geographic distribution and comments on these species that enriched the results.

  11. Off-site emergency response plans in case of technological catastrophes: the case Angra dos Reis

    International Nuclear Information System (INIS)

    Souza Junior, M.D. de.

    1990-04-01

    In the first part of the thesis a discussion of the technical, operational and methodological features of the current practices for emergency planning in case of a nuclear fallout. Based on this general reference is possible to evaluate the features in the natural and social environment of Angra dos Reis that probably will obstruct the application of the protective countermeasures to the public. These critical points are enhanced to permit the discussion of a methodological approach that is supposed to be suitable to the reality of Angra dos Reis. The approach was developed specifically to this region and was introduced as a part of the general emergency off-site plan to the Central Nuclear Almirante Alvaro Alberto (CNAAA). Starting from this experience will be possible to enlarge this approach in a further research, in order to study this potential hazards of other industrial plants. (author)

  12. Nuclear tracks in the Angra dos Reis and Moore County meteorites

    International Nuclear Information System (INIS)

    Carver, E.A.; Anders, E.

    1976-01-01

    Charged particle tracks were studied in the Angra dos Reis and Moore County meteorites, both of which contain an unexplained excess of He 4 . A selective annealing method was used to resolve cosmic-ray tracks from fission tracks. It gave the following cosmic-ray and fission-track densities, in units of 10 6 cm -2 : Angra dos Reis 1.3 to 4.4 and 7.8; Moore Co. feldspar 1.9 to 3.0 and 0.51; Moore Co. pigeonite 2.0 to 2.9 and 0.078 to 0.35. The fission-track densities are 10 to 100 times higher than expected from U 238 ; the excess is probably due to extinct Pu 244 . The Pu 244 /U 238 ratios at the start of track retention were 0.003 for Angra dos Reis and 0.002 to 0.03 got Moore Co. No evidence was found for fission tracks attributable to the unknown progenitor of excess He 4 in these meteorites; the fission branch of this progenitor comprises less than 10 -5 the α-branch. A search for pleochroic halos also gave negative results. The preatmospheric radii of the two meteorites are >= 13 and >= 7 cm. According to meteor theory, this implies geocentric velocities of >19 and >= 6 km/sec. The etching behaviour of Angra dos Reis augite is highly anomalous, giving rise to spurious angular anisotropies and skewed length distributions. This confirms similar observation by Fleischer et al (Proc. Apollo II Lunar Sci. Conf. Geochem. Cosmochim. Acta Suppl.; 1:2103 (1970)) on lunar augite. (author)

  13. Electronuclear Medical Assistance Foundation: medical preparedness and response in Angra dos Reis / Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Leite, Teresa C.S.B.; Maurmo, Alexandre M. [Fundacao Eletronuclear de Assistencia Medica, Angra dos Reis, RJ (Brazil)], e-mail: tleite@feam-etn.org.br, e-mail: maurmo@feam-etn.org.br

    2009-07-01

    This paper relates the health's experience in training and response to accidents involving ionizing radiation at Almirante Alvaro Alberto's Nuclear Power Plant in Angra dos Reis. The response system is organized in the same way of others health's system with pre-hospital attendance, local hospital and referential hospital .We also discussing how we training health workers about this kid of special response. (author)

  14. Determination of the safety zones of Angra dos Reis Nuclear Power Plant, according to the model of radion diffusion in the atmosphere

    International Nuclear Information System (INIS)

    Santina, M.D.

    1978-01-01

    The safety distance for Angra dos Reis Nuclear Power Plant are calculated, based on the model of the maximum credible accident for PWR power reactors and on the calculation of the dose due to hypothetical accidental release of radioactivity, using the model of radiation dispersion in the atmosphere. The safety distances for the Angra dos Reis reactors are also calculated using the model of the nine accident categories of the Rasmussen Report. The values of probability associated to each type of accident are used with the respective fractions of radiation release to the atmosphere. The soil contamination is also calculated for all the accidents considered and for several conditions of atmospheric stability, according to the model developed by Chamberlain. The program ACRA-II is used for calculation of the diffusion of radiation in the atmosphere, and the doses associated to it [pt

  15. Famílias escravas em Angra dos Reis, 1801-1888

    OpenAIRE

    Marcia Cristina Roma de Vasconcellos

    2006-01-01

    Em Angra dos Reis, a população local, na primeira metade do século XIX, dedicava-se ao autoconsumo e ao mercado interno. Desenvolveram-se o comércio e os transportes, pois seus portos foram um dos principais meios de escoamento do café do vale do Paraíba fluminense e paulista, dinamizando a vida econômica. Entretanto, ao longo da segunda metade do Oitocentos, instalou-se, gradativamente, um quadro de transformações econômicas e demográficas, resultante do término do tráfico de escravos e da d...

  16. Climatologia no Entorno da Central Nuclear de Angra dos Reis, RJ

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    João Batista Araujo Figueiredo

    Full Text Available Resumo Este trabalho tem por objetivo caracterizar os ciclos diurno e sazonal médios no entorno da Central Nuclear de Angra dos Reis. As condições médias são derivadas de dados horários, do período de janeiro de 2005 a dezembro de 2012. O local conta com quatro torres A, B, C e D. A Torre A mede vento e temperatura do ar a 10, 60 e 100 m e também precipitação, enquanto as demais torres medem somente vento a 15 m de altura. A atmosfera apresenta condições predominantemente estáveis ao longo do dia, com redução a partir das 6 e 7 h, sendo que condições instáveis predominam entre às 8 e 16 h no verão e primavera. Os ventos da região são predominantemente fracos, a maior frequência ocorre nas intensidades entre 1,5 e 2 m/s. O mínimo de intensidade dos ventos a 10 m ocorre no momento da entrada da brisa marítima, às 9 h. Os ventos catabáticos produzem um forte cisalhamento vertical dos ventos na região. Nas demais torres a máxima intensidade ocorre entre 13 e 15 h local. Ventos mais intensos e chuvas mais intensas foram registrados no outono (MAM, o que sugere ser este o período de tempestades mais intensas.

  17. Analysis of the emergency plan of Angra dos Reis Nuclear Power Plants: a critical view related to accessibility and mobility of people with special needs

    International Nuclear Information System (INIS)

    Correa, Luanda C.A.; Correa, Samanda C.A.; Santos, Geissa; Souza, Edmilson M.

    2014-01-01

    This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs

  18. Central nuclear almirante Alvaro Alberto: study on the phytoplanktonic variation in the region of unity 1 - Angra dos Reis - RJ

    International Nuclear Information System (INIS)

    Souza, C.A.F. de; Pessoa, M.A.R.; Utchitel, S.

    1988-01-01

    By according of ''staff'' which has elaborated the first works in phitoplankton, in initial phasis (before operation) of Central Nuclear Almirante Alvaro Alberto - CNAAA Unidade 1, Angra dos Reis, Rio de Janeiro, Brazil we carry out a search about physic - chemicals parameters at same area, during the times of 11 months, too. The efluent region presents a phytoplanktonic comunity of reasonable environmental conditions. The evaluation of biological parameters, or in the words, a natural environment in equilibrium. (author) [pt

  19. Maria Firmina dos Reis e seu conto Gupeva: uma breve digressão indianista

    Directory of Open Access Journals (Sweden)

    Rafael Balseiro Zin

    2017-07-01

    Full Text Available Se o tratamento que a escritora maranhense Maria Firmina dos Reis atribui às personagens negras e à questão da escravidão em seu romance inaugural Úrsula, publicado em 1859, e em seu conto A escrava, de 1887, é um tanto particular para a literatura brasileira produzida até aquele momento, em outro tema bastante em voga no período, o encontro da cultura europeia com a cultura indígena autóctone, ela também vai apresentar concepções distintas. Levando em consideração essa perspectiva, o presente artigo tem por objetivo analisar as ideias da autora contidas em seu conto indianista Gupeva, de 1861-2, uma vez que, nessa narrativa, ela se dedica a pensar o lugar destinado ao índio na sociedade brasileira oitocentista, no sentido de registrar a sua contribuição e de marcar o seu ideário acerca da questão nacional.

  20. Flebotomíneos de áreas com notificações de casos autóctones de leishmaniose visceral canina e leishmaniose tegumentar americana em Angra dos Reis, Rio de Janeiro, Brasil Phlebotomine fauna in areas of autochthonous cases of canine visceral leishmaniasis and American cutaneous leishmaniasis in Angra dos Reis, Rio de Janeiro, Brazil

    Directory of Open Access Journals (Sweden)

    Marcos Barbosa de Souza

    2009-01-01

    Full Text Available Flebótomos de áreas com notificações de casos autóctones de leishmaniose visceral canina e leishmaniose tegumentar americana em Angra dos Reis, Rio de Janeiro, Brasil. O município de Angra dos Reis apresenta casos humanos de leishmaniose tegumentar americana desde 1945. Inquéritos flebotomínicos realizados em 1978 revelaram a presença de Nyssomyia intermedia e a primeira notificação de Lutzomyia longipalpis no Rio de Janeiro, Ilha Grande, Angra dos Reis. Em agosto de 2002 foi notificado o primeiro caso canino de leishmaniose visceral na Ilha Grande, Angra dos Reis. Inquéritos flebotomínicos realizados nos peridomicílios, no período de novembro de 2002 a maio de 2003, em quatro localidades de Angra dos Reis, resultaram em 12.554 flebotomíneos e a presença de nove espécies: Brumptomyia sp.; Nyssomyia intermedia, Migonemyia migonei, Micropygomyia schreiberi, Pintomyia fischeri, Psychodopygus davisi, Psychodopygus ayrosai, Evandromyia tupinambay, Psathyromyia pelloni. foi Nyssomyia intermedia, predominante em todas as localidades, seguida por M.migonei. O principal vetor da LVA, Lutzomyia longipalpis, não foi detectado nas localidades, incluindo áreas do entorno, onde um cão infectado residia.The city of Angra dos Reis presents human cases of American cutaneous leishmaniasis since 1945. Phlebotomine surveys in 1978 had disclosed the presence of Nyssomyia intermedia and the first notification of Lutzomyia longipalpis in Rio de Janeiro, Ilha Grande, Angra dos Reis. In August of 2002 the first canine case of visceral leishmaniasis in the Ilha Grande, Angra dos Reis was notified. Surveys of phlebotomines in the peridomiciliary areas, in the period of November, 2002, through May, 2003, in four localities of Angra dos Reis, resulted in 12,554 specimens belonging to nine species: Brumptomyia sp. Nyssomyia intermedia, Migonemyia migonei, Micropygomyia schreiberi, Pintomyia fischeri, Psychodopygus davisi, Psychodopygus ayrosai

  1. Sucessão vegetal em uma encosta reflorestada com leguminosas arbóreas em Angra dos Reis, RJ Natural succession under a nitrogen-fixing legume trees stand in a hillside at Angra dos Reis - RJ, Brazil

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    Sylvia de Souza Chada

    2004-12-01

    Full Text Available Em uma encosta reflorestada há sete anos com leguminosas arbóreas (Acacia auriculiformis, A. mangium e Mimosa tenuiflora em Angra dos Reis, RJ, foi avaliada a composição florística e fitossociológica da regeneração natural, comparando-as com as de um fragmento de Mata Secundária situado a 200 m de distância. Foram considerados os três terços da encosta, com declividades decrescentes. Em 12 parcelas de 200 m², quatro em cada terço da encosta, foram amostrados 699 indivíduos vegetais a partir de 40 cm de altura, distribuídos em 25 famílias e 50 espécies. As famílias com maior nº de indivíduos foram Meliaceae (298, Euphorbiaceae (70, Piperaceae (64 e Lauraceae (41. Já as famílias com maior nº de espécies foram Solanaceae (7, Melastomataceae (5 e Myrtaceae (5. As leguminosas plantadas não estavam regenerando na própria área. A evolução da sucessão natural apresentou um gradiente de desenvolvimento em razão da menor declividade e menor distância dos remanescentes florestais, com maior densidade de indivíduos e maior riqueza de espécies na área de menor declividade.The floristic composition and natural regeneration under a 7-year-old legume tree plantation (Acacia auriculiformis, A. mangium e Mimosa tenuiflora was investigated in comparing with a secondary forest 200 m away at Angra dos Reis, RJ. The hillside was divided in 3 parts following the slope. The lower part of the hillside was the nearest to the natural forest remnant. In 12 plots with 200 m² each, 4 of them in each section of the hillside, 699 plants larger then 40 cm height were observed, distributed in 25 families and 50 species. The families with the most individuals were Meliaceae (298, Euphorbiaceae (70, Piperaceae (64 and Lauraceae (41. The families with the most species were Solanaceae (7, Melastomataceae (5 and Myrtaceae (5. None of the legume species introduced in the area had produced natural regeneration. The evolution of natural succession

  2. Selection of bioindicators for 90-Sr among the benthic marine algae from the Saco do Piraquara de Fora, Angra dos Reis, RJ (preliminary results)

    International Nuclear Information System (INIS)

    Azevedo, H.L.P. de; Vianna, M.E.C.; Monteiro, D.; Fernandes, H.; Gusmao Pedrini, A. de

    1983-01-01

    With the aim of pre-selecting bioindicators for Sr-90 among the marine algae, monthly sampling in three different fixed locations, have benn done and strontium and calcium concentrations have been determined in the most abundant species of algae in the region of Angra dos Reis. In order to establish the influence of seasonal variations, the sea water salinity and strontium and calcium concentrations have also been analysed. (E.G.) [pt

  3. Analysis of Particle Production in the Municipalities of Angra dos Reis, Campos and Petropolis in Rio de Janeiro

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    Sebastião Lourenço dos Santos João

    2014-12-01

    Full Text Available The productive clusters are currently constant reference in the research lines turn into strategic issue. Cities with production clusters have differentiated development in relation to other cities. This development has a direct influence on the location / installation and management of companies. This factor allows the organization gain a competitive advantage due to proximity to their suppliers and direct contact with the local population. With supplier companies increase the mobility of its supply chain and benefit from the existence of quality equipment in the network. This study aims to analyze, evaluate and classify the productive clusters of cities in the State of Rio de Janeiro, particularly in the municipalities of Angra dos Reis, Campos and Petropolis, to achieve balanced local development that benefits all stakeholders by product / city services. Productive clusters must necessarily contribute to improving the level of service offered to the customer. The methodology adopted was proposed by the Suzigan et al (2003 and Britto and Albuquerque (2002, to assess, analyze and classify the clusters in addition to bibliographic survey to support the study. The results show that depending on the importance of economic activity for the city, the production clusters greatly contribute to local development and increase the range of options for the local consumer.

  4. Behavior of Cs and Co in marine sediments of Enseada de Piraquara de Fora, Angra dos Reis, RJ, Brazil; Comportamento Cs e Co em sedimentos marinhos da Enseada de Piraquara de Fora - Angra dos Reis

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, I. M.; Carvalho, F. M.; Lauria, D.C., E-mail: dejanira@ird.gov.br [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro - RJ (Brazil)

    2017-07-01

    The release of {sup 137}Cs and {sup 60}Co in the liquid effluents from the Angra dos Reis power plants could radiologically impact the Saco de Piraquara de Fora (SPF) inlet. The mobility and trend of the radionuclides in the water-sediment compartment were investigated by studies of thermodynamic and sorption-desorption. The values of distribution coefficients (Kd) were around 500 L. kg{sup -1} for {sup 60}Co and 400 L. kg{sup -1} for {sup 137}Cs that are lower than the literature values. The predominance of kaolinite in the clay fraction may have played a major role in the low observed Kd values. For both radionuclides, the sorption was higher for the sediment with higher cation exchange capacity, and the equilibrium conditions were reached only after the third day. Despite the relatively low Kd values and low sorption rates, both can considerably be accumulated in sediments, and the sorption reactions are partially irreversible. {sup 60}Co and {sup 137}Cs accumulate in orders of magnitude of 1010 and 109 Bq g{sup -1} sediment, respectively, which shows the ability of the sediments to remove and retain much of the {sup 137}Cs and {sup 60}Co released by the power plants. Considering the range of temperature of the SPF water, both sorption and desorption of the two metals increase with temperature. However, in general, the retention rates of the radionuclides in sediments remain constant. The sorption sites are heterogeneous since the sorption data can be adjusted by the Langmuir and Freündlich isotherms. The sorption of Co and Cs are endothermic processes, which are spontaneous at low temperature. (author)

  5. Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil

    International Nuclear Information System (INIS)

    Barbosa, Alayde Alfaia

    2001-01-01

    The Saco do Bracui, located in the littoral zone of the Brazilian southeast, receives run off from the region of Angra dos Reis. Anthropological intervention in this area has modified local morphology during the last 40 years. These modifications include an intense deforestation of mangrove regions, construction of the Bracui Boat Yard, the dredging of part of the draining basin and development of the coastal plain. Results from seismic surveys identify three different stratigraphic units separated by two reflectors as well as Holocenic paleodeltas and paleochannels of the Bracui and Gratau rivers. Results from this study and previous work indicate an age of 6800 years for the top of the superior unit. Areal photographs from the years 1964, 1965, 1978 and 1991 reveal the principal modifications occurring during the last 40 years in the area. Field observations from this study as well as bathymetric profiles based on the nautical maps of 1980 and 1944 reveal shoaling and erosion areas in the Saco do Bracui. Sedimentation rates, using lead-210 profiles, are between 0,17 - 1,90 cm/year and lead-210 inventory values are between 16-6-dpm/cm 2 /year. The results for sedimentation rate and inventory show a high accumulation around Bracui, Gratau and Frade mouth rivers and agree with results from the bathymetric profiles with respect to the site of erosion and shoaling in the Saco do Bracui. The results for grain size and lead-210 analyses support the idea that the Saco do Bracui is suffering shoaling processes in specific sites and erosion in others. Comparison between long term sedimentation rates obtained by seismic results and short term rates obtained by lead-210 shows an increase of the sedimentary discharge in the 1960's, when the intense anthropological intervention in the area began. (author)

  6. Reevaluation of environmental monitoring program for radiological emergency at Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro - Brazil

    International Nuclear Information System (INIS)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar

    1996-01-01

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra dos Reis, Rio de Janeiro, the Emergency Response Team of the Institute for Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. The purpose of this program is to define a monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measures in case of a radiological accident, taking into account atmospheric diffusion, population conglomerates and their habits, water and land use, contemplating the entire Emergency Planning Zone of 15 km radius. This program has been reevaluated recently, aiming to optimize it and keep it up to date to assure adequacy of environmental surveillance data in support to a prompt response in case of an emergency situation in the nuclear power plant. It has been organized in the form of a handbook to facilitate handling by field teams. Future revisions will be necessary to incorporate additional pertinent information and keep the handbook up to date, since Angra dos Reis is a summer resort region, subject to constant changes. This paper discusses the structure of the environmental monitoring program and describes the content and preparation of this handbook. (author)

  7. Preface [13. international workshop on hadron physics, Angra dos Reis, RJ (Brazil), 22-27 March 2015

    International Nuclear Information System (INIS)

    2016-01-01

    The Hadron Physics series of workshops, which started in 1988, take place every two or three years. They have the format of an advanced school, consisting of didactic courses, thematic seminars and the presentation of posters on frontier topics in the physics of strong interactions. It is characterized by the active participation of graduate students and postdocs, and also promotes collaboration between reserach groups in Latin America and others distributed worldwide. The XIII International Workshop on Hadron Physics - XIII Hadron Physics - was held from 22-27 March 2015, in Hotel do Bosque, Mambucaba, near the city of Angra dos Reis, Rio de Janeiro state. With good weather, a beach and splendid natural beauty, the surroundings offered all the conditions for a fruitful and pleasant meeting. The scientific program of the XIII Hadron Physics workshop was composed of courses, seminars and contributed papers. The courses consisted of four sets of lectures of three hours each, which are all reproduced in the present volume, thanks to the kind efforts of the lecturers, for the use and appreciation of a wider public. These courses provided a pedagogical and updated account of recent developments that gave support to the discussion of frontier problems in the physics of strong interactions. Organizers and participants are aware that the lecturers bore primary responsibility for the success of the workshop and are especially grateful to them. The seminars reviewed recent developments in theory, computational techniques and experimentations investigating QCD in nonperturbative and high density regimes. Most of these seminars are reproduced in this volume. The Organizing Committee is thankful to the invited speakers for the quality of the presentations, which contributed to the success of the workshop. The contributed papers, mainly representing the scientific activity of young physicists, were exhibited as posters all throughout the event in the breakout area, and are also

  8. Concentration of heavy metals in benthic algae from Ribera Bay, Angra dos Reis, R.J. State, Brazil, suggesting monitor species

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.; Lacerda, L.D. de; Teixeira, V.L.; Faculdade de Biologia e Psicologia Maria Thereza, Niteroi

    1982-01-01

    Concentrations of Cu, Cr, Cd, Zn, Mn, Co, Pb and Ni were determined in benthic algae of Bay of Ribeira, Angra dos Reis, SE Brazilian coast. The results showed that these elements are concentrate under different degrees depending on the algae species considered: Galaxaura marginata and Caulerpa racemosa presented the highest concentrations (ppm) for Cu (5,2), Cd (1,5), Mn (91,5), Co (6,2) and Ni (8,0) and Cr (7,9) and Pb (21,9) respectively. These algae are then suggested as potential monitor species for these metals in tropical coastal waters. The estimated bioaccumulation factors varied from 10 2 for Ni to 10 5 for Pb, falling within the range reported in the literature, with the exception of Cd, which was found to be two orders of magnitude greater. (Author) [pt

  9. Study on the marine fouling communities near Central Nuclear Almirante Alvaro Alberto (CNAAA), Angra dos Reis, R.J. (Brazil)

    International Nuclear Information System (INIS)

    Nunes, A.J.B.

    1983-01-01

    The effects of chemical and thermal effluents from CNAAA (Angra 1 Reactor) on local biota are studied. The seasonal variations and the ecologic aspects are presented and the biota is used as pollution indicator. The biota taxonomic study is desctibed. (M.A.C.) [pt

  10. An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

    International Nuclear Information System (INIS)

    Araujo, Jefferson Borges; Delcourt, Jules H.

    2015-01-01

    The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

  11. An overview of acceptance and knowledge of Angra dos Reis city about the operation of the nuclear power plants considering the associated risks and benefits

    Energy Technology Data Exchange (ETDEWEB)

    Araujo, Jefferson Borges, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel; Ribeiro, Katia Maria Bruno; Medice Junior, Fabio, E-mail: Katiapsi.67@gmail.com [Universidade Estacio de Sa (UNESA), Angra dos Reis, RJ (Brazil); Delcourt, Jules H., E-mail: juleshd@gmail.com [Colegio Naval, Angra dos Reis, RJ (Brazil)

    2015-07-01

    The use of nuclear power plants for electricity supply is presently considered as an important factor to be considered in any energy matrix to ensure the diversification and availability criteria. Currently several countries resumed or started programs for the construction of nuclear power plants of new projects, with extremely improved security levels. Additionally, events and accidents in nuclear power plants have contributed substantially to the occurrence of design modifications and/or update the regulatory requirements to further enhance operational safety of these plants. Nowadays, one of the regulatory requirements necessary for the selection of a site for construction and operation of nuclear installations is the public hearing and discussion. The city of Angra dos Reis has two nuclear power plants in operation and a third one under construction. There are also, plans for the construction of more nuclear power plants in the country, to meet the growing demand for electricity. The first nuclear power plant in Brazil went into operation in 1983 and the second in 2000. The selection of the site for construction of these plants was due to political, economic and strategic factors, present in Brazil, in the decade of 70. The licensing process in de 70's decade did not involve an extensive participation of the society as a whole and of the local population, such as the occurrence of public hearings and the wide possibility for discussion and debate about the acceptance of the location of the plant. In the initial years of operation of the Angra 1 nuclear power plant, the level of knowledge of the local population was practically null, occurring mainly in local clarifications, made through seminars and lectures on special occasions, such as at the time of the annual exercises of the external emergency plan, specific information Programs or technical visits of educational institutions and the Government to Angra dos Reis Nuclear power plant. Since the

  12. Uptake by benthic algae of critical radionuclides to be released in the liquid effluent of the Angra dos Reis Nuclear Power Plant, R.J., Brazil

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.

    1982-06-01

    In vitro interaction of benthic algae from the Angra dos Reis region, R.J., Brazil, was studied with critical radionuclides to be released in the liquid effluent of CNAAA (unit I). 137 Cs- 60 Co - and 125 I uptake and loss by Sargassum filipendula, Padina Vickersiae and Acanthophora Spicifera were observed. Biological half-lives and bioaccumulation factors (B.F.) were estimated. Co and I uptake were fast (apparent equilibrium in 3 to 7 days). Cs uptake was slower (2 to 3 weeks). Loss followed an inverse pattern (fast for Cs, slow for Co and I). B.F. ranged from 10 1 for Cs, to 10 3 for I and 10 3 -10 4 for Co. Higher B.F. for Co and I were found for P. vickersiae (up to 1,4 X 10 4 ) an A. spicifera (up to 7 X 10 3 ) respectively. These species represent important potential media for the transference of Co-I-and-to a much lesser extent - Cs isotopes, through food-webs. They exhibited high capacity to compete with local sandy sediments for the retention of Co and I. High B.F., rapid uptake and moderate to long biological half-lives enable S. filipendula, P. vickersiae and A. specifera to be powerful aids in the monitoring of radioactive contamination by Co and I isotopes. Since the majority of marine organisms tends to exhibit Cs B.F. similars to those reported here, these algae may also be used as monitors for Cs isotopes, the low B.F. being compensated by their abundance, wide distribution and facility of collection. (M.A.) [pt

  13. Radionuclide dispersion and hydrodynamics of Ilha Grande Bay (Angra dos Reis, RJ) simulated from hypothetical accidental releases of liquid wastes

    International Nuclear Information System (INIS)

    Simoes Filho, Fernando Lamego; Lapa, Celso Marcelo Franklin; Aguiar, Andre Silva; Soares, Abner Duarte

    2011-01-01

    This study has the aim to assess the impact of accidental release of radionuclides postulate from a nuclear power reactor through environmental modeling of aquatic resources. In order to do that it was used computational models of hydrodynamic circulation and transport for the simulation of tritium dispersion caused by an accidental release in Ilha Grande Bay from the site of the future third plant in two circulation scenarios. The main difference between the scenarios is based on the enhancement of dilution of the highest concentrations in the last one. This dilution enhancement resulting in decreasing concentrations was observed only during the first two weeks, when they ranged from 1 x 10 9 to 5 x 10 5 Bq/m³ close to the Itaorna beach spreading just to Sandri Island. After 180 days, the plume could not be detected anymore in the bay, because their activities would be lower than the minimum detectable value (< 11 kBq/m³). (author)

  14. Detecção de ácido ocadaico em cultivo de mexilhões Perna perna, Angra dos Reis, RJ Okadaic acid detection in mussel cultivation Perna perna, Angra dos Reis, RJ

    Directory of Open Access Journals (Sweden)

    Geisi Ferreira Mariné

    2010-02-01

    Full Text Available A ficotoxina ácido ocadaico (AO é produzida por um grupo de microalgas conhecidas como dinoflagelados. Os mexilhões, ao se alimentarem dessas microalgas, acumulam a toxina em sua glândula digestiva, desencadeando a Síndrome ou Envenenamento Diarreico por Moluscos (EDM no ser humano. Os sintomas se apresentam em torno de 30 minutos após o consumo do molusco contaminado, variando entre náuseas, dores abdominais, vômitos e diarreia. Quando a ingestão da toxina acontece em quantidades inferiores a 48µg g-1, os sintomas não se desenvolvem, porém seu consumo continuado favorece o surgimento de tumores no trato gastrointestinal em razão do poder carcinogênico do AO. Este estudo pretendeu detectar e quantificar a toxina diarreica AO em mexilhões Perna perna coletados entre os meses de maio e outubro de 2006. A detecção do AO nos mexilhões foi realizada por Cromatografia Líquida de Alta Eficiência com Detecção Fluorimétrica (CLAE-DF. Os resultados cromatográficos indicaram a presença da toxina AO em baixas concentrações, em todas as amostras de mexilhões obtidas de maio a outubro de 2006. Os resultados indicam a necessidade da elaboração e aplicação efetiva de um programa de controle higiênico-sanitário dos moluscos, assim como o monitoramento do ambiente aquático, objetivando, acima de tudo, a segurança da saúde pública.Okadaic acid (OA is a phycotoxin produced by a group of microalgae known as Dino-flagellates. When mussels feed themselves from this micro seaweed the toxin accumulates in their hepatopancreas, triggering the Syndrome or Diarrhetic Shellfish Poisoning (DSP in the human being. The symptoms appear around 30 minutes after the consumption of contaminated mussels and include abdominal nauseas, pains, vomits and diarrhea. When the toxin ingestion happens in amounts lower than 48µg g-1, the above described symptoms do not develop. However, the continued consumption favors the emergence of tumors in the

  15. OS IMPACTOS AMBIENTAIS E O PROCESSO DE GESTÃO INTEGRADA: EXPERIÊNCIAS NA VILA DE ABRAÃO – ILHA GRANDE, ANGRA DOS REIS (RJ / The Environmental Impacts and The Process of Integrated Management: Experiences in The Vila de Abraão – Ilha Grande, Angra dos Reis (RJ

    Directory of Open Access Journals (Sweden)

    Sueli Maurício Leal Filha

    2006-12-01

    Full Text Available The Ilha Grande is situated at the intersection of the parallels 23°05' and 23°14' degrees Southlatitude with the meridians 44°05' and 44°23' West longitude, in Angra dos Reis county, at the Riode Janeiro state Southern coast. It has approximately 193Km² and has two districts, Araçatiba,situated at the western portion whose main villa of residents is Provetá, and Abraão, situated atthe East portion where detaches as the main village the Vila de Abraão. The Vila de Abraão isconsidered the “capital” of the Ilha Grande, where arrive and alter on a daily basis, inhabitants,visitors, public managers, researchers and environmental defenders. The present article considersenvironmental impacts in the Vila de Abraão as important vectors in the construction of managementprocess and territorial planning, mainly after the Island’s change of function - from federal prison(Instituto Penal Cândido Mendes and environmental conservation area it becomes the headoffice of the Centro de Estudos Ambientais e Desenvolvimento Sustentável, a State University ofRio de Janeiro (UERJ unit, which has both an institutional and environmental conservation use,however framed in touristic activity growth context.

  16. Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil; Modelagem Lagrangeana da dispersao atmoferica de radionuclideos e sistemas de informacao geografica como ferramentas de suporte ao planejamento de emergencia na area de influencia do complexo nuclear de Angra dos Reis, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Corbiniano

    2013-07-01

    Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

  17. Análise hidrológica e socioambiental da bacia hidrográfica do córrego Romão dos Reis, Viçosa-MG The hydrographic watershed of Romão dos Reis stream, Viçosa-MG

    Directory of Open Access Journals (Sweden)

    Genice Vieira Santos

    2007-10-01

    Full Text Available O objetivo deste trabalho foi analisar os aspectos hidrológico e socioeconômico da bacia hidrográfica do córrego Romão dos Reis, que se localiza no Município de Viçosa, na região da Zona da Mata do Estado de Minas Gerais. O estudo enfatizou o uso e ocupação da terra como fatores determinantes na análise da qualidade da água, além dos fatores físicos da bacia. Esta foi dividida em sub-bacias, o que possibilitou a escolha de locais representativos para coleta e análise de dados. Coletaram-se os dados referentes a vazão, qualidade da água, elevações, precipitação, uso do solo, tipo de solo e aspectos sociais e econômicos. Para a elaboração dos mapas, utilizou-se o modelo digitalizado, construído a partir de mosaicos e fotos aéreas da região, na escala de 1:30.000. As informações sobre o número de moradores e proprietários, assim como os seus respectivos sistemas de cultivos e ocupação na bacia, foram obtidas por meio de entrevistas semi-estruturadas, visando melhor compreender a organização social e o manejo de uso da terra das propriedades. Foram apontados indicadores de degradação, assim como estratégias de manejo adequadas à melhoria ambiental, que venham contribuir e garantir a sustentabilidade da bacia.This study was carried out to analyze the hydrological and socioeconomic aspects in the hydrographic watershed of Romão dos Reis stream in Viçosa county, Zona da Mata region, Minas Gerais State. In this study, the land use and occupation are emphasized as determinant factors for analyzing water quality, besides physical factors. The watershed was divided into sub-watersheds enabling to choose the representative sites for data collection and analysis. Data on flow rate, water quality, relief, precipitation, landscape (top, hillside and terrace, soil type, social and economic aspects were collected. A digitalized model built from mosaics and aerial photos of the area at 1:30.000 scale was used to draw up

  18. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant

    International Nuclear Information System (INIS)

    Silva, Diogo Neves Gomes da

    2016-01-01

    When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

  19. Anthropogenic impact on the sedimentation in coastal regions: an example in Saco do Bracui - Ribeira Bay, Angra dos Reis, Brazil; O impacto antropogenico sobre a sedimentacao em regioes costeiras: um exemplo no Saco do Bracui - Baia da Ribeira, Angra dos Reis, Brasil

    Energy Technology Data Exchange (ETDEWEB)

    Barbosa, Alayde Alfaia

    2001-07-01

    The Saco do Bracui, located in the littoral zone of the Brazilian southeast, receives run off from the region of Angra dos Reis. Anthropological intervention in this area has modified local morphology during the last 40 years. These modifications include an intense deforestation of mangrove regions, construction of the Bracui Boat Yard, the dredging of part of the draining basin and development of the coastal plain. Results from seismic surveys identify three different stratigraphic units separated by two reflectors as well as Holocenic paleodeltas and paleochannels of the Bracui and Gratau rivers. Results from this study and previous work indicate an age of 6800 years for the top of the superior unit. Areal photographs from the years 1964, 1965, 1978 and 1991 reveal the principal modifications occurring during the last 40 years in the area. Field observations from this study as well as bathymetric profiles based on the nautical maps of 1980 and 1944 reveal shoaling and erosion areas in the Saco do Bracui. Sedimentation rates, using lead-210 profiles, are between 0,17 - 1,90 cm/year and lead-210 inventory values are between 16-6-dpm/cm{sup 2}/year. The results for sedimentation rate and inventory show a high accumulation around Bracui, Gratau and Frade mouth rivers and agree with results from the bathymetric profiles with respect to the site of erosion and shoaling in the Saco do Bracui. The results for grain size and lead-210 analyses support the idea that the Saco do Bracui is suffering shoaling processes in specific sites and erosion in others. Comparison between long term sedimentation rates obtained by seismic results and short term rates obtained by lead-210 shows an increase of the sedimentary discharge in the 1960's, when the intense anthropological intervention in the area began. (author)

  20. Distribution of cysts of Strongyluris sp. (Nematoda) in the pallial system of Achatina fulica Bowdich, 1822 from Vila Dois Rios and Vila do Abraão, Ilha Grande, Angra dos Reis, Rio de Janeiro.

    Science.gov (United States)

    Oliveira, J L; Santos, S B

    2018-04-19

    This work aimed to assessing Strongyluris sp. cysts distribution pattern in the several inner organs from pallial system of Achatina fulica Bowdich, 1822. Also we verified if there is a relationship between the mollusk size and the number of specimens from parasites collected from two touristic villages in Ilha Grande (Angra dos Reis, Rio de Janeiro state): Vila Dois Rios (VDR) and Vila do Abraão (ABR). The samples were obtained through a field work conducted bimonthly during 2007, 2008, 2010, and 2011, at both locations. Height and width were measured from shells collected, and the all specimens were classified in different classes: class 1 - biomass and a larger area of the pallial system, allowing an efficient parasite colonization. Other possible explanation could be the long exposure of the molluscs of class 3 to the parasites, which allowed a longer time to the larvae to allocate themselves.

  1. Temperature distribution in the Piraquara de Fora Bay resulting from residual heat liberation of the Angra-1 Nuclear Power Plant in Angra dos Reis, RJ, Brazil and its possible ecological effects

    International Nuclear Information System (INIS)

    Mota Singer, E. da.

    1979-01-01

    A preliminary evaluation was done of the potential environmental consequences derived from the emission from the condenser cooling of the nuclear power plants at the Angra dos Reis site. The calculation of the temperature field starting from the point of emission of the coolant discharge was done using the model of Stolzenbach for three dimensional heated surface discharge. Considerations were made of the potential environmental damage to the marine life based on the calculated temperature increase. Special atention was given to the potential damage to the necton's life, by estimating the probability of occurance of higher than lethal temperature for the known species living at the site. These species were given in the Safety Analysis Report of the Unity I of the nuclear station. (Author) [pt

  2. Palinologia de espécies de Asteraceae de utilidade medicinal para a comunidade da Vila Dois Rios, Ilha Grande, Angra dos Reis, RJ, Brasil Pollen morpology of species of Asteraceae with medicinal utility for the community from Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro State, Brazil

    Directory of Open Access Journals (Sweden)

    Marcelo Neto Galvão

    2009-03-01

    Full Text Available O trabalho trata da morfologia polínica e de descrições taxonômicas de 12 espécies de Asteraceae correspondentes em 12 diferentes gêneros, distribuídos em nove tribos. Todas as espécies estudadas são utilizadas como medicamentos pelos moradores da Vila Dois Rios, Ilha Grande, Angra dos Reis, Rio de Janeiro. Neste estudo objetivou-se caracterizar os tipos polínicos das espécies usadas por esta comunidade e fornecer chaves diagnósticas de caracteres macromorfológicos e micromorfológicos que auxiliem a identificação das mesmas. A identificação taxonômica e palinológica correta é pré-requisito para estudos que validem a eficácia e segurança terapêutica dessas espécies. Deve-se considerar, ainda, que a utilização desses conhecimentos é importante para a comunidade, como por exemplo, na melissopalinologia. Os grãos de pólen foram acetolisados, medidos, descritos e ilustrados sob microscopia de luz. Para observar detalhes da superfície e abertura, grãos de pólen não acetolisados foram analisados em microscópio eletrônico de varredura. Foram estudadas as características dos grãos de pólen como forma, tamanho, constituição da sexina e abertura. Os resultados mostraram que a morfologia polínica é bem definida entre as espécies estudadas, podendo ser usada para sua identificação e sustenta o caráter euripalinológico de Asteraceae.This study is a palynologycal characterization and taxonomic description of 12 species within 12 genera, distributed in nine tribes from Asteracaeae. All studied species are used as medicines by people from Vila Dois Rios and they occur in Ilha Grande. This work aimed to characterize the pollen grains of medicinal species of Asteraceae from Vila Dois Rios and provide diagnostic keys based on macromorphological and pollen characters to help their identification, since the correct taxonomic and palynological recognition of these species is necessary for further studies on therapeutic

  3. Environmental monitoring program for radiological emergencies at the Almirante Alvaro Alberto Nuclear Power Plant, Angra dos Reis, Rio de Janeiro, Brazil

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Lilia M.J. Belem; Ramos Junior, Anthenor C.; Gomes, Carlos A.; Carvalho, Zenildo L.; Gouveia, Vandir; Estrada, Julio; Ney, Cezar [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)

    1997-12-31

    In order to respond to a major radiological emergency at the Almirante Alvaro Alberto Nuclear Power Plant, located in Angra do Reis, Rio de Janeiro, the Emergency Response Team of the Institute of Radiation Protection and Dosimetry (IRD/CNEN) established a program of environmental monitoring. A monitoring trend to assess the off-site radiological conditions and give support to decision making for implementing protective measure in case of a radiological accident is presented. For the selection of the monitoring points, the program takes into account atmospheric diffusion, population conglomerates and their habits, water and land use; it includes the entire Emergency Planning Zone of 15 km radius. The program has been organized in the form of a handbook to facilitate handling by field teams 2 refs., 1 fig.; e-mail: lilia at ird.gov.br

  4. Elites em perspectiva: uma discussão sobre hierarquias, composição da riqueza e consolidação dos grupos hegemônicos em São João del Rei = Elites in perspective: a discussion about hierarchies, composition of wealth and consolidation of hegemonic groups in São João del Rei

    Directory of Open Access Journals (Sweden)

    Melo, Keila Cecília de

    2014-01-01

    Full Text Available O artigo analisa aspectos econômicos da elite colonial mineira a partir de meados do século XVIII, mediante a investigação empírica da sociedade de São João Del Rei. O comércio em São João assumiu um papel central na liquidez da economia regional, permitindo a formação de grupos hegemônicos no século XIX. Mas há ainda muitas dúvidas sobre quem era essa elite no século XVIII. Com base em pesquisa prosopográfica que reconstrói os caminhos dos homens arrolados por Domingos Nunes Vieira como os mais ricos da capitania de Minas Gerais no ano de 1756, percebemos que a elite mineira que se formou no século XVIII diferia dos padrões mais gerais para a caracterização de grupos hegemônicos em outras regiões do Brasil, no mesmo período

  5. Establishment of criteria for classification of area remediation measures contaminated after an eventual radiation accident in Angra dos Reis, RJ, nuclear power plant; Estabelecimento de criterios para a classificacao de medidas de remediacao de areas contaminadas apos um eventual acidente nuclear na usina de Angra dos Reis (RJ)

    Energy Technology Data Exchange (ETDEWEB)

    Silva, Diogo Neves Gomes da

    2016-07-01

    When a radiological or nuclear accident that leads to the release of radioactive material to the environment occurs, it is important to implement protective and remediation measures in order to reduce human exposure to radionuclides. Therefore, it is necessary that the procedures to be chosen by the affected country authorities are the most efficient ones, which can only be defined based on previously established criteria. In Brazil, since the radiological accident in Goiania, in 1987, the development of tools to support decision-making in emergencies of this nature was started. The main objective of this work was to establish an acting basis for contaminated areas, in order to protect the individuals of public in case of any accident related to Almirante Alvaro Alberto nuclear power plant, in the municipality of Angra dos Reis (RJ), which leads to contamination to the environment and the consequent exposure of local population or from more distant regions to ionizing radiation. Initially, the high-risk areas near the location of the nuclear power plant were defined. Typical urban environments found in the main cities of these municipalities were surveyed, including homes, streets and recreation areas. The main characteristics of the study area were evaluated using images from Google Earth® and web pages of the municipalities. After the types of areas to be simulated were selected, these were quantified in terms of the number of residents, the size of the streets, and the number of trees, among others, per unit area. Considering the different housing characteristics for the selected municipalities, six main standard scenarios were developed for urban areas, including homes with different shielding, buildings and parks. The simulation of the procedures for each scenario was made with SIEM model, developed by the Institute of Radiation Protection and Dosimetry (IRD/CNEN), formed by the integration of various models including CORAL, focusing on agricultural areas

  6. Lagrangian modeling of atmospheric dispersion of radionuclides and geographical information systems as tools to support emergency planning in area of influence of nuclear complex of Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    Silva, Corbiniano

    2013-01-01

    Industrial accidents generally endanger structures and the set of environmental influence area where the enterprises are located, especially when affected by atmospheric dispersion of their pollutants, whose concern with the evacuation of the population is the main goal in emergency situations. Considering the nuclear complex Angra dos Reis - RJ, based on computer modeling analysis of the mechanisms of pollutant dispersion in conjunction with geographic information systems were developed. Thus, information about the dispersion of radionuclides - from simulations performed on the HYSPLIT; meteorological data (direction, intensity and calm on the wind regime and analysis of the wind field in the region using WRF), occurrence of landslides and data on the environmental study area were integrated into a GIS database using ArcGIS platform. Aiming at the identification and definition of escape routes in case of evacuation from accidental events in CNAAA, the results point solutions for long-term planning, based on weather and landslides, and short-term, supported by simulations of the dispersion radionuclides, in order to support actions that assist local emergency planning. (author)

  7. DOS.

    Science.gov (United States)

    Traven, Bill

    1988-01-01

    Discusses using the DOS PATH command (for MS-DOS) to enable the microcomputer user to move from directory to directory on a hard drive. Lists the commands to be programed, gives examples, and explains the use of each. (MVL)

  8. Os primeiros reis-de-armas do Brasil

    Directory of Open Access Journals (Sweden)

    Rui Vieira da Cunha

    1963-12-01

    Full Text Available A filiação direta dos arautos aos fetiales romanos (1 é negada pela pesquisa moderna, embora longe de dissipar as som-bras envolventes de suas origens (2 . Referidos nos poemas de Chrétien de Troyes, circa 1170, aparecem vinculados aos tor-neios e, pelos meados do século XIV, erravam à busca de onde prestar seus serviços, salvo uns poucos felizardos que estavam incluídos na casa de grandes senhores . Nesse último grupo, alguns, com autoridade sôbre os companheiros, eram denomi-nados reis, apelativo escolhido para significar, à época, análo-ga preeminência entre os menestréis, os devassos, os mendigos.

  9. Development of REI meetings (concluding remarks)

    International Nuclear Information System (INIS)

    Roessler, K.

    1988-01-01

    It is an honour and a pleasure to deliver the concluding remarks of this Fourth International Conference on Radiation Effects in Insulators. After commenting upon the present meeting, the genesis of REI conferences, their aims and position relative to related meetings in radiation and ion implantation research will be treated, particularly in order to inform new-comers. The development of the last four REI meetings will be discussed on the base of a statistical analysis. Some recommendations and an outlook of future trends will be given. (orig.)

  10. The long history of REI Conference: The first 30 years

    International Nuclear Information System (INIS)

    Mazzoldi, P.

    2010-01-01

    An analysis of the REI Conference evolution from the first, in 1981, to the last, 2009, REI-15, is reported, considering the contributions in the different topics, as fundamental processes, materials, nanosystem and application and revisiting some invited talks and presentations. Historical information concerning some Universities, which organized REI-Conferences, are introduced in the exposition.

  11. Phytoplankton community of Reis lake in the Brazilian Amazon

    Directory of Open Access Journals (Sweden)

    ISE G. SILVA

    2013-06-01

    Full Text Available Reis Lake is located in the municipality of Caracaraí, state of Roraima (Brazil and is subject to fluctuations in water level. The aim of this study was to analyze the structure of the phytoplankton community on the nictemeral and seasonal scales and determined the influence of limnological variables. Sampling was performed in the rainy season (June/2006 and dry season (November/2006, considering two nictemeral cycles. The phytoplankton community was assessed with regard to composition and density, abiotic variables were analyzed simultaneously. The lake had low concentrations of oxygen, clinograde profile and water stratified during the day and homogenous at night, with low concentrations of nutrients and waters ranging from slightly acidic to alkaline. The phytoplankton was represented by 43 taxa, 35 species in the dry season and 29 species in the rainy season. Low densities of phytoplankton occurred in both nictemeral cycles, with accentuated vertical gradient. The highest densities were recorded in the dry season. Reis Lake exhibits characteristics that classify it as a polymythic and oligotrophic environment. The variability in the data was more important seasonally than on the nictemeral scale, supporting the hypothesis of the influence of the hydrological cycle on the dynamics of phytoplankton communities in floodplain lakes.O lago dos Reis está localizado no município de Caracaraí, no estado de Roraima (Brasil e está sujeito a flutuações no nível da água. O objetivo do estudo foi analisar a estrutura da comunidade fitoplanctônica nas escalas nictemeral e sazonal e determinar a influência de variáveis limnológicas nesta comunidade. As amostragens foram realizadas nos periodos chuvoso e seco, considerando dois ciclos nictemeral. A comunidade fitoplanctônica foi avaliada no que diz respeito à composição e densidade, simultaneamente, variáveis abióticas foram analisadas. O lago apresentou baixas concentrações de oxig

  12. The efficiency of two anaerobic reactor components; Eficiencias de dos componentes de un reactor anaerobio

    Energy Technology Data Exchange (ETDEWEB)

    Vazquez Borges, E.; Mendez Novelo, R.; Magana Pietra, A. [Facultad de Ingenieria. Universidad de Yucatan (Mexico); Martinez Pereda, P.; Fernandez Villagomez, G. [Universidad Nacional Autonoma de Mexico. Division de Estudios de posgrado de la Facultad de Ingenieria. Mexico (Mexico)

    1997-09-01

    This study examined the behaviour of an anaerobic digester in treating pig farm sewage. The experimental model consisted of a UASB reactor at the bottom and a high-rate sedimentator at the top with a total capacity of 534 litres. The digester was installed on a pig farm and its performance under different operating conditions was determined, with hydraulic retention time (HRT) as the critical parameter for evaluating the anaerobic system`s efficiency. The results obtained during the experiment to establish the critical operating parameters are reported. The organic loads applied for a HRT of 1 day were 7.3 kg/m``3/day of total DQO and 3 kg/m``3/day of soluble DQO, following organic matter removal rates (as total DQO) of 36% and 49% respectively and removal rates (as soluble DQO) of 74% in the UASB and 8% in the sedimentator. The efficiency of the reactor as a whole at this HRT time was a removal rate of 74% of total DQO and 75% of soluble DQO. (Author) 25 refs.

  13. Maracatus Solar e Reis de Paus: tradição e modernidade no carnaval de rua em Fortaleza

    OpenAIRE

    Silva, Roberto Antônio de Sousa da

    2013-01-01

    Trata-se de um estudo etnográfico e comparativo dos Maracatus Solar (2006) e Reis de Paus (1960), cujo objetivo foi verificar o que existe de antigo e tradicional no novo maracatu praticado pela agremiação Solar e, em contrapartida, o que existe de novo ou moderno no velho maracatu ritualizado pela agremiação Reis de Paus. Cabe ressaltar que por meio deste estudo de caso pretendeu-se também observar etnograficamente e compreender melhor os processos de rupturas e continuidades ...

  14. Sacrifício rei, estado ruandês e genocídio

    Directory of Open Access Journals (Sweden)

    Christopher C. Taylor

    Full Text Available Em contraste com as análises do genocídio ruandês de 1994, que privilegiam o político, este artigo sustenta que o poder e a política durante o tempo que precedeu o genocídio foram afetadas por noções ruandesas específicas de cosmologia e ontologia. Para entender esse componente "imaginário" da violência, precisamos examinar atentamente as crenças e práticas relacionadas com a instituição da realeza sagrada em Ruanda. Embora essas crenças e práticas foram oficialmente encerradas em 1931, quando o último rei de Ruanda sagrado foi deposto e substituído por seu filho educado por missionários, a sua matriz cosmológica manteve-se em tempos recentes. Isto pode ser visto na literatura popular de rua Ruandesa, que circulou amplamente nos dias que antecederam o genocídio. Nessa literatura, o então presidente Juvenal Habyarimana era comparado explicitamente a um rei ruandês. Mais importante ainda para os objetivos deste artigo, foi a comparação mais difusa, implícita, e simbólica entre Habyarimana e um rei sagrado. Em particular, alguns dos elementos-chave neste simbolismo iluminam (e mostram a importância da persistência da imagem de como um rei (ou presidente deveria se comportar. Como havia muitos jornalistas ruandeses reacionários (e racistas que tinham começado a duvidar da capacidade do presidente Habyarimana de ser um "bom rei", seu "sacrifício"'subseqüente estava, em um sentido simbólico, fortemente predestinado.

  15. LÁ VEM A BANDEIRA... OS REIS E SEUS ATORES

    Directory of Open Access Journals (Sweden)

    Mauro Passos

    2011-01-01

    Full Text Available A religiosidade popular manifesta-se por meio de rituais, festas, comemorações e celebrações. Alicerçadas em elementos místicos, as tradições populares integram o natural, o social e o sagrado. Este artigo faz um estudo das “Folias de Reis”, particularmente em duas cidades do interior de Minas Gerais. Foram utilizados os procedimentos metodológicos da história oral, através de um conjunto de depoimentos. A religiosidade faz parte da cultura das classes populares. Seu estudo é um importante instrumento para a compreensão das raízes culturais e históricas do povo brasileiro. Na verdade, trata-se do mundo de Deus e mundo dos homens, ancorados no rio da vida. As Folias de Reis estão permeadas por múltiplos atores, lastreadas de continuidades / descontinuidades. Em vista disso, é necessário analisar seu significado e sua dinâmica.

  16. Sustainable Materials Management (SMM) - Recycling Economic Information (REI) Report

    Data.gov (United States)

    U.S. Environmental Protection Agency — The 2016 Recycling Economic Information (REI) Report aims to increase the understanding of the economic implications of material reuse and recycling. The report...

  17. Iconografia da honra e do prestígio: Reis de Armas e cavaleiros das Ordens Militares em Portugal e Castela (séculos XVII-XVIII)

    OpenAIRE

    Guillén Berrendero, José Antonio

    2016-01-01

    O tema deste artigo é demonstrar o poder das representações visuais dos indivíduos honrados nas coroas de Castela e de Portugal. Mostra uma visão transversal da representação da honra e do prestígio mediante a identificação das distintas marcas de nobreza que são atribuídas aos cavaleiros das Ordens Militares e pelos Reis de Armas. No caso dos primeiros, o autor analisa os elementos próprios de indivíduos identificados pela sua condição de nobres. No caso dos Reis de Armas, centra-se no valor...

  18. Preliminary evaluation of SACI-O code for the analysis of transients in a pressurized water reactor core

    International Nuclear Information System (INIS)

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

    1979-03-01

    SACI-O is a computer code which deals with the dynamics of the core of pressurized light water reactors (PWR). Its applicability is determined by the evaluation of the models used in the simulation of the several phenomena and processes which occur in the core during transients. This report presents a comparison between the results obtained with SACI-O and those presented in the Final Safety Analysis Report (FSAR) of Angra dos Reis Nuclear Station, Unit 1. Although some data used in the calculations done by Westinghouse are not known, there was a good agreement between the mentioned results. (Author) [pt

  19. António Reis and Margarida Cordeiro, eccentric filmmakers

    Directory of Open Access Journals (Sweden)

    Lucas Tavares Neves

    2016-02-01

    Full Text Available The international symposium "António Reis and Margarida Cordeiro, eccentric filmmakers" took place in Paris between the 3rd and the 4th of June, 2015. Speakers exchanged on the political, social and poetical aspects of the duo's cinematography, as well as on the reverberations of titles such as Jaime (1974 and Trás-os-montes (1976 on the Portuguese filmic landscape of the decades that followed.

  20. Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel

    NARCIS (Netherlands)

    Norton, M.I.; Frost, J.H.; Ariely, D.

    2011-01-01

    Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking-in seeming contrast to the results of our earlier article (Norton, Frost, & Ariely, 2007). We believe that Reis et al. (a) utilized paradigms far removed

  1. Efecto de dos metales pesados, cadmio y níquel, sobre la eficiencia de remoción de carga orgánica de un reactor UASB a escala de laboratorio

    Directory of Open Access Journals (Sweden)

    Luis Eduardo Forero

    2004-01-01

    Full Text Available Se realizaron ensayos en tres reactores UASB de tres litros cada uno, a un tiempo de retención hidráulico (TRH de cuatro horas y carga orgánica volumétrica de 4,8 g/L/d. Después de la fase inicial de arranque, tiempo de 4.000 horas para los tres reactores, se procedió a afectarlos de la siguiente forma: el primer reactor fue alimentado con 5 mg/L de cloruro de cadmio en forma continua, el segundo reactor fue alimentado con 10 mg/L de cloruro de níquel en forma continua también, mientras que el tercer reactor no se afectó con sustancia alguna y sirvió como control. La eficiencia de remoción de demanda química de oxígeno (DQO del primer reactor cambió del 60% de la fase de arranque (fase 1 al 18% en la fase afectada con cadmio (fase dos; la eficiencia de remoción de DQO en el reactor dos pasó del 60 al 24% y a su vez para el reactor tres control no hubo cambio significativo en dicha eficiencia. A su vez el reactor uno acumuló el cadmio en el lodo, mientras que el reactor dos no hizo lo propio con el níquel.

  2. Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel

    OpenAIRE

    Norton, M.I.; Frost, J.H.; Ariely, D.

    2011-01-01

    Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking-in seeming contrast to the results of our earlier article (Norton, Frost, & Ariely, 2007). We believe that Reis et al. (a) utilized paradigms far removed from spontaneous, everyday social interactions that were particularly likely to demonstrate a positive link between familiarity and liking and (b) failed to include and incorporate other sources o...

  3. The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

    Energy Technology Data Exchange (ETDEWEB)

    Goes, Alexandre Gromann de; Araujo, Jefferson Borges, E-mail: gromann@cnen.gov.br, E-mail: jeferson@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN/CGRC), Rio de Janeiro, RJ (Brazil). Coordenacao Geral de Reatores e do Ciclo Combustivel

    2015-07-01

    The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

  4. Cobalt adsorption/desorption on sediments from Piraquara de Fora bay, Angra dos Reis, Brazil

    International Nuclear Information System (INIS)

    Ferreira, Ingryd M.; Carvalho, Franciane M.; Ribeiro, Fernando C.A.; Martins, Nadia S.F.; Peres, Sueli S.; Lauria, Dejanira C.

    2015-01-01

    Among the radionuclides released with the liquid effluents from PWR power plants, cobalt isotopes ( 60 Co and 58 Co) play an important role for risk and environmental impact assessments. The laboratory experiments on radionuclide adsorption-desorption, followed by the use of adsorption isotherms are useful tools for prediction of transport, distribution, accumulation, and fate of a contaminant into a specific medium. Adsorption and desorption experiments were carried out in batches, using two sediment samples collected in Piraquara de Fora Bay, near the discharge channel of the liquid effluents from CNAAA. Aiming the assessment of the radioisotope adsorption mechanisms, sediment samples were shaken with solutions containing cobalt chloride which concentrations ranged between 10 -10 and 10 -3 M. In order to estimate the efficiency of adsorption, 100 Bq of 60 Co were used as radioactive tracer. The experimental data fitted well with Freundlich and Langmuir isotherms. Results point out a favorable and high cobalt adsorption on the sediments, although smaller than the ones reported in literature studies. Such smaller trend of adsorption coefficients may be caused by the low exchange capacity of the prevailing clay, kaolinite. The maximum adsorption capacities were found to be 10 and 17 moles/g for sediments in PT-01 and PT-02, respectively. Values lower than 8% of the adsorbed cobalt underwent desorption and this amount decreased to 4%, with time, which show the high retention capacity of these sediments. (author)

  5. Study of sea surface temperature distribution, in Angra dos Reis Nuclear Plant region - Mission Angra 01

    International Nuclear Information System (INIS)

    Stevenson, M.R.; Steffen, C.A.; Villagra, H.M.I.

    1982-03-01

    A study of spectral and temporal variations of sea surface temperature, using data obtained from level of satellite, aircraft and surface, with the purpose of evaluate and plot the small scale variations of sea surface temperature, due to thermal discharge from a nuclear the results of the first mission called Angra 1. (maps). (C.G.C.)

  6. Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region

    International Nuclear Information System (INIS)

    Biagio, Rosa Maria de Souza

    1982-01-01

    A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

  7. Experiments on radionuclide accumulation by fishes from the Angra Dos Reis region of Brazil

    International Nuclear Information System (INIS)

    Guimaraes, J.R.D.

    1988-11-01

    To follow the bioaccumulation and tissue distribution of 137 Cs and 60 Co in fish from tropical waters near the Angra nuclear power station in Brazil, juvenile grouper (Epinephelus sp.) were exposed under laboratory conditions to Angra sea water containing the two radionuclides initially added in chloride form. During the 4-month exposure period, the sea water was not changed and the fish received regular rations of non-radioactive food. Following uptake, the fish were dissected and composite tissue samples monitored for radioactivity. 137 Cs concentration factors (CFs) were 3 and 5 in whole fish and muscle, respectively. The highest concentration of 137 Cs was found in the muscle which accounted for 66% of the total body burden. In contrast, the highest concentration and greatest fraction (19%) of 60 Co was located in the liver. Whole body and muscle CFs for 60 Co, 0.2 and 0.08 respectively, were much lower than those for 137 Cs. Compared with published data, only very small amounts of both radionuclides were taken up by bone in the present study. This observation and the fact that much higher 137 Cs CFs have been reported in fish from field studies suggests that uptake through the food chain is the principal pathway for bioaccumulation in nature. Elution of freshly-prepared and previously-used radioactive sea water through chelating resins indicated that 60 Co added in the cationic form was almost totally converted to neutral or anionic forms after four months. Additional experiments carried out with the previously-used experimental media demonstrated that the possibly ligand-bound 60 Co was approximately 2.5 times more available for uptake by grouper than the cationic forms initially present. It is concluded that the uptake of 60 Co by fish exposed to radioactive effluents would be a function of the different forms of 60 Co present. 20 refs, 2 figs, 2 tabs

  8. The evolution and improvements of the external emergency plans of Angra dos Reis nuclear power plant

    International Nuclear Information System (INIS)

    Goes, Alexandre Gromann de; Araujo, Jefferson Borges

    2015-01-01

    The scenery that now has been configuring in the area of science and nuclear technology in the society, with their obstacles and their evolution tendencies, their philosophical discussions around fundamental concepts, and the necessity to evolve the capacity in emergency response is described in this paper. Some obstacles related to the acceptance of the nuclear energy are mentioned and some proposed strategies are also presented, as well as, specific politics for the analyzed case. One can conclude that it is imperative, that the opinion and public perception of the risk, associated with radioactive facilities should be considered and that the debate continues involving legislators, operators and the public in general. (author)

  9. 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.)

  10. Echoes of Portuguese Navigation in the Kitab-i Bahriye by Piri Reis

    Directory of Open Access Journals (Sweden)

    Rui Manuel Loureiro

    2013-10-01

    Full Text Available The world map drawn by Piri Reis in 1513, of which only the Atlantic fragment kept in Istanbul is known, is justly famous. Its surprising modernity is fully explained by the use of Iberian sources, resulting from nearly a century of exploration of both sides of the Atlantic by Portuguese and Spanish navigators, along with other collaborators. The ‘Book of maritime affairs’, prepared in the 1520s by the Turkish cartographer, gathering precious geographic and cartographic information about the Mediterranean and many other regions, is equally important, although rather less well known. In the foreword to his Kitab-i Bahriye, Piri Reis appears to be especially well informed about Portuguese explorations along the African coast and in the Asian seas, after the voyages of Bartolomeu Dias and of Vasco da Gama. Is it possible to identify the textual and cartographic sources used by Piri Reis in the preparation of both his cartographic works?

  11. 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.)

  12. Distrofia de Reis-Bücklers: Presentación de una familia

    Directory of Open Access Journals (Sweden)

    Daisy Flores Pérez

    2003-09-01

    Full Text Available Se presentan los resultados de un estudio realizado en 12 pacientes integrantes de una familia de la raza blanca. Se diagnosticaron 5 con distrofia de Reis-Bücklers. El defecto refractivo que predominó fue el astigmatismo. Se obtuvo un patrón de herencia autosómico dominante en la familia en estudio.The results of the study performed in 12 patients from a Caucasian family are presented. Five were diagnosed with Reis-BücKler dystrophy. The predominant refractory defect was astigmatism. A dominant autosomal hereditary pattern was obtained in the studied family.

  13. Väljapaistev riigimees August Rei puhkab kodumaa mullas / Urve Sagur

    Index Scriptorium Estoniae

    Sagur, Urve

    2006-01-01

    Asutava Kogu ja Riigikogu esimehe, riigivanema, ministri ja diplomaadi August Rei ja tema abikaasa urnid maeti Metsakalmistule Kuulsuste künkale. Mälestusteenistusel kõnelesid president Arnold Rüütel ja Riigikogu esimees Toomas Varek. Lisa: Ametid

  14. Fusion of classifiers for REIS-based detection of suspicious breast lesions

    Science.gov (United States)

    Lederman, Dror; Wang, Xingwei; Zheng, Bin; Sumkin, Jules H.; Tublin, Mitchell; Gur, David

    2011-03-01

    After developing a multi-probe resonance-frequency electrical impedance spectroscopy (REIS) system aimed at detecting women with breast abnormalities that may indicate a developing breast cancer, we have been conducting a prospective clinical study to explore the feasibility of applying this REIS system to classify younger women (breast cancer. The system comprises one central probe placed in contact with the nipple, and six additional probes uniformly distributed along an outside circle to be placed in contact with six points on the outer breast skin surface. In this preliminary study, we selected an initial set of 174 examinations on participants that have completed REIS examinations and have clinical status verification. Among these, 66 examinations were recommended for biopsy due to findings of a highly suspicious breast lesion ("positives"), and 108 were determined as negative during imaging based procedures ("negatives"). A set of REIS-based features, extracted using a mirror-matched approach, was computed and fed into five machine learning classifiers. A genetic algorithm was used to select an optimal subset of features for each of the five classifiers. Three fusion rules, namely sum rule, weighted sum rule and weighted median rule, were used to combine the results of the classifiers. Performance evaluation was performed using a leave-one-case-out cross-validation method. The results indicated that REIS may provide a new technology to identify younger women with higher than average risk of having or developing breast cancer. Furthermore, it was shown that fusion rule, such as a weighted median fusion rule and a weighted sum fusion rule may improve performance as compared with the highest performing single classifier.

  15. Reactors

    DEFF Research Database (Denmark)

    Shah, Vivek; Vaz Salles, Marcos António

    2018-01-01

    The requirements for OLTP database systems are becoming ever more demanding. Domains such as finance and computer games increasingly mandate that developers be able to encode complex application logic and control transaction latencies in in-memory databases. At the same time, infrastructure...... engineers in these domains need to experiment with and deploy OLTP database architectures that ensure application scalability and maximize resource utilization in modern machines. In this paper, we propose a relational actor programming model for in-memory databases as a novel, holistic approach towards......-level function calls. In contrast to classic transactional models, however, reactors allow developers to take advantage of intra-transaction parallelism and state encapsulation in their applications to reduce latency and improve locality. Moreover, reactors enable a new degree of flexibility in database...

  16. Does familiarity breed contempt or liking? Comment on Reis, Maniaci, Caprariello, Eastwick, and Finkel (2011).

    Science.gov (United States)

    Norton, Michael I; Frost, Jeana H; Ariely, Dan

    2011-09-01

    Reis, Maniaci, Caprariello, Eastwick, and Finkel (see record 2011-04644-001) conducted 2 studies that demonstrate that in certain cases, familiarity can lead to liking--in seeming contrast to the results of our earlier article (see record 2006-23056-008). We believe that Reis et al. (a) utilized paradigms far removed from spontaneous, everyday social interactions that were particularly likely to demonstrate a positive link between familiarity and liking and (b) failed to include and incorporate other sources of data-both academic and real-world-showing that familiarity breeds contempt. We call for further research exploring when and why familiarity is likely to lead to contempt or liking, and we suggest several factors that are likely to inform this debate. PsycINFO Database Record (c) 2011 APA, all rights reserved.

  17. A prática oceanográfica e a coleção iconográfica do rei dom Carlos I

    Directory of Open Access Journals (Sweden)

    Maria Estela Jardim

    2014-09-01

    Full Text Available Após a expedição do Challenger (1872-1878, outras nações começaram a interessar-se pela pesquisa oceanográfica e a organizar suas próprias expedições. Desde 1885 que o príncipe Albert I de Mónaco realizava campanhas oceanográficas, com a colaboração de alguns dos melhores cientistas em biologia marinha e em oceanografia física, inventando técnicas e instrumentos para a realização dos trabalhos oceanográficos. A atividade científica do príncipe Albert certamente contribuiu para estimular o interesse do seu amigo, o rei dom Carlos I de Portugal, pelo estudo dos oceanos e da vida marinha. Ambos compartilhavam a necessidade de usar a fotografia para documentar suas pesquisas. Este artigo analisa o papel da fotografia científica na ciência oceanográfica, particularmente nas expedições realizadas pelo monarca português.

  18. Analytik von Minorlipiden: Ferulasäureester von Phytosterolen (gamma-Oryzanol) in Reis

    OpenAIRE

    Miller, Andreas

    2005-01-01

    Ferulasäureestern von Phytosterolen (γ-Oryzanol) werden antioxidative und cholesterinsenkende Eigenschaften zugeschrieben. Bisher beschriebene Methoden zur Analytik von γ-Oryzanol in Reis erforderten eine aufwendige Aufreinigung des Probenextrakts. In dieser Arbeit wurde basierend auf der on-line LC-GC eine Methode entwickelt, die die simultane Bestimmung von γ-Oryzanol-Gehalt und Sterylferulat-Verteilung ohne Aufreinigung des Probenextrakts erlaubt. Mit Hilfe der Technik wurden die natürlich...

  19. Proposta de bioremediació de l'estany Olla del Rei de Castelldefels

    OpenAIRE

    Vidiella Martin, Maria

    2017-01-01

    The UPC campus and the Mediterranean Technology Park (PMT) is an educational and research site that includes a naturalized area that sets it apart: the lake called "Olla del Rei", included in the inventory of wetlands in Catalonia. The evolution of the system and the effects caused by the network of drainage channels connected to the lagoon, have generated huge problems that threaten the existence of the lake as a natural area: eutrophication and loss of quality of the water, the exponential ...

  20. Insertion of the Biogenesis Factor Rei1 Probes the Ribosomal Tunnel during 60S Maturation.

    Science.gov (United States)

    Greber, Basil Johannes; Gerhardy, Stefan; Leitner, Alexander; Leibundgut, Marc; Salem, Michèle; Boehringer, Daniel; Leulliot, Nicolas; Aebersold, Ruedi; Panse, Vikram Govind; Ban, Nenad

    2016-01-14

    Eukaryotic ribosome biogenesis depends on several hundred assembly factors to produce functional 40S and 60S ribosomal subunits. The final phase of 60S subunit biogenesis is cytoplasmic maturation, which includes the proofreading of functional centers of the 60S subunit and the release of several ribosome biogenesis factors. We report the cryo-electron microscopy (cryo-EM) structure of the yeast 60S subunit in complex with the biogenesis factors Rei1, Arx1, and Alb1 at 3.4 Å resolution. In addition to the network of interactions formed by Alb1, the structure reveals a mechanism for ensuring the integrity of the ribosomal polypeptide exit tunnel. Arx1 probes the entire set of inner-ring proteins surrounding the tunnel exit, and the C terminus of Rei1 is deeply inserted into the ribosomal tunnel, where it forms specific contacts along almost its entire length. We provide genetic and biochemical evidence that failure to insert the C terminus of Rei1 precludes subsequent steps of 60S maturation. Copyright © 2016 Elsevier Inc. All rights reserved.

  1. Reactor

    International Nuclear Information System (INIS)

    Fujibayashi, Toru.

    1976-01-01

    Object: To provide a boiling water reactor which can enhance a quake resisting strength and flatten power distribution. Structure: At least more than four fuel bundles, in which a plurality of fuel rods are arranged in lattice fashion which upper and lower portions are supported by tie-plates, are bundled and then covered by a square channel box. The control rod is movably arranged within a space formed by adjoining channel boxes. A spacer of trapezoidal section is disposed in the central portion on the side of the channel box over substantially full length in height direction, and a neutron instrumented tube is disposed in the central portion inside the channel box. Thus, where a horizontal load is exerted due to earthquake or the like, the spacers come into contact with each other to support the channel box and prevent it from abnormal vibrations. (Furukawa, Y.)

  2. The use of genetic algorithms with niching methods in nuclear reactor related problems; A utilizacao dos metodos de nichos dos algoritmos geneticos na otimizacao de problemas de reatores nucleares

    Energy Technology Data Exchange (ETDEWEB)

    Sacco, Wagner Figueiredo

    2000-03-01

    Genetic Algorithms (GAs) are biologically motivated adaptive systems which have been used, with good results, in function optimization. However, traditional GAs rapidly push an artificial population toward convergence. That is, all individuals in the population soon become nearly identical. Niching Methods allow genetic algorithms to maintain a population of diverse individuals. GAs that incorporate these methods are capable of locating multiple, optimal solutions within a single population. The purpose of this study is to test existing niching techniques and two methods introduced herein, bearing in mind their eventual application in nuclear reactor related problems, specially the nuclear reactor core reload one, which has multiple solutions. Tests are performed using widely known test functions and their results show that the new methods are quite promising, specially in real world problems like the nuclear reactor core reload. (author)

  3. Entre tradição e modernidade: Almeida Reis eo Paraíba

    Directory of Open Access Journals (Sweden)

    Alberto Martín Chillón

    2014-11-01

    Full Text Available Often highlighted are the modern features of some art works that caused them to be rejected in their time, such as the Paraíba, by Almeida Reis, 1866, set in Europe during the scholarship of the artist. In this paper, we analyze and question the modern or traditional character of this work, through its detailed study, its relationships and influences, its situation in the tradition of the subject represented, and the important fact that it was received into a very different artistic environment to the one in which it was created.

  4. Comparative analysis of three atmospheric dispersion coefficient systems at the Angra dos Reis, RJ, region; Analise comparativa de tres sistemas de coeficientes de dispersao atmosferica na regiao de Angra dos Reis, RJ

    Energy Technology Data Exchange (ETDEWEB)

    Biagio, Rosa Maria de Souza

    1982-07-01

    A comparative analysis was made in this work among Pasquill-Gifford (PG) atmospheric dispersion coefficients and those determined at the Juelich and Karlsruhe sites with the purpose of suggesting which one would be the most applicable to the Angra site. Each one of the three systems was determined by different experiments, carried out over sites with diversified features. The systems of Juelich and Karlsruhe were obtained over sites with high surface roughness and from stacks (elevated releases), while the PG system was obtained over sites with a small surface roughness and from ground level releases. The results of the application of these systems at a complex site like Angra,which has a highly diversified structure encompassing sea, vegetation, predominance of light winds and stable stability classes, show that the PG system, the most used in the world, is still the best choice. (author)

  5. Sorption of {sup 60}Co and {sup 137}Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil; Sorcao de {sup 60}Co e {sup 137}Cs em sedimentos do Saco de Piraquara de Fora - Angra dos Reis

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Franciane M.; Martins, Nadia S.F.; Lauria, Dejanira D., E-mail: francian@ird.gov.br, E-mail: nadia@ird.gov.br, E-mail: dejanira@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil); Ferreira, Ingryd M., E-mail: ingrydmarques@hotmail.com [Instituto Federal do Rio de Janeiro (IFRJ), RJ (Brazil); Azevedo, Izabella M.A.P., E-mail: izabella_azevedo@id.uff.br [Universidade Federal Fluminense (UFF), Niteroi, RJ (Brazil)

    2013-07-01

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of {sup 60}Co and {sup 137}Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 10{sup 2}.

  6. Quality assurance of civil works during the construction of the nuclear power plant Unit II Angra dos Reis in Brazil

    International Nuclear Information System (INIS)

    Nellessen, H.G.

    1980-01-01

    The lecture summarizes the structure of the applied Quality Assurance Manual, which is subdivided into three sections: (1) Quality Assurance Program, (2) General Proceedings and (3) Inspection Programs. Since the power plant was designed according to DIN standards but supervision and construction are being performed following ASTM or Brazilian standards, the Quality Assurance Manual and the Quality Assurance organization were developed specifically for the Angra-Site. The applied system is illustrated by practical examples of pile foundations. Quality Assurance supervision and flow charts showing the interaction of the quality control organization. (orig.)

  7. The foundation of the units 2 and 3 of the nuclear power plant Angra dos Reis/Brasil

    International Nuclear Information System (INIS)

    Bokemeyer, R.; Linder, W.R.

    1979-01-01

    The report describes the extraordinarily difficult and comprehensive foundation activities which started in Summer 1977. Because of the high building weight, and the gigantic soft superimposed layers prevailing on the site, a bay, a foundation on more than 2500 large-scale drilling posts for both units is planned. The posts have to be inserted into loose marine sediments, gneiss decomposition grounds and weather-worn rocks down to an average of 36 m, and often down to 60 m, into competent rocks, mostly gneiss or granite. Because of the size and the changing consistency of the weather-worn rocks and the great amount of the hard boulders which are deposited in the soft layers enormous technical difficulties have to be surmounted as the drilling work has to be accomplished within a very short time. It has not been necessary yet to cope with difficulties of this dimension. (orig./HP) [de

  8. 137Cs, 60Co and 125I bioaccumulation by seaweeds from the Angra dos Reis nuclear power plant region

    International Nuclear Information System (INIS)

    Guimaraes, J.R.; Penna-Franca, E.

    1985-01-01

    As part of a broad research program on the behaviour of critical radionuclides to be discharged into the sea by the first Brazilian nuclear power plant, the uptake, accumulation and loss of 137 Cs, 60 Co and 125 I by locally abundant seaweed species was studied. Uptake in static 12 liter aquarium experiments reached apparent steady-state in 2 to 7 days ( 60 Co and 125 I), or 2 to 3 weeks ( 137 Cs). Elimination followed a reverse pattern, being comparatively fast for 137 Cs and slow for 60 Co and 125 I. Dry weight bioaccumulation factors (BFs) were variable, falling in the 10 1 range for 137 Cs, 10 3 for 125 I and 10 3 to 10 4 for 60 Co. Various short-term experiments, performed over a 16 month period, showed marked temporal variations of 60 Co BFs for all species. The results demonstrated that the studied species may play an important role in the transfer of the critical radionuclides through local food webs and can be employed as useful monitors for routine or accidental radionuclide releases. (author)

  9. Composition of the marine macroflora in the Saco do Piraquara de Fora, CNAAA, Angra dos Reis, RJ

    International Nuclear Information System (INIS)

    Gusmao Pedrini, A. de; Pereira, M.A.S.

    1983-01-01

    A qualitative survey of the macroscopic algae of the benthic flora in the area, of Saco do Piraquara de Fora follow the seasonality of species, and indication of the most abundant group in the sites of collection, are presented. (E.G.) [pt

  10. Sorption of 60Co and 137Cs in sediments at Piraquara de Fora, Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    Carvalho, Franciane M.; Martins, Nadia S.F.; Lauria, Dejanira D.; Ferreira, Ingryd M.; Azevedo, Izabella M.A.P.

    2013-01-01

    In this study, sediment of Piraquara de Fora, located near the launch area of the effluents of the Central Nuclear Almirante Alvaro Alberto - CNAAA Nuclear Power Plants, were collected. It were determined the parameters particle size and cationic exchange capacity (CTC). From the sorption curves of 60 Co and 137 Cs, obtained experimentally in the laboratory, were estimated preliminary values of Kd at equilibrium, for these radionuclides in order of magnitude of 10 2

  11. Stockscheider Quartzo-Moscovíticos e Pegmatíticos na Zona de Cúpula do Granitóide Ritápolis, Região de São João del Rei, Minas Gerais

    Directory of Open Access Journals (Sweden)

    Ronaldo Mello Pereira

    2011-01-01

    Full Text Available Em quatro áreas da Província Pegmatítica de São João del Rei são encontrados clusters de corpos constituídos basicamente por quartzo-moscovita, que estão em estreita associação com pegmatitos posicionados paralelamente à zona de cúpula do granitóide Ritápolis, no contato deste com as rochas metassedimentares - metavulcânicas da faixa greenstone Rio das Mortes. As associações mineralógicas determinadas para os stockscheider quartzo-moscovíticos e pegmatíticos, representadas por columbita-tantalita, cassiterita, gahnita, zircão, xenotímio e monazita, são semelhantes às determinadas para os demais pegmatitos da Província Pegmatítica de São João del Rei. Os tipos de inclusões (Pb-tantalita, microlita, Pb-microlita, U-microlita, Ba-microlita, zircão rico em Hf contidas na Fe-columbita associada ao stocksheider também são as mesmas da Fe-columbita associada aos pegmatitos mais evoluídos da província. Os stockscheider quartzo-moscovíticos e pegmatíticos estão vinculados ao granitóide Ritápolis e este, aos demais pegmatitos da Província Pegmatítica de São João del Rei. O mecanismo proposto para a formação dos clusters de stockscheider quartzo-muscovíticos e pegmatíticos é o da cristalização de bolsões localizados contendo fluidos tardi-magmáticos e pós-magmáticos (hidrotermais - metassomáticos segregados do magma granítico, os quais foram injetados ao longo de fraturas paralelas à zona de cúpula do granitóide Ritápolis.

  12. A series of luminescent Re(I) complexes with electron-donor/acceptor moieties: Synthesis, characterization, and photoluminescence

    International Nuclear Information System (INIS)

    Ge Hu; Qing She; Lei Guo

    2012-01-01

    In this paper, we synthesize three Re(I) complexes of Re(CO) 3 (PPO)Br, Re(CO) 3 (PTO)Br, and Re(CO) 3 (PBI)Br, where PPO=2-phenyl-5-(pyridin-2-yl)-1,3,4-oxadiazole, PTO=2-(pyridin-2-yl)-5-p-tolyl-1,3,4-oxadiazole, PBI=2-(pyridin-2-yl)-1H-benzo[d]imidazole. Their single crystals and photophysical properties are measured and discussed in detail. The correlation between ligand structure and corresponding PL characteristics of Re(I) complex has been investigated. It is found that a ligand with strong electron-donor can efficiently increase both absorption and emissive energy of Re(I) complex. In addition, electron-rich ligand can increase the electron density of the complex and thus enhance the oscillator strength of electronic transition, improving the photoluminescence performance. - Highlights: ► Three novel phosphorescent Re(I) complexes are synthesized. ► Molecular structures, photophysical, and electronic properties are studied. ► Strong electron-donor can increase emissive energy. ► Electron-rich ligand can enhance the oscillator strength of electronic transition.

  13. Cinema, história pública e educação: circularidade do conhecimento histórico em Xica da Silva (1976) e Chico Rei (1985)

    OpenAIRE

    Rodrigo de Almeida Ferreira

    2014-01-01

    No contexto da educaçãA tese Cinema, história pública e educação: circularidade do conhecimento histórico em Xica da Silva (1976) e Chico Rei (1985) propõe compreender o filme de gênero histórico no que tange a mediação, divulgação e produção do conhecimento histórico, tanto em espaço escolar, quanto não-escolar. Problematiza-se esse gênero fílmico para o saber histórico a partir da análise dos imaginários sociais presentes nos filmes, construídas na interface entre a historiografia e outros ...

  14. Olhos de inferno: a morte no Rei Édipo de Sófocles

    Directory of Open Access Journals (Sweden)

    Ortep J. Trindade-Serra

    1995-12-01

    Full Text Available Os derradeiros versos do "Rei Édipo", de Sófocles, versos que se referem a um tópos consagrado, ocasionaram, através de uma paráfrase de Frínico, a criação do "mito" de Sófocles, cuja vida feliz a tradição consagrou como uma antítese do destino de seu personagem. O paradoxo desses versos, todavia, merece consideração mais profunda. Com efeito, em toda a tragédia a morte é representada de maneira paradoxal. Édipo faz a experiência de uma situação liminar em que morte e vida, cegueira e visão se confundem. Uma evidência disso é simbolicamente dada no verso 987 de Oedipus Rex.

  15. Tradução de teatro grego: Édipo Rei, de Sófocles.

    Directory of Open Access Journals (Sweden)

    Tereza Virgínia Ribeiro Barbosa

    2009-02-01

    Full Text Available http://dx.doi.org/10.5007/2175-7968.2008v2n22p89 Tendo em vista a especificidade do texto teatral, debatemos quais os elementos desse gênero devem ser preservados na tradução; discutimos a importância de algumas metáforas-base e das materializações no texto poético teatral como fios condutores da tradução. Finalmente, focalizamos as aparições da metáfora da terra (gê na peça de Sófocles, Édipo Rei e suas eventuais substituições por outros termos.

  16. Tradução de teatro grego: Édipo Rei, de Sófocles.

    OpenAIRE

    Barbosa, Tereza Virgínia Ribeiro

    2009-01-01

    http://dx.doi.org/10.5007/2175-7968.2008v2n22p89Tendo em vista a especificidade do texto teatral, debatemos quais os elementos desse gênero devem ser preservados na tradução; discutimos a importância de algumas metáforas-base e das materializações no texto poético teatral como fios condutores da tradução. Finalmente, focalizamos as aparições da metáfora da terra (gê) na peça de Sófocles, Édipo Rei e suas eventuais substituições por outros termos. Considering the specificity of theatrical t...

  17. A Companhia de Reis Santa Luzia, Londrina/PR: considerações acerca do catolicismo tradicional popular brasileiro e o papel de seus mestres-rituais

    Directory of Open Access Journals (Sweden)

    André Camargo Lopes

    2009-07-01

    Full Text Available Este artigo é resultado de uma série deentrevistas realizadas com o mestreembaixadorAntonio Francisco, da Companhiade Reis Santa Luzia, assim como o trabalho deobservação participante da jornada de Reis2007/2008 que realizamos junto a Companhiapelos bairros do município de Londrina/PR.Temos por objetivo apontar neste artigo algunselementos que caracterizam o catolicismo tradicionalpopular brasileiro, em seu aspectocultural, configurando a partir desta perspectivaa formação de seus mestres-rituais e a estruturaritualística e organizacional da jornada deReis dentro deste universo cultural.

  18. Granular corneal dystrophy Groenouw type I (GrI) and Reis-Bücklers' corneal dystrophy (R-B). One entity?

    Science.gov (United States)

    Møller, H U

    1989-12-01

    This paper maintains that Reis-Bücklers' corneal dystrophy and granular corneal dystrophy Groenouw type I are one and the same disease. Included are some of the technically best photographs of Reis-Bücklers' dystrophy found in the literature, and these are compared with photographs from patients with granular corneal dystrophy examined by the author. It is argued that most of the histological and ultrastructural findings on Reis Bücklers' dystrophy described in the literature are either congruent with what is found in granular corneal dystrophy or unspecific.

  19. Extreme-value limit of the convolution of exponential and multivariate normal distributions: Link to the Hüsler–Reiß distribution

    KAUST Repository

    Krupskii, Pavel; Joe, Harry; Lee, David; Genton, Marc G.

    2017-01-01

    The multivariate Hüsler–Reiß copula is obtained as a direct extreme-value limit from the convolution of a multivariate normal random vector and an exponential random variable multiplied by a vector of constants. It is shown how the set of Hüsler–Reiß parameters can be mapped to the parameters of this convolution model. Assuming there are no singular components in the Hüsler–Reiß copula, the convolution model leads to exact and approximate simulation methods. An application of simulation is to check if the Hüsler–Reiß copula with different parsimonious dependence structures provides adequate fit to some data consisting of multivariate extremes.

  20. Extreme-value limit of the convolution of exponential and multivariate normal distributions: Link to the Hüsler–Reiß distribution

    KAUST Repository

    Krupskii, Pavel

    2017-11-02

    The multivariate Hüsler–Reiß copula is obtained as a direct extreme-value limit from the convolution of a multivariate normal random vector and an exponential random variable multiplied by a vector of constants. It is shown how the set of Hüsler–Reiß parameters can be mapped to the parameters of this convolution model. Assuming there are no singular components in the Hüsler–Reiß copula, the convolution model leads to exact and approximate simulation methods. An application of simulation is to check if the Hüsler–Reiß copula with different parsimonious dependence structures provides adequate fit to some data consisting of multivariate extremes.

  1. Evaluation of two processes of hydrogen production starting from energy generated by high temperature nuclear reactors; Evaluacion de dos procesos de produccion de hidrogeno a partir de energia generada por reactores nucleares de alta temperatura

    Energy Technology Data Exchange (ETDEWEB)

    Valle H, J., E-mail: jvalle@upmh.edu.mx [Universidad Politecnica Metropolitana de Hidalgo, Boulevard Acceso a Tolcayuca 1009, Ex-Hacienda San Javier, 43860 Tolcayuca, Hidalgo (Mexico)

    2013-10-15

    In this work an evaluation to two processes of hydrogen production using energy generated starting from high temperature nuclear reactors (HTGR's) was realized. The evaluated processes are the electrolysis of high temperature and the thermo-chemistry cycle Iodine-Sulfur. The electrolysis of high temperature, contrary to the conventional electrolysis, allows reaching efficiencies of up to 60% because when increasing the temperature of the water, giving thermal energy, diminishes the electric power demand required to separate the molecule of the water. However, to obtain these efficiencies is necessary to have water vapor overheated to more than 850 grades C, temperatures that can be reached by the HTGR. On the other hand the thermo-chemistry cycle Iodine-Sulfur, developed by General Atomics in the 1970 decade, requires two thermal levels basically, the great of them to 850 grades C for decomposition of H{sub 2}SO{sub 4} and another minor to 360 grades C approximately for decomposition of H I, a high temperature nuclear reactor can give the thermal energy required for the process whose products would be only hydrogen and oxygen. In this work these two processes are described, complete models are developed and analyzed thermodynamically that allow to couple each hydrogen generation process to a reactor HTGR that will be implemented later on for their dynamic simulation. The obtained results are presented in form of comparative data table of each process, and with them the obtained net efficiencies. (author)

  2. A História encenada: O Processo do Rei, de João Mario Grilo, a imagem melancólica de um país

    Directory of Open Access Journals (Sweden)

    Tavares, Mirian

    2014-04-01

    Full Text Available This text analyses João Mário Grilo’s film: O Processo do Rei (The King’s Trial (1989. Based on the trial of Afonso VI, the director was able to remain faithful to the seventeenth century historical setting, but at the same time give it a contemporary feel, while exploring eternal and recurrent aspects of the story itself. Cinema, in this film, works as a stage where the story reveals the scenography that history books habitually conceal. In order to thoroughly examine the issues raised by this text, the article discusses the relationship between cinema and theatre starting with the concept of mise en scéne. What joins and separates these two artistic forms? How has cinema built its own mise en scéne throughout its history while resorting mostly to editing?En este texto analizaré la película O Processo do Rei (1989, de João Mário Grilo. Basado en el proceso contra D. Afonso VI, el realizador consiguió ser fiel al tiempo histórico –siglo XVII-, pero también profundamente contemporáneo, explorando aspectos eternos y cíclicos de la propia Historia. El cine, en esta película, funciona como un escenario donde la Historia revela la escenografía que los libros de Historia acostumbran a ocultar. Para profundizar en esta cuestión comienzo por discutir las relaciones entre el cine y el teatro a partir do concepto de mise en scéne. ¿Qué aproxima, y qué distancia, a estas dos formas artísticas? ¿De qué manera el cine, a lo largo de su historia, construyó su propia puesta en escena recurriendo, sobre todo, al montaje?

  3. Sobre a relação entre Rei, Lei e Parlamento no Antigo Regime

    Directory of Open Access Journals (Sweden)

    Alexander Martins Vianna

    2010-09-01

    Full Text Available Este ensaio pretende desenvolver um entendimento sobre as relações mutáveis entre Rei, Lei e Parlamento na Inglaterra, entre a “Grande Matéria” (1532-1535 de Henrique VIII e a Guerra Civil Inglesa (meados do século XVII, que as situe adequadamente nos caracteres institucionais (práticos e doutrinais do Antigo Regime, rompendo com a chave de leitura da historiografia liberal que, desde o século XIX, tende a essencializar uma espécie de distinção histórica entre Inglaterra e França, como se fossem protótipos, respectivamente, de “contratualismo” e “absolutismo”.

  4. Partida de um reator anaeróbio horizontal para tratamento de efluentes do processamento dos frutos do cafeeiro Start-up of an anaerobic horizontal-flow reactor for treating wastewater from a coffee fruits processing

    Directory of Open Access Journals (Sweden)

    Alisson C. Borges

    2009-01-01

    Full Text Available O presente estudo teve o objetivo de avaliar a partida e a adaptação de um reator anaeróbio horizontal de leito fixo (RAHLF no tratamento de águas residuárias do processamento primário dos frutos do cafeeiro (ARC. O reator foi construído com tubos de PVC de 0,2 m de diâmetro e 3,2 m de comprimento. O sistema foi preenchido com cubos de espuma de poliuretano para imobilização de biomassa ativa. O reator apresentou volume total de 0,1 m³ e volume útil equivalente a 0,04 m³. Em média, houve remoção de 49% da matéria orgânica, com o reator trabalhando sob carga orgânica volumétrica média de 2,66 kg m-3 d-1, medida como DQO. A suplementação de alcalinidade, somada à inoculação prévia de biomassa, proporcionou partida estável do RAHLF, confirmada pelo consumo de ácidos voláteis e adaptação da microbiota ao resíduo. O sistema apresentou resistência às variações de vazão e de carga orgânica observadas, e os teores de fenol e potássio monitorados não causaram inibição da atividade biológica no RAHLF. O maior controle sobre as variações de carga é fator importante na continuidade dos estudos.This study aimed to evaluate the start-up and the adaptation of an anaerobic horizontal-flow immobilized biomass (HAIB reactor in order to treat wastewater from a primary processing of coffee fruits. The reactor was built with PVC tubes of 0.2 m in diameter and 3.2 m in length. The system was filled with cubes of polyurethane foam for immobilization of active biomass. The reactor presented a total capacity of 0.1 m³ and reaction volume equal to 0.04 m³. 49% of organic matter. Removal efficiency was observed, with medium organic volumetric loads equal to 2.66 kg m-3 d-1 (as chemical oxygen demand. The supplementary addition of alkalinity and the previous biomass inoculation provided a stable start-up of the reactor, as confirmed by the reduction of volatile acids and an adaptation of the present microbiology community

  5. A support vector machine designed to identify breasts at high risk using multi-probe generated REIS signals: a preliminary assessment

    Science.gov (United States)

    Gur, David; Zheng, Bin; Lederman, Dror; Dhurjaty, Sreeram; Sumkin, Jules; Zuley, Margarita

    2010-02-01

    A new resonance-frequency based electronic impedance spectroscopy (REIS) system with multi-probes, including one central probe and six external probes that are designed to contact the breast skin in a circular form with a radius of 60 millimeters to the central ("nipple") probe, has been assembled and installed in our breast imaging facility. We are conducting a prospective clinical study to test the performance of this REIS system in identifying younger women (detection of a highly suspicious breast lesion and 50 were determined negative during mammography screening. REIS output signal sweeps that we used to compute an initial feature included both amplitude and phase information representing differences between corresponding (matched) EIS signal values acquired from the left and right breasts. A genetic algorithm was applied to reduce the feature set and optimize a support vector machine (SVM) to classify the REIS examinations into "biopsy recommended" and "non-biopsy" recommended groups. Using the leave-one-case-out testing method, the classification performance as measured by the area under the receiver operating characteristic (ROC) curve was 0.816 +/- 0.042. This pilot analysis suggests that the new multi-probe-based REIS system could potentially be used as a risk stratification tool to identify pre-screened young women who are at higher risk of having or developing breast cancer.

  6. Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

    Energy Technology Data Exchange (ETDEWEB)

    Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M. [Eletrobras Termonuclear S.A. - ELETRONUCLEAR, Rio de Janeiro, RJ (Brazil). Gerencia de Analise de Tensoes GAN.T], e-mail: glauco@eletronuclear.gov.br, e-mail: tarci@eletronuclear.gov.br, e-mail: prates@eletronuclear.gov.br

    2009-07-01

    Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

  7. Reactor building 3D-model for evaluating the pressures on concrete regularization and foundation waterproofing membrane

    International Nuclear Information System (INIS)

    Mello Junior, Glauco J.T.; Cardoso, Tarcisio de F.; Prates, Carlos L.M.

    2009-01-01

    Angra dos Reis site in Brazil has already 2 operating PWR NPPs. Unit 3, with identical design to Unit 2, also a 1350 MW PWR, is expected to have its construction started in 2009. This new plant shall be founded directly on sound rock. The first step is to prepare this rock surface with a concrete regularization and a foundation waterproofing membrane. This study presents a 3D model approach of the corresponding reactor building to verify the maximum pressure acting on this surface. The 3D model permits to show a more realistic pressure distribution at every foundation specific detail. A static analysis is performed using ANSYS Mechanical Release 11.1. Dead weight, permanent and live loads, Safe Shutdown Earthquake (SSE) combined with Burst Pressure Wave (BPW) from the Feedwater Tank (SSB=SSE+BPW) and differences of temperature are taken into account. Considering all foundation nodes , the pressure distribution on the waterproofing membrane for each load case is obtained for vertical and horizontal directions, which corresponds to compression and tangential reaction loads. The maximum values occur in distinct positions for each load case. The maximum results are obtained according to DIN 25449 (2008) load combination criteria. The results are compared to a simplified analysis performed before, showing a good agreement in global values. (author)

  8. A miopia da eficiência entrevista com Fábio Wanderley Reis

    Directory of Open Access Journals (Sweden)

    Marcos Antônio Lopes

    2004-12-01

    Full Text Available Fábio Wanderley Reis é professor emérito da Faculdade de Filosofia e Ciências Humanas da Universidade Federal de Minas Gerais. Doutor em Ciência Política pela Universidade Harvard, é organizador de trabalhos de relevo como A democracia no Brasil: dilemas e perspectivas, com Guillermo O'Donnell. Por seu Política e Racionalidade, foi ganhador do Prêmio Anpocs, como melhor obra científica em Ciências Humanas. Seus livros mais recentes são Mercado e Utopia (Edusp, 2000 e Tempo Presente (Editora UFMG, 2002.Obra labiríntica, por sua riqueza temática-uma visão panorâmica da política brasileira no último quarto de século -, Tempo Presente, resenhado por Mediações, revela-nos o alcance da atividade intelectual de um pensador dotado de vasta cultura política e de apurado grau de sofisticação analítica.Aposentado há alguns anos, depois de ensinar por mais de três décadas, ele tem participado ativamente do debate público. Os principais veículos de nossa grande imprensa têm dado destaque ao rigor crítico de suas idéias. Observador arguto da cena política brasileira atual, Fábio Wanderley concedeu a seguinte entrevista a Mediações.

  9. Análise de expressões formulaicas em textos tradicionais das Folias de Reis

    Directory of Open Access Journals (Sweden)

    Elisângela Tavares Dias

    2013-06-01

    Full Text Available Neste trabalho, focalizamos a relação entre intertexto e expressões formulaicas em Folias de Reis brasileiras. À luz da tradição discursiva (cf. Kabatek, 2006; Koch, 1997; Oesterreicher, 1997, e seguindo ferramentas teórico-metodológicas da Análise Textual (cf. Jubran, 2006; Marcuschi, 2008, nossa proposta é apontar como se dá a reiterabilidade do texto em dois momentos da folia: o início e a chegada da jornada. Dialogamos também com alguns autores que consubstanciam o pareamento escrito/falado na produção da língua/linguagem em sua interlocução, a saber: Zumthor (1997 e Ong (1982, dentre outros. Recorremos para nossa análise, a um corpus representativo de quatorze folias presentes nos estados de MG, RJ, GO, ES, SP e RN. Em face disso, suscitar essa relação dialógica permite-nos pontuar que é inegável a contribuição dada pela tradição oral, seja por seus traços ideológicos e histórico-culturais, seja pela continuidade do folguedo, sobretudo, porque a utilização de um texto dá realidade à retórica que o funda, pois é pela atualização da voz que este se justifica e existe em situação de performance (ZUMTHOR,1997.

  10. Validación del modelo REI para medir la clase social en población adulta

    Directory of Open Access Journals (Sweden)

    Antonio Cabrera de León

    2009-01-01

    mayor riesgo de problemas de salud, con mayor fuerza en las mujeres: sedentarismo (OR = 1,8, obesidad (OR = 4,4, obesidad abdominal (OR = 5,4, síndrome metabólico (OR = 3,4 y diabetes mellitus (OR = 2,0. Conclusiones: REI es un indicador válido, no basado en la ocupación ni en la situación laboral, fácilmente estandarizable, apto para medir cuantitativamente la clase social en estudios que precisen analizar el impacto de la misma como determinante de salud.

  11. Estudo observacional do comportamento empreendedor de Irineu Evangelista de Sousa da ótica de Filion no filme "Mauá - o Imperador e o Rei"

    Directory of Open Access Journals (Sweden)

    Fátima Regina Ney Matos

    Full Text Available Análise do comportamento empreendedor de Irineu Evangelista de Sousa, observado no filme "Mauá - O Imperador e o Rei". Procurou-se usar como base argumentativa o trabalho de Louis Jacques Filion (2004, 2000, 1993, 1991 sobre características empreendedoras básicas - inovação, aprendizagem, rede de relações e visão. A escolha do tema deveu-se ao pouco conhecimento dos alunos de graduação e pós-graduação em administração - detectado em uma pesquisa exploratória informal - sobre os empreendedores brasileiros e seu papel na evolução econômica do país, sendo relevante este resgate histórico. Após cinco exibições coletivas e algumas exibições individuais do filme, foi realizado um estudo observacional, tipo de observação de "segunda mão", indireta e não participante, com produtivas discussões em equipe. Na revisão bibliográfica buscou-se contextualizar, de maneira sucinta, as características do comportamento empreendedor da ótica de Filion (1991. Pode-se concluir que as características empreendedoras propostas na tipologia do autor apresentam-se com vigor no comportamento do Barão de Mauá, um homem à frente de seu tempo e que procurou contribuir na construção de um novo projeto para o Brasil, possibilitando a transição de um modelo econômico agrário exportador e escravocrata para uma economia de mercado baseada na industrialização, no trabalho assalariado e na livre iniciativa, sendo esse conhecimento essencial para o desenvolvimento do senso crítico e analítico do aluno.

  12. Autonomia profissional dos professores

    OpenAIRE

    Guerra, Teresa P.; Veiga, Feliciano

    2007-01-01

    Este estudo pretendeu analisar as representações dos professores acerca da sua autonomia em contexto escolar, com recurso a uma amostra de 203 professores de ambos os sexos, pertencentes a escolas dos distritos de Lisboa, Setúbal, Leiria e Aveiro. Utilizou-se a Escala de Autonomia Profissional dos Professores (EAPP).

  13. Study of 137Cs e 60Co sorption in sediments from Saco de Piraquara de Fora, Angra dos Reis and its application for environmental monitoring

    International Nuclear Information System (INIS)

    Ferreira, Ingryd Marques

    2016-01-01

    Both the suspended solid particles and the bed sediments sorb radionuclides, released in water systems. Sorption is usually represented mathematically by the distribution coefficient that is based in equilibrium between phases. Here the adsorption/desorption kinetics of 60 Co and 137 Cs in sea water were simulated by batch equilibrium experiments with sediments in two points (PT - 01, PT - 02) from Saco de Piraquara de Fora inlet (SPF). For both radionuclides, partition coefficient values (Kd) for the sampling point PT - 02 (509 and 385 L/kg for 60 Co and 137 Cs, respectively) were higher than the values determined for PT - 01 one (426 and 182 L/kg for 137 Cs and 60 Co, respectively). The higher values of Kd of PT-02 reflects the higher CEC (71,4 cmolc.dm 3 ) and content of mud < 63 μm (87%) when compared to PT-01 (CEC of 39,5 cmol c .dm 3 ) and mud (55%). In comparison with the values reported in the literature, the found Kd values are low, which may be related to the predominance of kaolinite, which is a clay of low sorption capacity. The Kd values with an increase in temperature of 23 deg C to 27 deg C were similar ( 60 Co in PT-02 and 137 Cs in both sediment) or 27 ° C values were higher ( 60 Co the PT-01). With increasing temperature to 31 °C Kd values for the two radionuclides showed a decrease. However, increasing temperature increases the desorption of the two radionuclides for both sediments The sorption process is spontaneous and favorable for both sediments and the model of sorption can be fitted by both Freundlich and Langmuir sorption isotherms. The maximum amount of 60 Co that can be sorbed on sediments were 1,64 10 -5 moles/g (4,12 10 10 Bq/g) and 2,79 10 -5 moles/g (7,03 10 10 Bq/g) to PT-01 and PT-02, respectively, and of 137 Cs 1,99 10 -6 moles/g (9,70 10 8 Bq/g) and 6,60 10 -6 mol/g (2,87 10 9 Bq/g ) to PT-01 and PT-02. Two areas in SPF can potentially accumulate 137 Cs: sediments located near the effluent discharge and the area located north of this site. An area in the interface of SPF and the bay of Ribeira would potentially the best accumulated of 60 Co. (author)

  14. Levels of {sup 137}Cs and {sup 40}K in marine superficial sediments near the Angra Nuclear Power Plant (Angra dos Reis, SE Brazil)

    Energy Technology Data Exchange (ETDEWEB)

    Lima Ferreira, Paulo Alves de; Farina Amorim, Lais; Marone Tura, Pedro; Medeiros Zacheo, Valter Andre; Lopes Figueira, Rubens Cesar [Universidade de Sao Paulo (IO-USP), SP (Brazil). Inst. Oceanografico

    2015-07-01

    This study evaluated the spatial distribution of two environmentally relevant radionuclides, {sup 137}Cs and {sup 40}K, in marine superficial sediments around the Angra Nuclear Power Plant, the only Brazilian nuclear power plant complex, thus establishing a baseline for bottom sediments, given the international importance of environmental monitoring around nuclear facilities. It was observed that these radionuclides are mostly present in the muddy sediments as a result of their stronger association with its fine-grained fraction, and that their lowest levels are located around the liquid effluent discharge of the plant, as a consequence of the prevented deposition of fine sediments due to the strong discharge water flux. The comparison of the {sup 137}Cs activities in the region with other locations in the world showed that the presence of this artificial nuclide is due to the atmospheric fallout from past nuclear tests made during the Cold War, not to the nuclear power plant activities.

  15. Impact assessment for the aquatic biota arising from discharges of radioactive liquid effluents into the marine environment - Angra dos Reis nuclear power plants

    International Nuclear Information System (INIS)

    Lauria, D.C.; Peres, S.S.; Martins, S.F.

    2011-01-01

    The Piraquara de Fora Bay receives the liquid effluents from the two Brazilian nuclear power plants (NPPs): Angra I that has been operating since 1985 and Angra II that started operating in 2000. The monitoring data set obtained by IRD/CNEN for marine samples over a period of 25 years (from 1985 to 2010) were statistically evaluated. Despite the high presence of non detect observations, suitable statistical tests were applied to compare 60 Co levels in sediments between two periods of time and from different sampling locations. The natural dose and the dose derived from the NPPs routine radioactive releases on the marine biota were assessed by the Erica tool. The highest value of dose rate due to the naturally occurrence radionuclides was estimated to be around 0.6 μGy h -1 for phytoplankton, mainly due to internal dose contribution of 238 U, while fishes received the highest dose (value around 0.4 μGy h -1 ) due to the radionuclide discharges of the NPPs. Accordingly, the dose rates to the studied species (fish, crustacean, macroalgae, zooplankton and phytoplankton) were clearly below the Erica screening level of 10 μGy h -1 , indicating no significant radiological impact of NPPs on these species. (author)

  16. Sedimentological, textural, mineralogical and geochemical study of surface sediments and suspension material in Baia da Ribeira, Angra dos Reis, RJ, Brazil

    International Nuclear Information System (INIS)

    Lima, Samuel do Carmo

    1985-01-01

    The geochemistry dispersion of the metals in aquatic environment is related to the physical chemistry proprieties of these elements as to their interaction by sorption on and desorption from solid particles. These interaction must be understood within the environmental dynamic, with its hydrological, sedimentological, chemical, physical and biological processes that may take the toxic elements (stables metals and radionuclides) to the bio alimentary chain. It was observed at the Ribeira Bay, its hydrodynamic behaviour through the suspension material and particulate organic carbon dispersion. And, through the textural, mineralogical and chemical parameters it was observed the behaviour of the geochemistry processes of the sedimentary materials and the influence that they may submit to the metals dispersion. (author)

  17. Ichthyofauna community from Saco de Piraquara de Fora area by the influence of liquid effluents from the Almirante Alvaro Alberto Nuclear Power in Angra dos Reis

    International Nuclear Information System (INIS)

    Almeida, A.F.V. de

    1995-01-01

    To verify if thermal and chemical effluents of Angra I Nuclear Power Plant are affecting the marine ictiofauna, Furnas Centrais Eletricas S.A. has implemented a monitoring program near the discharge area. Specific composition, frequency, specific relative abundance, specific diversity and others parameters are studied. The main target of this study is to check if the analyzed parametrers show any kind of impact on fish population. In this paper the results were presented. (author). 7 refs, 3 figs, 3 tabs

  18. Risk perception of workers at nuclear power plants from Angra dos Reis, Rio de Janeiro State: preliminary study of a reality on health

    International Nuclear Information System (INIS)

    Scliar, Claudio; Vasconcelos, Ana S.F.; Rodrigues, Anacely S.; Santos, Gloria R.R.; Albuquerque, Patricia O.; Carvalho, Sirlene L.A.; Oliveira, Simone

    1999-01-01

    The present paper analyses some social and occupational parameters that may have an influence on the risk perception levels of the workers in Brazilian Nuclear Power pLants, emphasizing possible relationship between the specificity of job tasks/literacy and risk perception. This study was based on two findings from the scientific literature: risk perception increases proportionally with literacy; risk perception decreases proportionally with the specificity of job tasks. The results of this pilot study indicates that risk perception levels of the workers in Brazilian Nuclear Power Plants increases proportionally with the literacy and specificity of their job tasks, contrasting with the american and european profiles. These results appears as a singular reality of those workers and the possibility of a new regard over the management and decision making process in the Brazilian Nuclear Power Plants. (author)

  19. Levels of 137Cs and 40K in marine superficial sediments near the Angra Nuclear Power Plant (Angra dos Reis, SE Brazil)

    International Nuclear Information System (INIS)

    Lima Ferreira, Paulo Alves de; Farina Amorim, Lais; Marone Tura, Pedro; Medeiros Zacheo, Valter Andre; Lopes Figueira, Rubens Cesar

    2015-01-01

    This study evaluated the spatial distribution of two environmentally relevant radionuclides, 137 Cs and 40 K, in marine superficial sediments around the Angra Nuclear Power Plant, the only Brazilian nuclear power plant complex, thus establishing a baseline for bottom sediments, given the international importance of environmental monitoring around nuclear facilities. It was observed that these radionuclides are mostly present in the muddy sediments as a result of their stronger association with its fine-grained fraction, and that their lowest levels are located around the liquid effluent discharge of the plant, as a consequence of the prevented deposition of fine sediments due to the strong discharge water flux. The comparison of the 137 Cs activities in the region with other locations in the world showed that the presence of this artificial nuclide is due to the atmospheric fallout from past nuclear tests made during the Cold War, not to the nuclear power plant activities.

  20. Assessment of impact of a severe accident at nuclear power plant of Angra dos Reis with release of radionuclides to the atmosphere

    International Nuclear Information System (INIS)

    Aguiar, Andre Silva de

    2015-01-01

    This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of 131 I in the atmosphere, so that, through concentrating and inhaling dose of the plume, were possible to verify if the results are in accordance with the indicated data by the Plan of Emergency of the CNAAA regarding the Impact Zone and Control. This exercise was performed with the aid of an atmospheric model and a dispersion where to atmospheric modeling we used the data coupling WRF / CALMET and of dispersion, CALPUFF. The suggested accident consists of a Station Blackout at Nuclear Power of Angra (Unit 1), where through the total core involvement, will release 100% of the 131 I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

  1. CARACTERIZAÇÃO GEOMORFOLÓGICA DAS ÁREAS LIVRES DE GELO EM RESPOSTA DA TENDÊNCIA DE RETRAÇÃO DA GELEIRA POLAR CLUB, PENÍNSULA POTTER, ILHA REI GEORGE, ANTÁRTICA

    Directory of Open Access Journals (Sweden)

    Betânia Bonada

    2018-01-01

    Full Text Available Este trabalho objetiva investigar a dinâmica geomorfológica glacial das áreas livres de gelo na Península Potter, Ilha Rei George, Antártica, em resposta à recente retração da geleira Polar Club. O mapeamento geomorfológico e a interpretação da evolução dos sistemas lacustres entre 2006 e 2011 das áreas livres de gelo na Península Potter foi realizado através da interpretação visual em uma imagem Quickbird (RGB432, em imagens COSMO-SkyMed polarizações VV e HH em modo spotlight processadas com filtros espaciais e perfis topográficos. Também foram considerados os aspectos morfométricos da península, interpretados através da geração de mapas de hipsometria, declividade, curvas de nível e sombreamento. A variação frontal da geleira Polar Club entre os anos de 1981 a 2015 foi obtida pela análise temporal de imagens Landsat. O mapeamento geomorfológico da Península Potter evidenciou os processos geomorfológicos proglaciais e o padrão de disposição espacial das feições lineares marginais ao gelo, como cordões morâinicos e feições glaciofluviais (relacionadas ao aporte da fusão sazonal da neve e do gelo, bem como terraços marinhos, ravinas e afloramentos rochosos. O modelo de evolução da variação frontal da geleira Polar Club indica que condição de último avanço glacial registrado pela geomorfologia proglacial pode estar relacionado à Pequena Idade do Gelo e que houve um contínuo processo de retração desde então. Entre 1981-2015 evidenciou-se a redução de área de 2,95km² para a geleira Polar Club (perda de área total de 9,4%. Este processo pode estar relacionado com a tendência de aumento das temperaturas médias do ar, a tendência de aumento de dias com precipitação líquida no verão e o número de dias em que a temperatura média ultrapassou os 0°C na região nas últimas décadas. O recuo da geleira Polar Club é pouco expressivo quando comparado a outras geleiras da Ilha Rei George

  2. De jure sacro: a inquisição nas vilas d'El Rei De jure sacro: the inquisition in the villages of the king

    Directory of Open Access Journals (Sweden)

    Maria Leônia Chaves de Resende

    2011-06-01

    Full Text Available Esse artigo tem por objetivo divulgar as denúncias registradas nos Cadernos do Promotor relativos a Minas Gerais, pertencentes ao fundo da Inquisição de Lisboa, depositados no Arquivo Nacional da Torre de Tombo/Portugal, com ênfase nos estudos de caso relativos a São João del-Rei e TiradentesThe purpose of this article is to make known the accusations registered in the Lisbon Inquisition's Cadernos do Promotor (Prosecutor'S Notebooks and the prosecuted cases pertaining to Minas Gerais, especially the villages of São João del-Rei and Tiradentes. These sources are deposited in Portugal's Arquivo Nacional da Torre de Tombo/Lisboa

  3. GEOMORFOLOGIA E SEDIMENTOLOGIA GLACIAL APLICADAS NA RECONSTRUÇÃO DA EVOLUÇÃO DO AMBIENTE DE DEGLACIAÇÃO DA GELEIRA WANDA, ILHA REI GEORGE, ANTÁRTICA

    Directory of Open Access Journals (Sweden)

    Kátia Kellem Rosa

    2010-09-01

    Full Text Available Este artigo apresenta resultados das atividades de campo realizadas durante o OPERANTAR XXVI, no verão de 2007/2008, ao longo da área de deglaciação da geleira Wanda, ilha Rei George, Antártica. A geleira tem apresentado retração glacial nas últimas décadas, resultando num ambiente sedimentar, com a exposição de várias geoformas e depósitos. Esses registros geomorfológicos são úteis para a reconstrução da evolução deste ambiente de deglaciação. Os dados foram obtidos através da análise em laboratório dos sedimentos coletados em campo e posterior fotointerpretação de fotos aéreas (2003 na escala de 1:50.000, fornecidas pelo SHOA/SAF (Servicio Hidrográfico y Oceanográfico de la Armada de Chile/ Servicio Aéreo Fotogramétrico, juntamente com a análise de imagens de satélites SPOT de diferentes anos. Os resultados mostram distintas fases de deglaciação para a geleira Wanda com uma aceleração de sua retração e perda de espessura nas últimas décadas. Registros sedimentares também indicam que a geleira possui regime termal basal úmido.

  4. Measurements of the neutron energy spectra in the core of IPEN/MB-01 reactor; Medida do espectro de energia dos neutrons no nucleo do reator IPEN/MB-01

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Fernando Prat Goncalves

    2006-07-01

    This work presents the neutron spectrum measurements in the Reactor IPEN/MB-01 using very thin activation detectors in the metallic form, in reactor core, in moderator region. An articulated device allows that the foils are inserted in the central position of reactor core, ensuring that all the foils are irradiated in the same position. The activation detectors of different materials such Au{sup 197}, Mg{sup 24}, Ti{sup 4}'8, In{sup 115}, Sc{sup 45} and others, were selected to cover a large range of neutron spectrum. After the irradiation, the activation detectors were submitted to a spectrometry gamma by using a system of counting with high purity Germanium, to obtain the saturation activity per target nuclide. The saturation activity is one of the main data of input of unfolding code SANDBP, that through an iterative adjustment, modify the spectrum that better agree with the dataset of code input, composition mainly for measure reaction rate per target nuclide and a initial input spectrum, calculated for Hammer-Technion code, supplying a solution spectrum. (author)

  5. Measurements of the neutron energy spectra in the core of IPEN/MB-01 reactor; Medida do espectro de energia dos neutrons no nucleo do reator IPEN/MB-01

    Energy Technology Data Exchange (ETDEWEB)

    Martins, Fernando Prat Goncalves

    2006-07-01

    This work presents the neutron spectrum measurements in the Reactor IPEN/MB-01 using very thin activation detectors in the metallic form, in reactor core, in moderator region. An articulated device allows that the foils are inserted in the central position of reactor core, ensuring that all the foils are irradiated in the same position. The activation detectors of different materials such Au{sup 197}, Mg{sup 24}, Ti{sup 4}'8, In{sup 115}, Sc{sup 45} and others, were selected to cover a large range of neutron spectrum. After the irradiation, the activation detectors were submitted to a spectrometry gamma by using a system of counting with high purity Germanium, to obtain the saturation activity per target nuclide. The saturation activity is one of the main data of input of unfolding code SANDBP, that through an iterative adjustment, modify the spectrum that better agree with the dataset of code input, composition mainly for measure reaction rate per target nuclide and a initial input spectrum, calculated for Hammer-Technion code, supplying a solution spectrum. (author)

  6. To report the obtained results in the simulation with the FCS-11 and Presto codes of the two first operation cycles of the Laguna Verde Unit 1 reactor; Reportar los resultados obtenidos en la simulacion con los codigos FCS-11 y PRESTO de los dos primeros ciclos de operacion del reactor Laguna Verde Unidad 1

    Energy Technology Data Exchange (ETDEWEB)

    Montes T, J.L.; Moran L, J.M.; Cortes C, C.C

    1990-08-15

    The objective of this work is to establish a preliminary methodology to carry out analysis of recharges for the reactor of the Laguna Verde U-1, by means of the evaluation of the state of the reactor core in its first two operation cycles using the FCS2 and Presto-B codes. (Author)

  7. 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

  8. Simplified methodology for control cell constant calculations of the reactor cores for the space kinetics; Metodologia simplificada para calculos das constantes das celulas de controles dos nucleos de reatores para a cinetica espacial

    Energy Technology Data Exchange (ETDEWEB)

    Santos, Rubens Souza dos [Instituto de Engenharia Nuclear (IEN), Rio de Janeiro, RJ (Brazil); Martinez, Aquilino Senra; Alvim, Antonio Carlos Marques [Universidade Federal, Rio de Janeiro, RJ (Brazil). Coordenacao dos Programas de Pos-graduacao de Engenharia. Programa de Engenharia Nuclear

    2002-07-01

    In this work is presented a methodology which focuses the distribution of neutron absorber rods in nuclear reactor power plants, for utilizing in space kinetic calculations, principally in the cluster ejection transients of control rods. A numerical model for macroscopic constant calculations based on the knowledge of the neutron flux without the control rods is proposed, as alternative to the analytical models, based on the hypothesis of the null current on the cell super boundaries. The proposed model in this work has itself showed adequate to deal with problems with strong space dependence, once that the model showed consistence in the global average built in the analytical model. (author)

  9. Algas marinhas bentônicas da Reserva Biológica Estadual da Praia do Sul, Ilha Grande, Angra dos Reis, Rio de Janeiro, Brasil Benthic marine algae of the State Biological Reserve of Praia do Sul, Ilha Grande, Angra dos Reis, Rio de Janeiro, Brazil

    Directory of Open Access Journals (Sweden)

    Lísia Mônica de Souza Gestinari

    1998-04-01

    Full Text Available Na Reserva foram encontradas 121 espécies, sendo 27 de Chlorophyceae, 21 de Phaeophyceae e 73 de Rhodophyceae. Dentre estas espécies, 38 são novas referências para a ilha, sendo que Cladophora catenata (L. Kütz. é pela primeira vez citada para o litoral do Rio de Janeiro. Não foram encontradas espécies endêmicas e nem flora específica de região insular. A comparação da flora da Reserva com a de regiões vizinhas indica alta percentagem de espécies em comum entre elas.A survey in the Reserve showed 27 species of Chlorophyceae, 21 of Phaeophyceae and 73 of Rhodophyceae. Among the recorded species, 38 are new references to the Island and Cladophora catenata (L. Kütz. is for the first time quoted to the Rio de Janeiro coast. Neither endemic species nor specific flora from insular area were found in the Reserve. A comparison between the flora of the Reserve and those of neighboring areas, showed a high percentage of similarity.

  10. Study of {sup 137}Cs e {sup 60}Co sorption in sediments from Saco de Piraquara de Fora, Angra dos Reis and its application for environmental monitoring; Estudo da sorcao de {sup 137}Cs e {sup 60}Co em sedimentos do Saco de Piraquara de Fora em Angra dos Reis e sua aplicacao para o monitoramento ambiental

    Energy Technology Data Exchange (ETDEWEB)

    Ferreira, Ingryd Marques

    2016-08-01

    Both the suspended solid particles and the bed sediments sorb radionuclides, released in water systems. Sorption is usually represented mathematically by the distribution coefficient that is based in equilibrium between phases. Here the adsorption/desorption kinetics of {sup 60}Co and {sup 137}Cs in sea water were simulated by batch equilibrium experiments with sediments in two points (PT - 01, PT - 02) from Saco de Piraquara de Fora inlet (SPF). For both radionuclides, partition coefficient values (Kd) for the sampling point PT - 02 (509 and 385 L/kg for {sup 60}Co and {sup 137}Cs, respectively) were higher than the values determined for PT - 01 one (426 and 182 L/kg for {sup 137}Cs and {sup 60}Co, respectively). The higher values of Kd of PT-02 reflects the higher CEC (71,4 cmolc.dm{sup 3}) and content of mud < 63 μm (87%) when compared to PT-01 (CEC of 39,5 cmol{sub c}.dm{sup 3}) and mud (55%). In comparison with the values reported in the literature, the found Kd values are low, which may be related to the predominance of kaolinite, which is a clay of low sorption capacity. The Kd values with an increase in temperature of 23 deg C to 27 deg C were similar ({sup 60}Co in PT-02 and {sup 137}Cs in both sediment) or 27 ° C values were higher ({sup 60}Co the PT-01). With increasing temperature to 31 °C Kd values for the two radionuclides showed a decrease. However, increasing temperature increases the desorption of the two radionuclides for both sediments The sorption process is spontaneous and favorable for both sediments and the model of sorption can be fitted by both Freundlich and Langmuir sorption isotherms. The maximum amount of {sup 60}Co that can be sorbed on sediments were 1,64 10{sup -5} moles/g (4,12 10{sup 10} Bq/g) and 2,79 10{sup -5} moles/g (7,03 10{sup 10} Bq/g) to PT-01 and PT-02, respectively, and of {sup 137}Cs 1,99 10{sup -6} moles/g (9,70 10{sup 8} Bq/g) and 6,60 10{sup -6} mol/g (2,87 10{sup 9} Bq/g ) to PT-01 and PT-02. Two areas in SPF can potentially accumulate {sup 137}Cs: sediments located near the effluent discharge and the area located north of this site. An area in the interface of SPF and the bay of Ribeira would potentially the best accumulated of {sup 60}Co. (author)

  11. Assessment of impact of a severe accident at nuclear power plant of Angra dos Reis with release of radionuclides to the atmosphere; Avaliacao do impacto de um acidente severo na usina de Angra dos Reis com liberacao de radionuclideos para a atmosfera

    Energy Technology Data Exchange (ETDEWEB)

    Aguiar, Andre Silva de

    2015-07-01

    This study had as purpose the assess the impact of a severe accident, and also analyze the dispersion of {sup 131}I in the atmosphere, so that, through concentrating and inhaling dose of the plume, were possible to verify if the results are in accordance with the indicated data by the Plan of Emergency of the CNAAA regarding the Impact Zone and Control. This exercise was performed with the aid of an atmospheric model and a dispersion where to atmospheric modeling we used the data coupling WRF / CALMET and of dispersion, CALPUFF. The suggested accident consists of a Station Blackout at Nuclear Power of Angra (Unit 1), where through the total core involvement, will release 100% of the {sup 131}I to the atmosphere. The value of the total activity in the nucleus to this radionuclide is 7.44 x 1017 Bq, that is relative on the sixth day of burning. This activity will be released through the chimney at a rate in Bq/s in the scenario of 12, 24, 48 and 72 hours of release. Applying the model in the proposed scenario, it is verified that the plume has concentrations of the order of 1020 Bq/m³ and dose of about 108 Sv whose value is beyond of the presented by Eletronuclear in your current emergency plan. (author)

  12. Influência dos Incentivos à Qualificação dos Servidores Técnico-administrativos da Universidade Federal de São João Del Rei

    Directory of Open Access Journals (Sweden)

    Ferreira, Luciana Gonçalves

    2015-06-01

    Full Text Available Objective was to investigate the influence that incentives qualification established by Law11.091/2005 has on the motivation of servers to qualify. Using quantitative methodologies, which used questionnaire from the evaluation model degree of stimulus applied to the Likert scale to 141servers a University. Results indicate relations between the factors stimulus from the identification of five distinct constructs. The study demonstrated that the construct “career” was the predominant motivation of servers TAs to carry the qualification. According to statistical analysis, the stimulus factors: knowledge to improve the work, the current scenario of the labor market and the percentage of financial incentives for qualifying formed the factors of most motivation for the students to follow the qualification. However, the findings suggest that the financial incentive is just to be a major stimulus factor for the qualification is associated with other stimuli.

  13. Thermal and fast neutron distribution determination in the IPR-R1 reactor core; Levantamento das distribuicoes dos fluxos de neutrons termicos e rapidos no nucleo do reator IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

    Guimaraes, R R.R.

    1985-06-01

    The work is aimed at obtaining a physical method for neutron flux distribution determination within the reactor core, in order to analyze the project of power increase in the TRIGA IPR-R1 reactor at the Nuclebras Centro de Desenvolvimento da Tecnologia Nuclear (CDTN), located in Belo Horizonte, Minas Gerais, Brazil. The experimental process utilizes the neutron activation technique in impurities of stainless steel welding rods 700 mm long, set in acrylic supports. These rods provide simultaneous information on the thermal and fast neutron fluxes through capture and threshold reactions. The process of detection and counting of activation products utilizes a high resolution Ge (Li) detector and a mechanical scanning device, designed and manufactured at CDTN for burn-up measurements of irradiated fuel elements. Besides its simplicity, the method presents the advantage of substituting high purity imported materials by one easily obtained that also furnishes simultaneous information on the thermal and fast neutron fluxes. Furthermore, values for the absolute thermal neutron flux a long the whole core height are obtained. The procedure consists of the assessment of the thermal neutron flux in a fixed point by means of a conventional detector, and then establishing the correspondence of this measurement with the response of the stainless steel rods. (author). 30 refs, 39 figs, 9 tabs.

  14. Definition of the electric requirements for the equipment associated to the limiter reactor on a 550 kV line occurring from manoeuvres under short circuits; Definicao dos requisitos eletricos dos equipamentos associados ao reator limitador em 550 kV, em decorrencia de manobras sob curtos-circuitos

    Energy Technology Data Exchange (ETDEWEB)

    Machado Junior, Camilo; Furuoka, Nita; Rose, Eber Havila [ELETRONORTE, Brasilia, DF (Brazil)]. E-mail: eber@eln.gov.br; Violin, Airton; Martinez, Manuel Luis Barreira [Escola Federal de Engenharia de Itajuba (EFEI), MG (Brazil). Inst. de Engenharia Eletrica. Lab. de Alta Tensao; Saraiva, Carlos Alberto Moura [Consorcio THEMAG-ENGEVIX, Sao Paulo, SP (Brazil)

    2001-07-01

    This paper presents the ascertaining based on the TRT study results performed to the definition of the new circuit breakers characteristics for the second stage of the Tucurui hydroelectric power plant, placed at the northern Brazil and with final configuration of two power houses and two air isolated substations, amounting 9 GVA. To reduce the short-circuit level to satisfactory values series reactors were used among the 550 kV substations. The result of the studies associated to the circuit breaker specifications are presented.

  15. Biodosimetric analysis of medium pressure UV disinfection reactor treating unfiltered surface water

    International Nuclear Information System (INIS)

    Leinan, B.E.; Craik, S.A.; Smith, D.W.; Belosevic, M.

    2002-01-01

    Many small and medium-sized communities use chlorination of surface water as their sole treatment of potable water. Ultraviolet (UV) disinfection may offer these communities a cost effective treatment option for protection against pathogens not readily inactivated by chlorine. The effectiveness of UV reactors for microorganism reduction, however, is sensitive to UV dose delivery, which is in turn influenced by water quality characteristics. The effectiveness of a Calgon Carbon Inc. Sentinel medium-pressure UV reactor for microorganism reduction was determined using biodosimetry with two non-pathogenic indicator organisms - MS2 phage and Bacillus subtilis. Testing was conducted using low turbidity (<0.5 NTU) lake water characterized by relatively high absorbance in the UV range (UVT of approx. 87 to 88% at 254 nm). The efficiency of UV dose delivery in the reactor was determined for various operating conditions by calculating the normalized reductive equivalent irradiance (REI). With a single lamp in operation, the normalized REI measured with B. subtilis increased significantly when the flow rate through the reactor was increased from 380 L/min to 1140 L/min. This increase in reactor efficiency was believed to be due to improved reactor hydrodynamics and axial mixing that accompanied the higher flow rates. In contrast, treatment efficiency based on biodosimetry with MS2 phage was found to decrease with increasing flow rate when a single lamp was in operation. In general, treatment efficiency was greater when more than one adjacent lamp was in operation, suggesting that the influence of flow short-circuiting with single lamp operation. Differences between the outcomes observed with the two indicator microorganisms were not resolved, however, it was concluded that reactor efficiency was sensitive to both water flow rate and the number of adjacent lamps that were in operation. (author)

  16. O Rei Maia Kukulcán e seus discursos de propaganda política em Chichén Itzá

    Directory of Open Access Journals (Sweden)

    Alexandre Guida Navarro

    2013-08-01

    Full Text Available Chichén Itzá foi um populoso centro urbano maia responsável por tributar centenas de cidades, organizar um exército eficaz para os empreendimentos guerreiros e realizar comércio de longa distância com outras cidades maias e de outras etnias. Durante seu auge, no século IX, a cidade foi governada por um rei chamado Kukulcán, que foi responsável pela maioria das construções arquitetônicas da cidade. Tal governo foi marcado por uma eficiente propaganda política que foi planejada segundo um processo cognitivo de representação imagética do governante, cuja principal manifestação deu-se em forma de uma serpente emplumada. Estas imagens serviram de propaganda política para perpetuar a soberania deste rei, além de ser um registro imagético de sua importância na memória coletiva desta cidade maia.

  17. Structural Properties and UV-Visible Absorption Spectroscopy of Retinal-pyridyl-CN Re(I) Carbonyl Bipyridine Complex: A Theoretical Study.

    Science.gov (United States)

    Eng, Julien; Daniel, Chantal

    2015-10-29

    The structural, electronic, and optical properties of the all-trans and five cis conformers of [Re(CO)3(bpy)(ret-pyr-CN)](+) (bpy = 2,2'-bipyridine; ret-pyr-CN = pyridyl-CN-3,7-dimethyl-9-(2,6,6-trimethylcyclohex-2-n)-none-(2,4,6,8-tetraen) were studied in solvent by means of density functional theory (DFT) and time-dependent DFT. The isolated retinal-like chromophore ret-pyr-CN was investigated as well for comparison. By coordination to the complex the two lowest intraligand (IL) states localized on the retinal group are slightly red-shifted from 627 to 690 nm and from 415 to 450 nm, respectively. Several isomerization pathways are open upon irradiation of the Re(I) complex by visible light (400-450 nm), especially to two cis conformers corresponding to the isomerization of the two double bonds of the retinal-like ligand close to the pyridyl group linked to the Re(I) fragment. The metal-to-ligand charge transfer states localized either on the retinal group or on the bpy ligand should play a minor role in the isomerization process itself but could improve its efficiency via ultra-fast intersystem crossing.

  18. 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...

  19. Reis Siberisse / Art Leete

    Index Scriptorium Estoniae

    Leete, Art, 1969-

    1995-01-01

    1994. aastal viibisid Tjumeni oblastis Jamali-Neenetsi ringkonnas välitöödel Eesti Keele Instituudi teadustöötaja Triinu Ojamaa ja Eesti Rahva Muuseumi arhivaar Art Leete. Läbitud asulate ja kohatud asukate kirjeldused

  20. O ecologismo dos pobres

    Directory of Open Access Journals (Sweden)

    Juan Martinez ALIER

    1997-12-01

    Full Text Available O ecologísmo tem colocado em cheque as leis capitalistas de mercado, principalmente na sua fase globalizada, devido à apropriação e exploração inconsequente dos recursos naturais. Ao mesmo tempo tem apontado que o meio ambiente não se reduz ao tratamento somente cientifico da natureza. O presente artigo ressalta aspectos importantes do ecologísmo como a participação das mulheres, o marxismo, o neo-narodnismo, etc. e é rico em exemplos de problemas ambientais decorrentes das relações de produção. O ecologísmo dos pobres é apontado como uma perspectiva necessária às lutas ambientais no Terceiro Mundo.

  1. O Jardim dos Sonhos

    Directory of Open Access Journals (Sweden)

    RAUL CÂNOVAS

    2010-06-01

    Full Text Available O jardim dos sonhos sempre foi um ideal dos homens. No Antigo Egito, já se falava em um jardim sempre verde para onde as pessoas de bom coração iam após a morte. E na mitologia grega, um lindo jardim era palco das festas bucólicas dos deuses. As grandes religiões também citavam jardins como paraísos, como o Jardim do Éden. Neste artigo, Raul Cânovas nos leva a refletir sobre o sentido de um “jardim perfeito”, sem tratar a perfeição como apenas plástica e estruturada com exatidão, mas referindo-se a um jardim que nos inspire e emocione, emancipado de modismos passageiros. O paisagista também nos alerta sobre as condições mutáveis de um jardim, que nunca está finalizado. O paisagismo não é apenas técnica; é também sensibilidade, utilidade, sustentabilidade e equilíbrio das forças da natureza.

  2. Design, construction and implementation of two redundant circuits of the actuation logic of the protection system of the new control console of TRIGA Mark III reactor of ININ; Diseno, construccion e implementacion de dos circuitos redundantes de la logica de actuacion del sistema de proteccion de la nueva consola de control del reactor Triga Mark III del ININ

    Energy Technology Data Exchange (ETDEWEB)

    Celestino M, E.

    2016-07-01

    The Instituto Nacional de Investigaciones Nucleares (ININ) in Mexico has a nuclear reactor type TRIGA Mark III, which was put into operation in 1968. The reactor is used for staff training, radioisotope production, and for research projects of different areas. Over time and due to advances constantly has the electronics industry, maintenance of electronic systems is complicated because basically sometimes components that are no longer manufactured or no longer exist in the market, making it necessary to create projects required modernization. This is the case of the TRIGA reactor of ININ, so the Department of Automation and Instrumentation ININ is undertaking a new project to update the reactor control console. Systems that make up a nuclear reactor protection system (Ps) is relevant, since it is responsible for generating the necessary steps to shut down the reactor to an event of uncertainty which could affect the operators or the installation own actions. As part of the renovation project, this study design is presented to update the Logic of Action (La) of the Ps, whose final design must meet the requirements or specifications set by users and or regulations applicable to nuclear research reactors. One of the requirements established for the proposed new design La, is that it must be implemented with components and devices manufactured with latest technologies, and readily available on the market. The design which is operating currently uses TTL logic whose components are no longer available in the market, so for the new design you decide to use programmable circuits, and specifically, the CPLDs called (by the acronym Complex Programmable Logic Device). These CPLDs are electronic devices that solve complex logic equations and meeting the requirements of functionality and modernity for the new design of the La. In this work the criteria used for the selection of the CPLDs considering the availability and ease of software and hardware to use, and the design and

  3. A disputa entre o Papa Bonifácio VIII e o Rei Filipe IV no final do século XIII

    Directory of Open Access Journals (Sweden)

    Strefling, Sérgio Ricardo

    2007-01-01

    Full Text Available A questão das relações entre Igreja e Estado provocou debates prolongados e acesos, principalmente durante a idade média, no momento em que a igreja, dotada de um domínio próprio temporal, encontrava-se em convívio com o Sacro Império Romano que abraçava os mesmos súditos e apoiava-se sobre bases jurídicas derivadas do Cristianismo. Sob tal situação ainda era possível manter uma diferenciação entre estado e Igreja? No presente estudo, apresentaremos a polêmica causada pela teoria do Papa Bonifácio VIII no conflito com o Rei Filipe, o Belo. Daí surgem três documentos importantes, entre eles, a Bula Unam Sanctam

  4. Use of new technologies in the documentation of the origin and urban development of São João Del Rei Minas Gerais, Brasil.

    Directory of Open Access Journals (Sweden)

    Altino Barbosa Caldeira

    2015-01-01

    Full Text Available The city of São Joao del Rei, situated in the state of Minas Gerais, Brazil, has a currently economic, social and tourism performance that stands outamong the other cities of the state. This article seeks to clarify these reasons, taking into account the region and the occupied territory, theirsubsequent development and the changes occurring in the landscape from this occupation. It also aims to demonstrate how to use the resources ofnew technologies to document the cultural heritage left by past  generations and how spread it to new generations. For this, we will make use of the physical and human geography, as well as its history, to analyze facts, activities and the reasons that led to its current appearence. It will be considered the natural environment, human interventions and cultural expressions of its people regarding aspects of intangible heritage to analyzes the spatial dimension of the local culture, using the concepts of cultural geography.

  5. Folia de Reis não é folia de rádio Off the radio: preserving popular culture in São Paulo

    Directory of Open Access Journals (Sweden)

    Mônica de Carvalho

    2010-12-01

    Full Text Available O objetivo deste artigo é analisar o sentido da preservação da Folia de Reis no distrito da Freguesia do Ó, Zona Norte da cidade de São Paulo, tomando como contraponto o evento Revelando São Paulo, que, organizado pelo governo do estado, também tem por objetivo a preservação da cultura popular tradicional paulista. Tomando como referência teórico-metodológica o debate iniciado nos anos de 1940 entre Florestan Fernandes e os folcloristas, a intenção é demonstrar que naquela figuração o que está em disputa é o sentido mesmo de preservação e, mais do que isso, o seu próprio objeto.This article explores the meaning of attempts to preserve the Folia de Reis (Revelry of the Wise Men in the district of Freguesia do Ó, in the north of São Paulo city. As a counterpoint, it analyzes the event Revelando São Paulo (Revealing São Paulo, organized by the State Government, which also looks to preserve São Paulo's traditional popular culture. Using the debate between Florestan Fernandes and the folklorists, initiated in the 1940s, as a theoretical and methodological starting point, the article aims to demonstrate that what is being disputed in the former's figuration is not only the meaning of preservation but, more importantly, how the preservation itself is achieved.

  6. O ecologismo dos pobres

    OpenAIRE

    ALIER, Juan Martinez

    1997-01-01

    O ecologísmo tem colocado em cheque as leis capitalistas de mercado, principalmente na sua fase globalizada, devido à apropriação e exploração inconsequente dos recursos naturais. Ao mesmo tempo tem apontado que o meio ambiente não se reduz ao tratamento somente cientifico da natureza. O presente artigo ressalta aspectos importantes do ecologísmo como a participação das mulheres, o marxismo, o neo-narodnismo, etc. e é rico em exemplos de problemas ambientais decorrentes das relações de produç...

  7. Dos novelas colombianas olvidadas

    Directory of Open Access Journals (Sweden)

    Eduardo García Piedrahita

    1980-06-01

    Full Text Available Estas dos novelas olvidadas llevan por títulos Pax de don Lorenzo Marroquín (pr. edi. 1907, y Diana Cazadora de don Clímaco Soto Borda(pr. edi. 1917, ambos bogotanos aunque de disímiles estirpes literarias; y como tales en sus obras fluyen física y verbalmente, el ambiente de su ciudad natal; espíritu hecho de zumbona crítica, individualismo cáustico y solapada parodia de usos y costumbres. Y sobre tales bases sentimentales y estilísticas debe considerárselas.

  8. Geoeconomia dos emergentes

    OpenAIRE

    Pinto, Pedro

    2010-01-01

    Mercados decisivos para a recuperação da economia global, até porque muito mais imunes às consequências da crise fi nanceira, os países emergentes apresentam taxas de crescimento mais altas face aos principais países desenvolvidos e têm desempenhado um papel fundamental na consolidação dos volumes de comércio internacional e de crescimento da economia mundial ao longo desta última década.

  9. Dos cupas complutenses

    Directory of Open Access Journals (Sweden)

    Stylow, Armin U.

    2006-12-01

    Full Text Available Publication of two cupae from the ancient territory of Complutum. One was found in excavations in Alcalá de Henares (Madrid and is unpublished; of the other one, which came to light in the church of Alovera (Guadalajara, a new reading is given.Se publican dos cupas del antiguo territorio de Complutum, una, inédita, encontrada en excavación en Alcalá de Henares (Madrid, y la segunda, procedente de la iglesia de Alovera (Guadalajara, con una nueva lectura.

  10. CAPITAL HUMANO: DOS ENFOQUES

    Directory of Open Access Journals (Sweden)

    María Isabel Pueyo Roy

    2005-01-01

    Full Text Available El artículo presenta un resumen de la teoría existente sobre capital humano, considerando dos proposiciones que se complementan: la Teoría Neoclásica -educación como formación laboral o señalización al mercado de trabajo- y la Teoría Institucional o de mercados internos de trabajo. Se presenta el desarrollo de ambas teorías, los problemas que presentan y la complementariedad entre las mismas.

  11. 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

  12. 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.

  13. 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.

  14. 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

  15. dos estudios de caso

    Directory of Open Access Journals (Sweden)

    Daniel Kersffeld

    2013-01-01

    Full Text Available La UNASUR se ha destacado desde sus inicios en la compleja labor de mediación y resolución de conflictos internacionales. Para ello, esta entidad multilateral ha apelado a distintas fórmulas políticas tendientes al encausamiento de problemáticas y conflictos apartados del camino de la institucionalidad y de los medios tradicionales de resolución. Con todo, y pese a la búsqueda de caminos alternativos, han sido las cumbres presidenciales la principal herramienta destinada a encontrar soluciones innovadoras y respetuosas del orden democrático y constitucional de los países sudamericanos. En este artículo se analiza de manera específica la actuación de la unasur en dos casos de profunda gravedad institucional: el intento de golpe de Estado ocurrido en Ecuador el 30 de septiembre de 2010 y el derrocamiento del ex presidente Fernando Lugo en Paraguay en junio de 2012. Luego de analizar estos dos casos extremos, y las implicancias políticas generadas, se avanza en una visión comprensiva acerca del éxito o el fracaso del papel político de la unasur como instancia de resolución de conflictos a nivel internacional.

  16. 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

  17. 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

  18. 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.)

  19. 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.)

  20. Dos estudios de casos

    Directory of Open Access Journals (Sweden)

    Hernán Guillermo Salazar Morales

    1989-04-01

    Full Text Available RESUMEN A continuación se presenta dos casos de estudio en donde se puede apreciar a la forma  como se establecen  las relaciones en una organización y lo que una DECISION  puede llegar a incidir en el desarrollo de las operaciones de una empresa. Decisiones basadas en la intuición, o en corazonadas, frecuentemente conducen en dirección equivocada, ocasionando pérdidas en tiempo, personal y dinero. El proceso de toma de decisiones deben ser TAREAS ESTRUCTURADAS que se sustenten con hechos. Su ejecución debe hacerse secuencialmente y cumplir con cada uno de sus pasos. El diseño de los  casos está orientado para que  sirvan como material de aplicación en la asignatura de  taller de planeación.

  1. A sociedade dos vivos

    Directory of Open Access Journals (Sweden)

    Leis Héctor Ricardo

    2003-01-01

    Full Text Available A pergunta: qual é o significado da experiência da morte na sociedade contemporânea? A hipótese: que existe uma faceta sombria e degradante da condição humana, associada à privatização institucional ou "pacificação" da morte que estamos assistindo em nossa época. Muitos teóricos sociais contemporâneos apostam em estratégias como a reflexividade para reconstruir a fragmentação do ser humano, porém essa reconstrução mal poderia vir sem procurar apoio em aspectos chaves da condição humana. Apontar alguns dos déficits da teoria social contemporânea e assinalar alguns caminhos para superar impasses da sociedade contemporânea resume a tentativa deste trabalho.

  2. 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

  3. 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

  4. O rei do pop e as nuances da pós-modernidade trágica

    Directory of Open Access Journals (Sweden)

    Nayana M. Moraes

    2010-12-01

    Full Text Available Este artigo mostra a relação das celebridades com os aspectos trágicos de suas vidas e o envolvimento dos fãs a partir da catarse. Todos estes termos imbricados dialogarão com um dos gêneros literários mais antigos: a tragédia grega. Esta permeará um entendimento acerca da forma com que nós, espectadores, analisamos alguns famosos, bem como sua influência na indústria do entretenimento. Neste contexto, alguns deles não conseguem adquirir um equilíbrio entre a fama e sua vida pessoal, que cai diante de sua hybris (desequilíbrio interno. E um destes artistas, considerado o mito da música e do entretenimento, compreenderá esta discussão: Michael Jackson. O filósofo grego Aristóteles discutiu e revigorou a importância e verossimilhança desta literatura no ser humano. Veremos, entretanto, que mesmo com estes conflitos, o mito permanece.

  5. 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.)

  6. 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.)

  7. 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)

  8. 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

  9. Essential learning tools for continuing medical education for physicians, geneticists, nurses, allied health professionals, mental health professionals, business administration professionals, and reproductive endocrinology and infertility (REI) fellows: the Midwest Reproductive Symposium International.

    Science.gov (United States)

    Collins, Gretchen G; Jeelani, Roohi; Beltsos, Angeline; Kearns, William G

    2018-04-01

    Essential learning tools for continuing medical education are a challenge in today's rapidly evolving field of reproductive medicine. The Midwest Reproductive Symposium International (MRSi) is a yearly conference held in Chicago, IL. The conference is targeted toward physicians, geneticists, nurses, allied health professionals, mental health professionals, business administration professionals, and reproductive endocrinology and infertility (REI) fellows engaged in the practice of reproductive medicine. In addition to the scientific conference agenda, there are specific sessions for nurses, mental health professionals, and REI fellows. Unique to the MRSi conference, there is also a separate "Business Minds" session to provide education on business acumen as it is an important element to running a department, division, or private clinic.

  10. 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

  11. Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

    Directory of Open Access Journals (Sweden)

    Nelson A. de Araújo Filho

    1981-12-01

    Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.

  12. Linguagem fílmica: uma metáfora de comunicação para a análise dos discursos nas organizações

    Directory of Open Access Journals (Sweden)

    Alessandra Demite Gonçalves de Freitas

    2015-03-01

    Full Text Available O objetivo da pesquisa aqui relatada foi investigar a linguagem fílmica como metáfora de comunicação para a análise dos discursos nas organizações. Trata-se de uma pesquisa qualitativa, com uso da estratégia de análise fílmica. Os dados foram coletados por meio da observação indireta e não participante, registrados em protocolo de observação. Foi utilizada a estratégia de análise de discurso do personagem do Rei George VI no filme comercial/artístico O discurso do rei; a análise documental do filme documentário The king speaks - "The true story behind the film" e a análise de conteúdo da obra literária biográfica O discurso do rei - "Como um homem salvou a monarquia britânica". Nos resultados, reforçou-se que o uso da linguagem fílmica, nesta pesquisa, contribui para o entendimento do fenômeno da comunicação nas organizações. Seu uso cria a oportunidade de simulação a partir de cenas que podem ser comparadas com dados inseridos no contexto organizacional, como metáforas, desde que haja cuidado com a dimensão afetiva envolvida no processo de significação fílmica. Sua utilização torna-se conveniente, desde que não se permita a escolha do filme pelo filme e que haja um alinhamento entre o filme escolhido e o construto que se pretende investigar.

  13. 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.)

  14. 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

  15. 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

  16. Leishmaniose tegumentar americana na Ilha Grande. Rio de Janeiro: V. Observações sobre a biologia dos transmissores em condiçoes naturais

    Directory of Open Access Journals (Sweden)

    Nelson A. de Araújo Filho

    1981-12-01

    Full Text Available Durante um surto de Leishmaniose Tegumentar Americana (LTA na Praia Vermelha, Ilha Grande, município de Angra dos Reis, Rio de Janeiro, foram coletados 4.192 exemplares de flebotomíneos em ambiente domiciliar e silvestre, com isca animal e outros abrigos naturais, durante o período de janeiro de 1976 a abril de 1977. Entre o total de 11 espécies coletadas encontraram-se 2.493 exemplares de Lutzomyia intermedia, 1.594 de Lutzomyia migonei e 105 exemplares de outras espécies. A L. intermedia apresentou densidade mais elevada no domicílio humano, enquanto a L. migonei apresentou coletas mais rendosas com iscas animais e galinheiros. O sinantropismo e a elevada densidade no ambiente domiciliar incriminam as espécies L. intermedia e L. migonei como as prováveis vetoras da LTA na Ilha Grande.During an outbreak of mucocutaneous leishmaniasis in Praia Vermelha, Ilha Grande (Great Island in the county of Angra dos Reis, State of Rio de Janeiro, 4.192 species of Phlebotomus were collected in domestic and wild environment with the use of animal baits and other natural shelters from January 1976 to April 1977. In a total of 11 species collected, 2.493 samples of Lutzomyia intermedia, 1.594 of Lutzomyia migonei and 105 samples of other species were found. The Lutzomyia intermedia presented a higher density in human dwellings, while the Lutzomyia migonei presented better results with animal baits and chicken-coops. The sinantropism and high density found in the houses incriminate the species L. intermedia and L. migonei as the probable vectors of Mucocutaneous Leishmaniasis in Ilha Grande.

  17. 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

  18. IL CONTRIBUTO DI INNOCENZO III ALLA FORMAZIONE DELLA CULTURA GIURIDICA OCCIDENTALE: IN PARTICOLARE IN RELAZIONE AL NOTO PRINCIPIO «REI PUBLICAE INTEREST NE CRIMINA REMANEANT IMPUNITA»

    Directory of Open Access Journals (Sweden)

    Cesare Edoardo Varalda

    2016-12-01

    Full Text Available Within the period so called renovatio, many principles contained in the Roman legal sources have been explained in a new and innovative way, influencing the history of juridical thought and contributing to the development of the European legal experience. In fact, the principle "Rei publice interest it crimina remaneant impunita" (mentioned in two decretals of Innocent III: i.e. the Inauditum in 1199 and i.e. the Ut famae in 1203 has an essential role in the development of the conceptual system of modern criminal law. The content of this study will be, on the one hand, the detailed study of historical iter by which this principle has been consolidated and has been embraced by canonical experience and, more generally, in the Western one; on the other hand, it will analyse both from a technical and a metagiuridico point of view the origin of such formula and on the contribution that Christian theology might have given by clarifying and specifying its meaning. Therefore, it’s clear the importance of this principle in the development of the European legal system and, broadly, in the Western legal experience.

  19. 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

  20. DOS cones along atomic chains

    Science.gov (United States)

    Kwapiński, Tomasz

    2017-03-01

    The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin-orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears.

  1. DOS cones along atomic chains

    International Nuclear Information System (INIS)

    Kwapiński, Tomasz

    2017-01-01

    The electron transport properties of a linear atomic chain are studied theoretically within the tight-binding Hamiltonian and the Green’s function method. Variations of the local density of states (DOS) along the chain are investigated. They are crucial in scanning tunnelling experiments and give important insight into the electron transport mechanism and charge distribution inside chains. It is found that depending on the chain parity the local DOS at the Fermi level can form cone-like structures (DOS cones) along the chain. The general condition for the local DOS oscillations is obtained and the linear behaviour of the local density function is confirmed analytically. DOS cones are characterized by a linear decay towards the chain which is in contrast to the propagation properties of charge density waves, end states and Friedel oscillations in one-dimensional systems. We find that DOS cones can appear due to non-resonant electron transport, the spin–orbit scattering or for chains fabricated on a substrate with localized electrons. It is also shown that for imperfect chains (e.g. with a reduced coupling strength between two neighboring sites) a diamond-like structure of the local DOS along the chain appears. (paper)

  2. Dos chalets, en Suecia

    Directory of Open Access Journals (Sweden)

    Erskine, Ralph

    1968-04-01

    Full Text Available Villa Engström, at Sorunda This house, of semi-spheric shape, has besically only one floor level, without basement. However, the guest room and the attic are a kind of second floor within the cupula. This is an experiment, with a view to the possible mass construction of this prototype. The various rooms are grouped in two blocks, one comprising the bedrooms, which are cellular type and of minimum size, and the bathrooms; the other includes the children's room, a living room which extends into the vestibule, and guest room at a higher level. Villa Ström, near Stockholm This house is practically cube shaped, with ample terraces, which are structurally independent of the central volume. A principal aim has been to obtain fine views in all directions, and also to take advantage of the ground slope. This house, of original and competent design, includes indoor gardens which add colour and life to the rooms.Villa Engström, en Sorunda Esta vivienda, que presenta una «forma» semiesferica, es fundamentalmente un edificio de una sola planta, sin sótano; sin embargo, el cuarto de huéspedes y el «ático» forman como una especie de doble planta dentro de la cúpula. Se trata de una experiencia con vistas a una posible fabricación en serie. Las diferentes habitaciones se hallan agrupadas en dos bloques: uno de ellos ocupado por los dormitorios —que son de tipo celular y de tamaño mínimo—, y los cuartos de baño; y el otro que comprende un cuarto para los niños, la sala de estar —unida con el vestíbulo—, y la habitación de los huéspedes en la parte superior. Villa Ström, cerca de Estocolmo La casa es prácticamente un cubo, con terrazas amplias e independientes estructuralmente del volumen principal. En todo caso, ha dominado la doble preocupación de conseguir magníficas vistas hacia todos los alrededores y una adaptación total a la pendiente del terreno. La vivienda se ha resuelto con maestría y originalidad, procurando zonas

  3. OS SACRAMENTAIS, SACRAMENTOS DOS POBRES

    Directory of Open Access Journals (Sweden)

    Victor Codina

    1990-01-01

    Full Text Available Basta ter tido um pouco de experiência pastoral com setores populares, concretamente na América Latina, para constatar a importância dos sacramentais na vida cristã do povo. Além das manifestações de piedade popular que se costuma estudar sob a rubrica de religiosidade popular (peregrinações, festas de padroeiro, procissões..., gostaria de destacar aqui outros elementos mais estreitamente ligados ao mundo dos sacramentos, ainda que não formem parte dos sete sacramentos tridentinos.

  4. 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.

  5. Reactor safety

    International Nuclear Information System (INIS)

    Butz, H.P.; Heuser, F.W.; May, H.

    1985-01-01

    The paper comprises an introduction into nuclear physics bases, the safety concept generally speaking, safety devices of pwr type reactors, accident analysis, external influences, probabilistic safety assessment and risk studies. It further describes operational experience, licensing procedures under the Atomic Energy Law, research in reactor safety and the nuclear fuel cycle. (DG) [de

  6. Nuclear reactor

    International Nuclear Information System (INIS)

    Mysels, K.J.; Shenoy, A.S.

    1976-01-01

    A nuclear reactor is described in which the core consists of a number of fuel regions through each of which regulated coolant flows. The coolant from neighbouring fuel regions is combined in a manner which results in an averaging of the coolant temperature at the outlet of the core. By this method the presence of hot streaks in the reactor is reduced. (UK)

  7. 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.)

  8. RA Reactor

    International Nuclear Information System (INIS)

    1989-01-01

    This chapter includes the following: General description of the RA reactor, organization of work, responsibilities of leadership and operators team, regulations concerning operation and behaviour in the reactor building, regulations for performing experiments, regulations and instructions for inserting samples into experimental channels [sr

  9. Reactor physics

    International Nuclear Information System (INIS)

    Ait Abderrahim, H.

    1998-01-01

    Progress in research on reactor physics in 1997 at the Belgian Nuclear Research Centre SCK/CEN is described. Activities in the following four domains are discussed: core physics, ex-core neutron transport, experiments in Materials Testing Reactors, international benchmarks

  10. 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.)

  11. 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.)

  12. 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.)

  13. 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

  14. 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.)

  15. 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.)

  16. Cucos, formigas, abelhas e a evolução dos instintos

    Directory of Open Access Journals (Sweden)

    César Ades

    Full Text Available Neste artigo, abordo o capítulo VII de "A Origem das Espécies" (Instinto, no qual Charles Darwin efetua uma aplicação da teoria da evolução por seleção natural ao domínio dos instintos, inaugurando a análise biológica do comportamento. Darwin pretendeu mostrar a possibilidade de uma evolução gradual no caso de exemplos complexos como o parasitismo de ninhada do cuco, o hábito escravagista de formigas e a construção das células do favo de abelhas melíferas. Atribuiu ao comportamento um caráter funcional, comparou espécies próximas para reconstituir etapas evolucionárias, colocou os cálculos de custo e benefício e de otimização subjacentes à seleção do comportamento, indicou aspectos de competição entre espécies e de manipulação de umas por outras, e utilizou o pensamento da seleção de grupo para dar conta da presença de indivíduos estéreis em insetos eusociais. Mais do que soluções e resultados, Darwin traz, no capítulo Instinto, argumentos e uma proposta paradigmática para a análise dos comportamentos típicos da espécie, verdadeiro ponto de partida para as abordagens atuais da etologia e da ecologia comportamental.

  17. Produção de sementes macho-estéreis em arroz Male-sterile rice seed production

    Directory of Open Access Journals (Sweden)

    Claudio Bragantini

    2001-02-01

    Full Text Available A obtenção comercial de sementes da linhagem macho-estéril é uma das limitações para viabilizar a produção de híbridos de arroz (Oryza sativa L.. Este trabalho buscou estudar três proporções entre a linhagem macho-estéril (linhagem A e a mantenedora (linhagem B. As proporções estudadas foram 8:4, 10:2 e 14:4. As características avaliadas para determinar qual das proporções apresenta maior potencial foram: número e porcentagem de grãos cheios por panículas, e número de grãos de pólen por unidade de área. A proporção 8:4 produziu maior porcentagem de grãos cheios por panícula que as outras duas, mas, proporcionalmente, ocupa maior área física com a linhagem B no campo. Foram observadas diferenças estatísticas na porcentagem de grãos cheios entre as amostras coletadas nas várias fileiras da linhagem A (diferentes distâncias da fonte polinizadora, e observou-se uma influência marcante com relação à direção predominante dos ventos. O número de grãos de pólen foi igual para todas as relações e distâncias da fonte de pólen; por isso, não foi o fator determinante das diferenças observadas em porcentagem de grãos cheios por panícula. Os resultados permitiram concluir que a proporção 10:2 é a de maior potencial para a produção comercial de sementes da linhagem macho-estéril.Commercial male-sterile rice (Oryza sativa L. seed production is one of the limitations to allow large scale hybrid seed production. This work studied three ratios between male-sterile line (A line and maintainer (B line. The A:B ratios used in the study were: 8:4, 10:2 and 14:4. The evaluated traits to determine which ratio is more suitable were: number and percentage of filled grains per panicle and number of pollen grains per unit area. The 8:4 ratio produced statistically significant higher percentage of filled grains per panicle than the other two, but proportionally it requires more field area for the B line. Statistical

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Rau, P.

    1980-01-01

    The reactor core of nuclear reactors usually is composed of individual elongated fuel elements that may be vertically arranged and through which coolant flows in axial direction, preferably from bottom to top. With their lower end the fuel elements gear in an opening of a lower support grid forming part of the core structure. According to the invention a locking is provided there, part of which is a control element that is movable along the fuel element axis. The corresponding locking element is engaged behind a lateral projection in the opening of the support grid. The invention is particularly suitable for breeder or converter reactors. (orig.) [de

  19. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    A nuclear reactor containment vessel faced internally with a metal liner is provided with thermal insulation for the liner, comprising one or more layers of compressible material such as ceramic fiber, such as would be conventional in an advanced gas-cooled reactor and also a superposed layer of ceramic bricks or tiles in combination with retention means therefor, the retention means (comprising studs projecting from the liner, and bolts or nuts in threaded engagement with the studs) being themselves insulated from the vessel interior so that the coolant temperatures achieved in a High-Temperature Reactor or a Fast Reactor can be tolerated with the vessel. The layer(s) of compressible material is held under a degree of compression either by the ceramic bricks or tiles themselves or by cover plates held on the studs, in which case the bricks or tiles are preferably bedded on a yielding layer (for example of carbon fibers) rather than directly on the cover plates

  20. Nuclear reactor

    International Nuclear Information System (INIS)

    Miyashita, Akio.

    1981-01-01

    Purpose: To facilitate and accelerate a leakage test of valves of a main steam pipe by adding a leakage test partition valve thereto. Constitution: A leakage testing partition valve is provided between a pressure vessel for a nuclear reactor and the most upstream side valve of a plurality of valves to be tested for leakage, a testing branch pipe is communicated with the downstream side of the partition valve, and the testing water for preventing leakage is introduced thereto through the branch pipe. Since main steam pipe can be simply isolated by closing the partition valve in the leakage test, the leakage test can be conducted without raising or lowering the water level in the pressure vessel, and since interference with other work in the reactor can be eliminated, the leakage test can be readily conducted parallel with other work in the reactor in a short time. Clean water can be used without using reactor water as the test water. (Yoshihara, H.)

  1. 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.)

  2. REACTOR SHIELD

    Science.gov (United States)

    Wigner, E.P.; Ohlinger, L.E.; Young, G.J.; Weinberg, A.M.

    1959-02-17

    Radiation shield construction is described for a nuclear reactor. The shield is comprised of a plurality of steel plates arranged in parallel spaced relationship within a peripheral shell. Reactor coolant inlet tubes extend at right angles through the plates and baffles are arranged between the plates at right angles thereto and extend between the tubes to create a series of zigzag channels between the plates for the circulation of coolant fluid through the shield. The shield may be divided into two main sections; an inner section adjacent the reactor container and an outer section spaced therefrom. Coolant through the first section may be circulated at a faster rate than coolant circulated through the outer section since the area closest to the reactor container is at a higher temperature and is more radioactive. The two sections may have separate cooling systems to prevent the coolant in the outer section from mixing with the more contaminated coolant in the inner section.

  3. 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.

  4. Breeder reactors

    International Nuclear Information System (INIS)

    Gollion, H.

    1977-01-01

    The reasons for the development of fast reactors are briefly reviewed (a propitious neutron balance oriented towards a maximum uranium burnup) and its special requirements (cooling, fissile material density and reprocessing) discussed. The three stages in the French program of fast reactor development are outlined with Rapsodie at Cadarache, Phenix at Marcoule, and Super Phenix at Creys-Malville. The more specific features of the program of research and development are emphasized: kinetics and the core, the fuel and the components [fr

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Schulze, I.; Gutscher, E.

    1980-01-01

    The core contains a critical mass of UN or U 2 N 3 in the form of a noncritical solution with melted Sn being kept below a N atmosphere. The lining of the reactor core consists of graphite. If fission progresses part of the melted metal solution is removed and cleaned from fission products. The reactor temperatures lie in the range of 300 to 2000 0 C. (Examples and tables). (RW) [de

  6. Reactor technology

    International Nuclear Information System (INIS)

    Erdoes, P.

    1977-01-01

    This is one of a series of articles discussing aspects of nuclear engineering ranging from a survey of various reactor types for static and mobile use to mention of atomic thermo-electric batteries of atomic thermo-electric batteries for cardiac pacemakers. Various statistics are presented on power generation in Europe and U.S.A. and economics are discussed in some detail. Molten salt reactors and research machines are also described. (G.M.E.)

  7. 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.)

  8. 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.)

  9. Integrity evaluation of the pressure vessels of Angra-2 and Angra-3 reactors by stress analysis

    International Nuclear Information System (INIS)

    Gomes, E.

    1978-01-01

    The integrity of the reactor pressure vessel of the unit II/III of the Nuclear Power Station at 'Angras do Reis' is evaluated by stress analysis, through the dynamics relaxation method. For the solution of the problem an axisymmetric model is fixed. Initially, the data of the Oak Ridge Vessel V-7 is compared with those obtained by two computer programs used in this study. The methods used in the computer programs are FEM and DEM. A11 the results are compared with the ASME Code Section III 1974 edition. The range deviation is determined to 99% confidence limit, in order to minimize the error probabilities. Finally, the equivalent intensity stress obtained is calculated and compared with the acceptable values of the ASME Code Section III, 1974 edition [pt

  10. Aquatic macro algae of a region under Almirante Alvaro Alberto nuclear power plant influence. I. Taxonomic composition; Macroalgas marinhas da regiao sob influencia da Central Nuclear Almirante Alvaro Alberto, Angra dos Reis, RJ, Brasil. I. Composicao taxonomica

    Energy Technology Data Exchange (ETDEWEB)

    Pedrini, A.G. [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil)]|[Universidade Santa Ursula, Rio de Janeiro, RJ (Brazil). Centro de Ciencias Biologicas; Cassano, V.; Coelho, L.G.; Labronici, G.J. [Universidade do Estado, Rio de Janeiro, RJ (Brazil). Inst. de Biologia

    1994-12-31

    A total of 134 taxa were found: 32 Chlorophyta, 29 Phaeophyta and 74 Rhodophyta. The Caulerpales (Chlorophyta) had the highest number of taxa (37,5%) followed by the Dictyotales (Phaeophyta - 43%) and Ceramiales (Rhodophyta - 53%). The benthic flora shows some affinity to that of Ilha Grande (part), Sepetiba Bay and Paraty (Sorensen`s Index - 0,62, 0,61 and 0,58 respectively. (author). 22 refs, 1 fig, 1 tab.

  11. Dinâmica Glacial e Características Sedimentares Resultantes na Zona Proglacial da Geleira Ecology-Baía do Almirantado, Ilha Rei George Antártica.

    OpenAIRE

    Kátia Kellem Rosa; Rosemary Vieira; Jefferson Cardia Simões

    2006-01-01

    A geleira Ecology, localizada na ilha Rei George, ilhas Shetlands do Sul, está sofrendo um processo de rápida retração ao longo das últimas décadas, sendo que no período de 1956 a 1992/95 a geleira retrocedeu 0,37 Km2. Isto gerou um ambiente de deglaciação, com a exposição de várias geoformas na zona proglacial. Este trabalho objetiva estudar o ambiente de deglaciação da zona proglacial da geleir...

  12. 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.)

  13. 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

  14. Brazil-Argentina bilateral cooperation - Protocol 11. Nuclear safety and radiation protection. Visit of CNEA engineers to Brazil

    International Nuclear Information System (INIS)

    Gasparian, A.E.

    1991-01-01

    The activities carried out by Techniques of Argentine Organization (CNEA) during visitation to Angra dos Reis (Brazil) are related. Licensing procedures for nuclear installations (reactors), and transport, licensing of personnels for nuclear installations, quality assurance and regulatory inspections were discussed. (M.C.K.)

  15. Nuclear reactors

    Energy Technology Data Exchange (ETDEWEB)

    Prescott, R F; George, B V; Baglin, C J

    1978-05-10

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given.

  16. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1978-01-01

    Reference is made to thermal insulation on the inner surfaces of containment vessels of fluid cooled nuclear reactors and particularly in situations where the thermal insulation must also serve a structural function and transmit substantial load forces to the surface which it covers. An arrangement is described that meets this requirement and also provides for core support means that favourably influences the flow of hot coolant from the lower end of the core into a plenum space in the hearth of the reactor. The arrangement comprises a course of thermally insulating bricks arranged as a mosaic covering a wall of the reactor and a course of thermally insulating tiles arranged as a mosaic covering the course of bricks. Full constructional details are given. (UK)

  17. Bioconversion reactor

    Science.gov (United States)

    McCarty, Perry L.; Bachmann, Andre

    1992-01-01

    A bioconversion reactor for the anaerobic fermentation of organic material. The bioconversion reactor comprises a shell enclosing a predetermined volume, an inlet port through which a liquid stream containing organic materials enters the shell, and an outlet port through which the stream exits the shell. A series of vertical and spaced-apart baffles are positioned within the shell to force the stream to flow under and over them as it passes from the inlet to the outlet port. The baffles present a barrier to the microorganisms within the shell causing them to rise and fall within the reactor but to move horizontally at a very slow rate. Treatment detention times of one day or less are possible.

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Scholz, M.

    1976-01-01

    An improvement of the accessibility of that part of a nuclear reactor serving for biological shield is proposed. It is intended to provide within the biological shield, distributed around the circumference of the reactor pressure vessel, several shielding chambers filled with shielding material, which are isolated gastight from the outside by means of glass panes with a given bursting strength. It is advantageous that, on the one hand, inspection and maintenance will be possible without great effort and, on the other, a large relief cross section will be at desposal if required. (UWI) [de

  19. NEUTRONIC REACTOR

    Science.gov (United States)

    Wigner, E.P.; Weinberg, A.W.; Young, G.J.

    1958-04-15

    A nuclear reactor which uses uranium in the form of elongated tubes as fuel elements and liquid as a coolant is described. Elongated tubular uranium bodies are vertically disposed in an efficient neutron slowing agent, such as graphite, for example, to form a lattice structure which is disposed between upper and lower coolant tanks. Fluid coolant tubes extend through the uranium bodies and communicate with the upper and lower tanks and serve to convey the coolant through the uranium body. The reactor is also provided with means for circulating the cooling fluid through the coolant tanks and coolant tubes, suitable neutron and gnmma ray shields, and control means.

  20. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    The method of operating a water-cooled neutronic reactor having a graphite moderator is described which comprises flowing a gaseous mixture of carbon dioxide and helium, in which the helium comprises 40--60 volume percent of the mixture, in contact with the graphite moderator. 2 claims, 4 figures

  1. Neutronic reactor

    International Nuclear Information System (INIS)

    Wende, C.W.J.

    1976-01-01

    A safety rod for a nuclear reactor has an inner end portion having a gamma absorption coefficient and neutron capture cross section approximately equal to those of the adjacent shield, a central portion containing materials of high neutron capture cross section and an outer end portion having a gamma absorption coefficient at least equal to that of the adjacent shield

  2. Reactor facility

    International Nuclear Information System (INIS)

    Suzuki, Hiroaki; Murase, Michio; Yokomizo, Osamu.

    1997-01-01

    The present invention provides a BWR type reactor facility capable of suppressing the amount of steams generated by the mutual effect of a failed reactor core and coolants upon occurrence of an imaginal accident, and not requiring spacial countermeasures for enhancing the pressure resistance of the container vessel. Namely, a means for supplying cooling water at a temperature not lower by 30degC than the saturated temperature corresponding to the inner pressure of the containing vessel upon occurrence of an accident is disposed to a lower dry well below the pressure vessel. As a result, upon occurrence of such an accident that the reactor core should be melted and flown downward of the pressure vessel, when cooling water at a temperature not lower than the saturated temperature, for example, cooling water at 100degC or higher is supplied to the lower dry well, abrupt generation of steams by the mutual effect of the failed reactor core and cooling water is scarcely caused compared with a case of supplying cooling water at a temperature lower than the saturation temperature by 30degC or more. Accordingly, the amount of steams to be generated can be suppressed, and special countermeasure is no more necessary for enhancing the pressure resistance of the container vessel is no more necessary. (I.S.)

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Gilroy, J.E.

    1980-01-01

    An improved cover structure for liquid metal cooled fast breeder type reactors is described which it is claimed reduces the temperature differential across the intermediate grid plate of the core cover structure and thereby reduces its subjection to thermal stresses. (UK)

  4. Reactor licensing

    International Nuclear Information System (INIS)

    Harvie, J.D.

    2002-01-01

    This presentation discusses reactor licensing and includes the legislative basis for licensing, other relevant legislation , the purpose of the Nuclear Safety and Control Act, important regulations, regulatory document, policies, and standards. It also discusses the role of the CNSC, its mandate and safety philosophy

  5. Nuclear reactor

    International Nuclear Information System (INIS)

    Hattori, Sadao; Sekine, Katsuhisa.

    1987-01-01

    Purpose: To decrease the thickness of a reactor container and reduce the height and the height and plate thickness of a roof slab without using mechanical vibration stoppers. Constitution: Earthquake proofness is improved by filling fluids such as liquid metal between a reactor container and a secondary container and connecting the outer surface of the reactor container with the inner surface of the secondary container by means of bellows. That is, for the horizontal seismic vibrations, horizontal loads can be supported by the secondary container without providing mechanical vibration stoppers to the reactor container and the wall thickness can be reduced thereby enabling to simplify thermal insulation structure for the reduction of thermal stresses. Further, for the vertical seismic vibrations, verical loads can be transmitted to the secondary container thereby enabling to reduce the wall thickness in the same manner as for the horizontal load. By the effect of transferring the point of action of the container load applied to the roof slab to the outer circumferential portion, the intended purpose can be attained and, in addition, the radiation dose rate at the upper surface of the roof slab can be decreased. (Kamimura, M.)

  6. Reactor system

    International Nuclear Information System (INIS)

    Miyano, Hiroshi; Narabayashi, Naoshi.

    1990-01-01

    The represent invention concerns a reactor system with improved water injection means to a pressure vessel of a BWR type reactor. A steam pump is connected to a heat removing system pipeline, a high pressure water injection system pipeline and a low pressure water injection system pipeline for injecting water into the pressure vessel. A pump actuation pipeline is disposed being branched from a main steam pump or a steam relieaf pipeline system, through which steams are supplied to actuate the steam pump and supply cooling water into the pressure vessel thereby cooling the reactor core. The steam pump converts the heat energy into the kinetic energy and elevates the pressure of water to a level higher than the pressure of the steams supplied by way of a pressure-elevating diffuser. Cooling water can be supplied to the pressure vessel by the pressure elevation. This can surely inject cooling water into the pressure vessel upon loss of coolant accident or in a case if reactor scram is necessary, without using an additional power source. (I.N.)

  7. Reactor core

    International Nuclear Information System (INIS)

    Matsuura, Tetsuaki; Nomura, Teiji; Tokunaga, Kensuke; Okuda, Shin-ichi

    1990-01-01

    Fuel assemblies in the portions where the gradient of fast neutron fluxes between two opposing faces of a channel box is great are kept loaded at the outermost peripheral position of the reactor core also in the second operation cycle in the order to prevent interference between a control rod and the channel box due to bending deformation of the channel box. Further, the fuel assemblies in the second row from the outer most periphery in the first operation cycle are also kept loaded at the second row in the second operation cycle. Since the gradient of the fast neutrons in the reactor core is especially great at the outer circumference of the reactor core, the channel box at the outer circumference is bent such that the surface facing to the center of the reactor core is convexed and the channel box in the second row is also bent to the identical direction, the insertion of the control rod is not interfered. Further, if the positions for the fuels at the outermost periphery and the fuels in the second row are not altered in the second operation cycle, the gaps are not reduced to prevent the interference between the control rod and the channel box. (N.H.)

  8. Zumbi dos Palmares: a afroresiliencia

    Directory of Open Access Journals (Sweden)

    Josué Petrônio Quirino de Oliveira

    2017-10-01

    Full Text Available O artigo buscou fazer uma releitura de Zumbi dos Palmares sob o prisma da resiliência, demonstrando uma visão singular ao olhar para os escravos nos quilombos e suas histórias de superação e transformação perante as adversidades, levando não só a reconstruir o imaginário afrodescendente brasileiro com o caleidoscópio da resiliência, mas revelar que a resiliência sempre foi inerente a história dos negros no Brasil. Para tanto se caracterizou como uma pesquisa exploratória com abordagem qualitativa e procedimentos bibliográficos que foram essenciais para a construção do artigo, amadurecendo e ampliando os conhecimentos envolvidos na temática. Nesta abordagem o quilombo dos Palmares foi um conjunto complexo de condições, atitudes e ações que apesar das adversidades tiveram resultados positivos, os fatos demonstraram que os negros nos quilombos foram uma prova que a resiliência negra não foi apenas um fator individual, mas uma característica comunitária que desencadeou um processo de ruptura e recuperação social, um grito de liberdade em defesa da consciência de uma raça, e de um povo. Zumbi não foi apenas um líder de um movimento libertário que marcou a história dos negros oriundos de Pernambuco e Alagoas, mas a história de uma raça por gerações no país, que se tornou sinônimo de resiliência.

  9. 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

  10. Reis Rosenbergi ajudesse / Vaapo Vaher

    Index Scriptorium Estoniae

    Vaher, Vaapo, 1945-

    2007-01-01

    Lugemismuljeid raamatutest: Piper, Ernst. Alfred Rosenberg : Hitleri peaideoloog. Tallinn : Tänapäev, 2007 ; Judt, Tony. Pärast sõda. Euroopa ajalugu 1945. aastast. Tallinn : Varrak, 2007 ; Döblin, Alfred. Berliin, Alexanderplatz / tlk. Mati Sirkel. Tallinn : Tänapäev, 2007 ; Adson, Artur. Siuru-raamat. Tallinn : Tänapäev, 2007

  11. 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.)

  12. Development of the user Interface of digital simulation system of the operational parameters of the TRIGA IPR-R1 Nuclear Research Reactor; Desenvolvimento da interface para usuário do sistema digital de simulação dos parâmetros operacionais do reator nuclear de pesquisa Triga IPR-R1

    Energy Technology Data Exchange (ETDEWEB)

    Felippe, Adriano de A.M., E-mail: adrianoamfelippe@gmail.com [Universidade Federal de Minas Gerais (UFMG), Belo Horizonte, MG (Brazil); Lage, Aldo M.F.; Mesquita, Amir Z., E-mail: aldo@cdtn.br, E-mail: amir@cdtn.br [Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/CNEN-MG), Belo Horizonte, MG (Brazil)

    2017-07-01

    The development of simulation systems has been increasingly improved to ensure security and reliability to the systems being associated. Computational tools, simulation systems and programming languages increasingly allow the diversification of control systems. With increasing concern about monitoring the key parameters involved in chain reactions inside a nuclear reactor, new technologies are being developed to ensure operations safety. This paper deals with a practical application of a work that is being developed in the Center for the Development of Nuclear Technology - CDTN, which intends to simulate the operation of the TRIGA-IPR-R1 nuclear research reactor using the LabVIEW® software, evaluating the evolution of the neutron flux and other related events. In this paper, the visual interface of the reactor control table, developed through virtual instruments that allow, in a vast repertoire of tools, replicating the panels of the control table in modern screens that can be operated by a user of an analogous form, but still more practical and complete. Since the innovations developed for research reactors can be replicated in power reactors, and because of their lower operating and maintenance costs, projects in this area allow the development of several technologies.

  13. As misericórdias e as transferências de bens: o caso dos Monteiros, entre o Porto e a Ásia (1580-1640

    Directory of Open Access Journals (Sweden)

    Isabel dos Guimarães Sá

    Full Text Available Resumo Os testamentos de dois mercadores da mesma família, envolvidos na viagem do Japão, Antônio e Domingos Monteiro, revelam um modo de vida marcado pela mobilidade entre vários territórios do Sudeste Asiático, transacionando grande variedade de produtos. Por meio de sua rede de relações, é possível discernir a presença de parentes seus, sobretudo sobrinhos, e de outros negociantes portuenses, sugerindo que o modelo português de emigração para o Brasil já estava em ação no Oriente. Embora a transmissão de bens competisse aos provedores dos defuntos e ausentes, as misericórdias transferiam capitais de defuntos para a metrópole, em detrimento dos agentes diretos do rei, embora fosse impossível evitar a ingerência destes últimos. Apesar da vontade em fazer chegar o dinheiro à metrópole rapidamente para convertê-lo em padrões de juro, conveniências do trato, a burocracia régia e litígios sucessórios tornavam moroso o processo de transferência.

  14. Tiit Kask, Aldur Vunk (Hrsg.): Reis (nõukogude) läände / Journey to the [Soviet] west. Kuurortlinn Pärnu 1940-88. Artiklite kogumik / Resort town of Pärnu 1940-88. Collection of articles, Pärnu: Pärnu Linnavalitsus 2009, 121 S., 97 Abb. / Andr

    Index Scriptorium Estoniae

    Fülberth, Andreas

    2011-01-01

    Raamatuarvustus: Reis (nõukogude) läände : kuurortlinn Pärnu 1940-88 : artiklite kogumik = Journey to the [Soviet] West : resort town of Pärnu during 1940-88 : collection of articles. Pärnu, 2009

  15. Nuclear reactor

    International Nuclear Information System (INIS)

    Gibbons, J.F.; McLaughlin, D.J.

    1978-01-01

    In the pressure vessel of the water-cooled nuclear reactor there is provided an internal flange on which the one- or two-part core barrel is hanging by means of an external flange. A cylinder is extending from the reactor vessel closure downwards to a seat on the core cupport structure and serves as compression element for the transmission of the clamping load from the closure head to the core barrel (upper guide structure). With the core barrel, subject to tensile stress, between the vessel internal flange and its seat on one hand and the compression of the cylinder resp. hold-down element between the closure head and the seat on the other a very strong, elastic sprung structure is obtained. (DG) [de

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Sasaki, Tomozo.

    1987-01-01

    Purpose: To improve the nuclear reactor availability by enabling to continuously exchange fuels in the natural-slightly enriched uranium region during operation. Constitution: A control rod is withdrawn to the midway of a highly enriched uranium region by means of control rod drives and the highly enriched uranium region is burnt to maintain the nuclear reactor always at a critical state. At the same time, fresh uranium-slightly enriched uranium is continuously supplied gravitationally from a fresh fuel reservoir through fuel reservoir to each of fuel pipes in the natural-slightly enriched uranium region. Then, spent fuels reduced with the reactivity by the burn up are successively taken out from the bottom of each of the fuel pipes through an exit duct and a solenoid valve to the inside of a spent fuel reservoir and the burn up in the natural-slightly enriched uranium region is conducted continuously. (Kawakami, Y.)

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Sakurai, Mikio; Yamauchi, Koki.

    1983-01-01

    Purpose: To improve the channel stability and the reactor core stability in a spontaneous circulation state of coolants. Constitution: A reactor core stabilizing device comprising a differential pressure automatic ON-OFF valve is disposed between each of a plurality of jet pumps arranged on a pump deck. The stabilizing device comprises a piston exerted with a pressure on the lower side of the pump deck by way of a pipeway and a valve for flowing coolants through the bypass opening disposed to the pump deck by the opening and closure of the valve ON-OFF. In a case where the jet pumps are stopped, since the differential pressure between the upper and the lower sides of the pump deck is removed, the valve lowers gravitationally into an opened state, whereby the coolants flow through the bypass opening to increase the spontaneous circulation amount thereby improve the stability. (Yoshino, Y.)

  18. Nuclear reactor

    International Nuclear Information System (INIS)

    Aleite, W.; Bock, H.W.; Struensee, S.

    1976-01-01

    The invention concerns the use of burnable poisons in a nuclear reactor, especially in PWRs, in order to improve the controllability of the reactor. An unsymmetrical arrangement in the lattice is provided, if necessary also by insertion of special rods for these additions. It is proposed to arrange the burnable poisons in fuel elements taken over from a previous burn-up cycle and to distribute them, going out from the side facing the control rods, over not more than 20% of the lenth of the fuel elements. It seems sufficient, for the burnable poisons to bind an initial reactivity of only 0.1% and to become ineffective after normal operation of 3 to 4 months. (ORU) [de

  19. Reactor container

    International Nuclear Information System (INIS)

    Ichiki, Tadaharu; Saba, Kazuhisa.

    1979-01-01

    Purpose: To improve the earthquake resistance as well as reduce the size of a container for a nuclear reactor with no adverse effects on the decrease of impact shock to the container and shortening of construction step. Constitution: Reinforcing profile steel materials are welded longitudinally and transversely to the inner surface of a container, and inner steel plates are secured to the above profile steel materials while keeping a gap between the materials and the container. Reactor shielding wall planted to the base concrete of the container is mounted to the pressure vessel, and main steam pipeways secured by the transverse beams and led to the outside of container is connected. This can improve the rigidity earthquake strength and the safetiness against the increase in the inside pressure upon failures of the container. (Yoshino, Y.)

  20. Reactor container

    International Nuclear Information System (INIS)

    Oyamada, Osamu; Furukawa, Hideyasu; Uozumi, Hiroto.

    1979-01-01

    Purpose: To lower the position of an intermediate slab within a reactor container and fitting a heat insulating material to the inner wall of said intermediate slab, whereby a space for a control rod exchanging device and thermal stresses of the inner peripheral wall are lowered. Constitution: In the pedestal at the lower part of a reactor pressure vessel there is formed an intermediate slab at a position lower than diaphragm floor slab of the outer periphery of the pedestal thereby to secure a space for providing automatic exchanging device of a control rod driving device. Futhermore, a heat insulating material is fitted to the inner peripheral wall at the upper side of the intermediate slab part, and the temperature gradient in the wall thickness direction at the time of a piping rupture trouble is made gentle, and thermal stresses at the inner peripheral wall are lowered. (Sekiya, K.)

  1. Neutronic reactor

    International Nuclear Information System (INIS)

    Lewis, W.R.

    1978-01-01

    Disclosed is a graphite-moderated, water-cooled nuclear reactor including a plurality of rectangular graphite blocks stacked in abutting relationship in layers, alternate layers having axes which are normal to one another, alternate rows of blocks in alternate layers being provided with a channel extending through the blocks, said channeled blocks being provided with concave sides and having smaller vertical dimensions than adjacent blocks in the same layer, there being nuclear fuel in the channels

  2. Nuclear reactors

    International Nuclear Information System (INIS)

    Humphreys, P.; Davidson, D.F.; Thatcher, G.

    1980-01-01

    The cooling system of a liquid metal cooled fast breeder nuclear reactor of the pool kind is described. It has an intermediate heat exchange module comprising a tube-in-shell heat exchanger and an electromagnetic flow coupler in the base region of the module. Primary coolant is flowed through the heat exchanger being driven by electromagnetic interaction with secondary liquid metal coolant flow effected by a mechanical pump. (author)

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Jungmann, A.

    1975-01-01

    Between a PWR's reactor pressure vessel made of steel and the biological shield made of concrete there is a gap. This gap is filled up with a heat insulation facting the reactor pressure vessel, for example with insulating concrete segments jacketed with sheet steel and with an additional layer. This layer serves for smooth absorption of compressive forces originating in radial direction from the reactor pressure vessel. It consists of cylinder-segment shaped bricks made of on situ concrete, for instance. The bricks have cooling agent ports in one or several rows which run parallel to the wall of the pressure vessel and in alignment with superposed bricks. Between the layer of bricks and the biological shield or rather the heat insulation, there are joints which are filled, however, with injected mortar. That guarantees a smooth series of connected components resistant tom compression. Besides, a slip foil can be set between the heat insulation and the joining joint filled with mortar for the reduction of the friction at thermal expansions. (TK) [de

  4. Reactor building

    International Nuclear Information System (INIS)

    Ebata, Sakae.

    1990-01-01

    At least one valve rack is disposed in a reactor building, on which pipeways to a main closure valve, valves and bypasses of turbines are placed and contained. The valve rack is fixed to the main body of the building or to a base mat. Since the reactor building is designed as class A earthquake-proofness and for maintaining the S 1 function, the valve rack can be fixed to the building main body or to the base mat. With such a constitution, the portions for maintaining the S 1 function are concentrated to the reactor building. As a result, the dispersion of structures of earthquake-proof portion corresponding to the reference earthquake vibration S 1 can be prevented. Accordingly, the conditions for the earthquake-proof design of the turbine building and the turbine/electric generator supporting rack are defined as only the class B earthquake-proof design conditions. In view of the above, the amount of building materials can be saved and the time for construction can be shortened. (I.S.)

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Yoshioka, Michiko.

    1985-01-01

    Purpose: To obtain an optimum structural arrangement of IRM having a satisfactory responsibility to the inoperable state of a nuclear reactor and capable of detecting the reactor power in an averaged manner. Constitution: As the structural arrangement of IRM, from 6 to 16 even number of IRM are bisected into equial number so as to belong two trip systems respectively, in which all of the detectors are arranged at an equal pitch along a circumference of a circle with a radius rl having the center at the position of the central control rod in one trip system, while one detector is disposed near the central control rod and other detectors are arranged substantially at an equal pitch along the circumference of a circle with a radius r2 having the center at the position for the central control rod in another trip system. Furthermore, the radius r1 and r2 are set such that r1 = 0.3 R, r2 = 0.5 R in the case where there are 6 IRM and r1 = 0.4 R and R2 = 0.8 R where there are eight IRM where R represents the radius of the reactor core. (Kawakami, Y.)

  6. MLR reactor

    International Nuclear Information System (INIS)

    Ryazantsev, E.P.; Egorenkov, P.M.; Nasonov, V.A.; Smimov, A.M.; Taliev, A.V.; Gromov, B.F.; Kousin, V.V.; Lantsov, M.N.; Radchenko, V.P.; Sharapov, V.N.

    1998-01-01

    The Material Testing Loop Reactor (MLR) development was commenced in 1991 with the aim of updating and widening Russia's experimental base to validate the selected directions of further progress of the nuclear power industry in Russia and to enhance its reliability and safety. The MLR reactor is the pool-type one. As coolant it applies light water and as side reflector beryllium. The direction of water circulation in the core is upward. The core comprises 30 FA arranged as hexagonal lattice with the 90-95 mm pitch. The central materials channel and six loop channels are sited in the core. The reflector includes up to 11 loop channels. The reactor power is 100 MW. The average power density of the core is 0.4 MW/I (maximal value 1.0 MW/l). The maximum neutron flux density is 7.10 14 n/cm 2 s in the core (E>0.1 MeV), and 5.10 14 n/cm 2 s in the reflector (E<0.625 eV). In 1995 due to the lack of funding the MLR designing was suspended. (author)

  7. Nuclear reactor

    International Nuclear Information System (INIS)

    Shirakawa, Toshihisa.

    1979-01-01

    Purpose: To prevent cladding tube injuries due to thermal expansion of each of the pellets by successively extracting each of the control rods loaded in the reactor core from those having less number of notches, as well as facilitate the handling work for the control rods. Constitution: A recycle flow control device is provided to a circulation pump for forcibly circulating coolants in the reactor container and an operational device is provided for receiving each of the signals concerning number of notches for each of the control rods and flow control depending on the xenon poisoning effect obtained from the signals derived from the in-core instrument system connected to the reactor core. The operational device is connected with a control rod drive for moving each of the control rods up and down and a recycle flow control device. The operational device is set with a pattern for the aimed control rod power and the sequence of extraction. Upon extraction of the control rods, they are extracted successively from those having less notch numbers. (Moriyama, K.)

  8. Reactor container

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Hatamiya, Shigeo; Kawasaki, Terufumi; Fukui, Toru; Suzuki, Hiroaki; Kataoka, Yoshiyuki; Kawabe, Ryuhei; Murase, Michio; Naito, Masanori.

    1990-01-01

    In order to suppress the pressure elevation in a reactor container due to high temperature and high pressure steams jetted out upon pipeway rupture accidents in the reactor container, the steams are introduced to a pressure suppression chamber for condensating them in stored coolants. However, the ability for suppressing the pressure elevation and steam coagulation are deteriorated due to the presence of inactive incondensible gases. Then, there are disposed a vent channel for introducing the steams in a dry well to a pressure suppression chamber in the reactor pressure vessel, a closed space disposed at the position lower than a usual liquid level, a first channel having an inlet in the pressure suppression chamber and an exit in the closed space and a second means connected by way of a backflow checking means for preventing the flow directing to the closed space. The first paths are present by plurality, a portion of which constitutes a syphon. The incondensible gases and the steams are discharged to the dry well at high pressure by using the difference of the water head for a long cooling time after the pipeway rupture accident. Then, safety can be improved without using dynamic equipments as driving source. (N.H.)

  9. 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.)

  10. Molten salt reactors: reactor cores

    International Nuclear Information System (INIS)

    1983-01-01

    In this critical analysis of the MSBR I project are examined the problems concerning the reactor core. Advantages of breeding depend essentially upon solutions to technological problems like continuous reprocessing or graphite behavior under neutron irradiation. Graphite deformation, moderator unloading, control rods and core instrumentation require more studies. Neutronics of the core, influence of core geometry and salt composition, fuel evolution, and thermohydraulics are reviewed [fr

  11. 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%

  12. Da arquitetura dos textos a eloquência dos lugares

    OpenAIRE

    Rochelle de Quadros Loguércio; UFPEL

    2008-01-01

    Uma das questões importantes nas perspectivas pós- moderna e pós-estruturalistas em educação é a possibilidade de ler textos que estão visibilizados de outras formas que não as da fala e da escrita. Outro e evidenciar uma discussão sobre a linguagem caracterísitca de um fazer científico e de um fazer educacional tendo como  plano de fundo as falas da Educação em Bioquímica. Pretende-se mostrar que as linguagens dos campos de origem -bioquímica e educação - conformam e determinam um modo de li...

  13. Impact of uranium concentration reduction in side plates of the fuel elements of IEA-R1 reactor on neutronic and thermal hydraulic analyses; Impacto da reducao na concentracao de uranio nas placas laterais dos elementos combustiveis do reator IEA-R1 nas analises neutronica e termo-hidraulica

    Energy Technology Data Exchange (ETDEWEB)

    Rios, Ilka Antonia

    2013-09-01

    This master thesis presents a study to verify the impact of the uranium concentration reduction in the side plates of the reactor IEA-R1 fuel elements on the neutronic and thermal-hydraulic analyses. To develop such study, a previous IPEN-CNEN/SP research was reproduced by simulating the fuel elements burn-up, with side plate uranium density reduced to 50, 60 and 70% of the standard fuel element plates. This research begins with the neutronic analysis using the computer code HAMMER and the first step consists in the calculation of the cross section of all materials presented at the reactor core, with their initial concentration; the second step consists in the calculation of the fast and thermal neutron group fluxes and power densities for fuel elements using the computer code CITATION. HAMMER output data is used as input data. Once the neutronic analysis is finished and the most critical fuel elements with highest power density have been defined, the thermal-hydraulics analysis begins. This analysis uses MCTR-IEA-R1 thermal-hydraulics model, which equations are solved by commercial code EES. Thermalhydraulics analysis input is the power density data calculated by CITATION: it is considered the highest power density on each fuel element, where there is a higher energy release and, consequently, higher temperatures. This data is used on energy balance equations to calculate temperatures on critical fuel element regions. Reactor operation comparison for three different uranium densities on fuel side plates is presented. Uranium density reduction contributes to the cladding surface temperature to remain below the established limit, as reactor operation safety requirement and it does not affect significantly fuel element final burn-up nor reactor reactivity. The reduction of uranium in the side plates of the fuel elements of the IEA-R1 showed to be a viable option to avoid corrosion problems due to high temperatures. (author)

  14. 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

  15. 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

  16. Nuclear reactor

    International Nuclear Information System (INIS)

    Jolly, R.

    1979-01-01

    The support grid for the fuel rods of a liquid metal cooled fast breeder reactor has a regular hexagonal contour and contains a large number of unit cells arranged honeycomb fashion. The totality of these cells make up a hexagonal shape. The grid contains a number of strips of material, and there is a window in each of three sidewalls staggered by one sidewall. The other sidewalls have embossed protrusions, thus generating a guide lining or guide bead. The windows reduce the rigidity of the areas in the middle between the ends of the cells. (DG) [de

  17. Nuclear reactor

    International Nuclear Information System (INIS)

    Anthony, A.J.; Gruber, E.A.

    1979-01-01

    A nuclear reactor with control rods in channels between fuel assemblies wherein the fuel assemblies incorporate guide rods which protrude outwardly into the control rod channels to prevent the control rods from engaging the fuel elements. The guide rods also extend back into the fuel assembly such that they are relatively rigid members. The guide rods are tied to the fuel assembly end or support plates and serve as structural members which are supported independently of the fuel element. Fuel element spacing and support means may be attached to the guide rods. 9 claims

  18. “Financing for urbanizing” Rio de Janeiro: José de Oliveira Reis between the Department of Urban Planning and the Superintendency of Urban Planning and Sanitation in the implementation of the Plano de Realizações

    Directory of Open Access Journals (Sweden)

    Rodrigo Santos de Faria

    2009-06-01

    Full Text Available The present article is characterized by the analysis of the insertion of engineer José de Oliveira Reis in a specific moment (not the only one of the continued construction process of the municipal administrative instances in charge of urban planning and urban plans in Rio de Janeiro. From 1956 through 1960, José de Oliveira Reis reassumes, for the last time, the Department of Urban Planning of Distrito Federal City Hall, actively taking part in the ascribed institutional construction-creationimprovement process of municipal organs responsible for the planning, financing and execution of public urban works. In this case, for the creation of the Superintendency of Urban Planning and Sanitation (SURSAN of the Special Fund for Public Works, and for the implementation of the Execution Plan issued in deliberations in Law no. 899, of November 28th 1957. The understanding of the national context – in the scope of the Brazilian Municipalist Movement – of this whole process of the creation of municipal instances in the urban planning sector, during the 1950s, is also fundamental for comprehending engineer José de Oliveira Reis’s positions as the director of the Department. Centered in the basic precepts of political and financial autonomy, Brazilian Municipalism preconizes an important set of deliberations resulting from National Congresses of Brazilian Municipalities – especially from the four first ones - , among which the need for the implementation of mechanisms and instruments for increasing municipal budgets in the execution of works, that is, “financing for urbanizing”. In the case of the Execution Plan, through the focus in the road system problematics undertaken by the Department of Urban Planning, explicating debate on the construction of the Perimetral Avenue.

  19. Country Report: Rep. of Korea. {sup 188}re-Tricabonyl Labeling Strategy: Preparation of 1{sup 188}Re(I) Tricarbonyl Precursor [{sup 188}Re(OH{sub 2}){sub 3}(CO){sub 3}]+ for the Labeling of Biomolecules

    Energy Technology Data Exchange (ETDEWEB)

    Park, Sang Hyun [Radiation Research Division for Biotechnology, Korea Atomic Energy Research Institute (Korea, Republic of)

    2010-07-01

    The {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl precursors [M(OH{sub 2}){sub 3}(CO){sub 3}]{sup +} have been shown to be excellent starting materials for the synthesis of {sup 99m}Tc(I) and {sup 188}Re(I) tricarbonyl complexes as well as radiolabeling of target-specific biomolecules.{sup 1-8} Recently, a user-friendly kit formulation (IsoLink{sup TM}) was developed using potassium boranocarbonate, K{sub 2}[BH{sub 3}CO{sub 2}], for preparation of the {sup 99m}Tc precursor complex. This solid reagent serves both as a source of carbon monoxide and a reducing agent for technetium. It was also used by Schibli and coworkers for the preparation of the corresponding {sup 188}Re precursor complex (“Schibili’s kit”).{sup 9} This approach involved the reduction of [{sup 188}Re]perrhenate eluate (1 ml) in neutral solution with 3 mg K{sub 2}[BH{sub 3}CO{sub 2}] and 5 mg BH3≅NH3 by incubation at 60 °C for 15 min. The amounts of reducing agents and acid (concentrated phosphoric acid) were carefully balanced not only to avoid fast hydrolysis of the boranes, but also to maintain a sufficiently low pH to stabilize reduced rhenium intermediates. The preparations resulted in yields >85 % of the desired precursor complex. In addition, perrhenate (7±3 %), colloidal {sup 188}ReO{sub 2} (<5 %), and a byproduct of unknown composition were also detected. To increase the yields even further, we evaluated the recently described borohydride exchange resin (BER) as an additional reducing agent and an anion scavengers.

  20. Remessas de recursos dos imigrantes

    Directory of Open Access Journals (Sweden)

    Ana Cristina Braga Martes

    2006-08-01

    Full Text Available AS REMESSAS contribuem para o desenvolvimento local e para redução da pobreza? Essa é a pergunta-chave que os estudos recentes sobre migrações internacionais têm levantado. O que se está procurando compreender é de que modo as remessas poderiam afetar positiva ou negativamente a economia dos países de origem dos imigrantes. Discutir o papel e o significado das remessas implica, assim, uma discussão em torno da existência (ou não de um "campo de positividades" do fenômeno migratório internacional. O principal objetivo deste artigo é contribuir para essa discussão por meio de um estudo empírico do caso brasileiro que adota as remessas como foco. Para tanto, é identificado o perfil das remessas e dos remetentes, assim como os objetivos e os beneficiários do dinheiro enviado. A pesquisa usa uma abordagem baseada em entrevistas em profundidade e survey não-representativo (Boston e Governador Valadares.DO REMITTANCES contribute to local development and the reduction of poverty? What are the consequences of the dollars sent by the migrants to the people, families, and organizations that receive them in the cities of origin? These are the key questions that recent studies have raised. According to some authors "migration is inevitable and has the potential to be quite positive in terms of development and reduction of poverty. The policies that have their origins in this principle will be more successful than those that attempt to oppose, intransigently, both globalization and the migration of people in space". Do current international migrations produce positive local development effects? The main objective of this article is to contribute to this discussion through an empirical study of the Brazilian case, which takes remittances as its focus. Thus, we identify who the immigrants are who send remittances from the United States to Brazil, to what ends the remittances are directed, who the beneficiaries are, and how the remittances

  1. AS AULAS RÉGIAS E OS SALÁRIOS DOS PROFESSORES NO PERÍODO DE REORGANIZAÇÃO DOS ESTUDOS (MINAS GERAIS, 1795-1800

    Directory of Open Access Journals (Sweden)

    Cleide Cristina Oliveira

    2012-10-01

    Full Text Available RESUMO:Em 1777 D. Maria I assumiu o trono de Portugal. Todavia, a rainha fora afastada do poder por se encontrar em um estado de insanidade mental e, durante a regência de seu filho D. João, iniciada em 1792, suas determinações sofreram uma inflexão. Sob um contexto de crise econômica, houve uma tentativa de reorganização das escolas, baseada em um processo de centralização administrativa. A partir deste contexto é que analisamos os temas discutidos neste artigo: a disseminação das aulas régias na Capitania de Minas Gerais e os salários dos professores. Para tanto, tomamos como fontes de pesquisa documentos oficiais, produzidos entre 1795 e 1800. Identificamos as aulas de Primeiras Letras e de Gramática Latina como as mais numerosas e, ainda, que nem sempre as escolas oficialmente autorizadas funcionavam. Os valores dos salários dos mestres eram diferenciados conforme a especialidade ensinada: Filosofia (460$000 réis anuais, Retórica (440$000, Gramática Latina (400$000 e Primeiras Letras (150$000. No final do século XVIII, havia professores que não recebiam os salários integralmente e muitos que não recebiam absolutamente nada há anos. Os professores de Primeiras Letras eram os que possuíam salários atrasados com maior frequência e, mesmo assim, continuavam a exercer suas atividades.PALAVRAS-CHAVE: aulas régias; reorganização dos estudos; salários de professores.ABSTRACT: In 1777 Queen Mary I took the throne of Portugal. However, the queen was removed from power because he is in a state of insanity and, during the regency of his son King John, started in 1792, its provisions have undergone a shift. Under a context of economic crisis, there was an attempt to reorganize the schools, based on an administrative centralization process. From this context is that we analyze the issues discussed in this article: the spread of royal schools in Minas Gerais captaincy and teacher salaries. To this end, we take as research

  2. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.; George, B.V.; Baglin, C.J.

    1979-01-01

    In a nuclear reactor (e.g. one having coolant down-flow through a core to a hearth below) thermal insulation (e.g. of a floor of the hearth) comprises a layer of bricks and a layer of tiles thereon, with smaller clearances between the tiles than between the bricks but with the bricks being of reduced cross-section immediately adjacent the tiles so as to be surrounded by interconnected passages, of relatively large dimensions, constituting a continuous chamber extending behind the layer of tiles. By this arrangement, lateral coolant flow in the inter-brick clearances is much reduced. The reactor core is preferably formed of hexagonal columns, supported on diamond-shaped plates each supported on a pillar resting on one of the hearth-floor tiles. Each plate has an internal duct, four upper channels connecting the duct with coolant ducts in four core columns supported by the plate, and lower channels connecting the duct to a downwardly-open recess common to three plates, grouped to form a hexagon, at their mutually-adjacent corners. This provides mixing, and temperature-averaging, of coolant from twelve columns

  3. Reactor container

    International Nuclear Information System (INIS)

    Oikawa, Hirohide; Otonari, Jun-ichiro; Tozaki, Yuka.

    1993-01-01

    Partition walls are disposed between a reactor pressure vessel and a suppression chamber to separate a dry well to an upper portion and a lower portion. A communication pipe is disposed to the partition walls. One end of the communication pipe is opened in an upper portion of the dry well at a position higher than a hole disposed to a bent tube of the suppression chamber. When coolants overflow from a depressurization valve by an erroneous operation of an emergency reactor core cooling device, the coolants accumulate in the upper portion of the dry well. When the pipeline is ruptured at the upper portion of the pressure vessel, only the inside of the pressure vessel and the upper portion of the dry well are submerged in water. In this case, the water level of the coolants does not elevate to the opening of the commuication pipe but they flow into the suppression chamber from the hole disposed to the bent tube. Since the coolants do not flow out to the lower portion of the dry well, important equipments such as control rod drives disposed at the lower portion of the dry wall can be prevented from submerging in water. (I.N.)

  4. Reactor monitor

    International Nuclear Information System (INIS)

    Takada, Tamotsu.

    1992-01-01

    The device of the present invention monitors a reactor so that each of the operations for the relocation of fuel assemblies and the withdrawal and the insertion of control rods upon exchange of fuel assemblies and control rods in the reactor. That is, when an operator conducts relocating operation by way of a fuel assembly operation section, the device of the present invention judges whether the operation indication is adequate or not, based on the information of control rod arrangement in a control rod memory section. When the operation indication is wrong, a stop signal is sent to a fuel assembly relocating device. Further, when the operator conducts control rod operation by way of a control rod operation section, the device of the present invention judges in the control rod withdrawal judging section, as to whether the operation indication given by the operator is adequate or not by comparing it with fuel assembly arrangement information. When the operation indication is wrong, a stop signal is sent to control rod drives. With such procedures, increase of nuclear heating upon occurrence of erroneous operation can be prevented. (I.S.)

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Matheson, J.E.

    1983-01-01

    A nuclear reactor has an upper and a lower grid plate. Protrusions project from the upper grid plate. Fuel assemblies having end fittings fit between the grid plates. An arrangement is provided for accepting axial forces generated during the operation of the nuclear reactor by the flow of the cooling medium and thermal expansion and irradiation-induced growth of the fuel assembly, which comprises rods. Each fuel assembly rests on the lower grid plate and its upper end is elastically supported against the upper grid plate by the above-mentioned arrangement. The arrangement comprises four (for example) torsion springs each having a torsion tube and a torsion bar nested within the torsion tube and connected at one end thereto. The other end of the torsion bar is connected to an associated one of four lever arms. The torsion tube is rigidly connected to the other end fitting and the springs are disposed such that the lever arms are biassed against the protrusions. (author)

  6. Reactor core fuel management

    International Nuclear Information System (INIS)

    Silvennoinen, P.

    1976-01-01

    The subject is covered in chapters, entitled: concepts of reactor physics; neutron diffusion; core heat transfer; reactivity; reactor operation; variables of core management; computer code modules; alternative reactor concepts; methods of optimization; general system aspects. (U.K.)

  7. Hybrid adsorptive membrane reactor

    Science.gov (United States)

    Tsotsis, Theodore T [Huntington Beach, CA; Sahimi, Muhammad [Altadena, CA; Fayyaz-Najafi, Babak [Richmond, CA; Harale, Aadesh [Los Angeles, CA; Park, Byoung-Gi [Yeosu, KR; Liu, Paul K. T. [Lafayette Hill, PA

    2011-03-01

    A hybrid adsorbent-membrane reactor in which the chemical reaction, membrane separation, and product adsorption are coupled. Also disclosed are a dual-reactor apparatus and a process using the reactor or the apparatus.

  8. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-11-01

    This single page document is the November 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the production reactor.

  9. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-01

    This single page document is the October 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  10. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-10-15

    This single page document is the October 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  11. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-09-15

    This single page document is the September 15, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production Reactor.

  12. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-15

    This single page document is the December 16, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  13. Reactor outage schedule (tentative)

    Energy Technology Data Exchange (ETDEWEB)

    Walton, R.P.

    1969-12-01

    This single page document is the December 1, 1969 reactor refueling outage schedule for the Hanford Production Reactor. It also contains data on the amounts and types of fuels to be loaded and relocated in the Production reactor.

  14. 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

  15. Anníbal marques da costa e a "matemática em versos e prosas": histórias da matemática na são joão del-rei do início do século XX Anníbal Marques da Costa and the "Matemática em versos e prosas": histories of mathematics in Sao João del-Rei in the early twentieth century

    Directory of Open Access Journals (Sweden)

    Romélia Mara Alves Souto

    2011-01-01

    Full Text Available Neste artigo, apresentamos os resultados de um estudo analítico-descritivo que realizamos da obra "Matemática em versos e prosas", de Anníbal Marques da Costa, encontrada no acervo do Clube Teatral Artur Azevedo, na Universidade Federal de São João del-Rei (UFSJ, em Minas Gerais. A obra é um manuscrito, em dois volumes, produzida entre 1942 e 1954, que, com explícita intenção de divulgação da matemática, embora nunca tenha sido impressa, trata de conceitos e propriedades da matemática elementar. A investigação possibilitou-nos elaborar uma descrição seguida de uma análise histórica e crítica do texto, que foi enriquecida pelo acréscimo de algumas informações sobre o autor e a época em que ele viveu.This paper presents the results of an analytical-descriptive study of the book "Matemática em versos e prosas" by Anníbal Marques da Costa, found in Clube Teatral Artur Azevedo, archives from the Universidade Federal de São João del-Rei (UFSJ, in Minas Gerais. The book has never been published and is a manuscript in two volumes produced between 1942 and 1954 aiming to promote Mathematics. It deals with the concepts and properties of elementary mathematics. The research enabled the development of a description and a historical and critical analysis of the text, enriched by some information about the author and the time he lived.

  16. 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

  17. 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.

  18. Os Fungos no Funcionamento dos Ecossistemas Florestais

    OpenAIRE

    Santos-Silva, Celeste; Machado, Helena

    2011-01-01

    Os fungos no funcionamento dos ecossistemas Florestais: Papel dos fungos sapróbios na degradação da matériaorgânica Papel dos fungos micorrízicos na nutrição e saúde das árvores Diversidade fúngica e estabilidade das florestas Relações entre os fungos e os animais Doenças radiculares associadas ao declínio do montado de sobro e azinho

  19. 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.)

  20. Das bruxas, dos índios, dos negros e dos jovens da Febem

    Directory of Open Access Journals (Sweden)

    Sylvia Leser de Mello

    2001-01-01

    Full Text Available Este artigo visa discutir os temas Pesquisa e Direitos Humanos, partindo da definição do que pretende a Ciência, suas limitações e momentos seus a serviço de condenações de bruxas e ateus. Trata-se de levantar a questão da 'parcialidade' da Ciência e das formas de exclusão que ela ajudou a gerar e manter face aos criminosos, aos loucos, aos negros e, sem dúvida, aos jovens das camadas populares que são institucionalizados na FEBEM. E, na tentativa de resistência a se deixar levar pelo que de nefasto existe na mercantilização da Ciência hoje, buscar radicalizar a exigência de defesa dos Direitos Humanos.

  1. Reactor safety

    International Nuclear Information System (INIS)

    Meneley, D.A.

    The people of Ontario have begun to receive the benefits of a low cost, assured supply of electrical energy from CANDU nuclear stations. This indigenous energy source also has excellent safety characteristics. Safety has been one of the central themes of the CANDU development program from its very beginning. A great deal of work has been done to establish that public risks are small. However, safety design criteria are now undergoing extensive review, with a real prospect of more stringent requirements being applied in the future. Considering the newness of the technology it is not surprising that a consensus does not yet exist; this makes it imperative to discuss the issues. It is time to examine the policies and practice of reactor safety management in Canada to decide whether or not further restrictions are justified in the light of current knowledge

  2. Nuclear reactor

    International Nuclear Information System (INIS)

    Schabert, H.P.; Weber, R.; Bauer, A.

    1975-01-01

    The refuelling of a PWR power reactor of about 1,200 MWe is performed by a transport pipe in the containment leading from an external to an internal fuel pit. A wagon to transport the fuel elements can go from a vertical loading position to an also vertical deloading position in the inner fuel pit via guide rollers. The necessary horizontal movement is effected by means of a cable line through the transport pipe which is inclined at least 10 0 . Gravity thus helps in the movement to the deloading position. The cable line with winch is fastened outside the containment. Swivelling devices tip the wagon from the horizontal to the vertical position or vice versa. Loading and deloading are done laterally. (TK/LH) [de

  3. Nuclear reactor

    International Nuclear Information System (INIS)

    Schweiger, F.; Glahe, E.

    1976-01-01

    In a nuclear reactor of the kind which is charged with spherical reaction elements and in which control rods are arranged to be thrust directly into the charge, each control rod has at least one screw thread on its external surface so that as the rod is thrust into the charge it is caused to rotate and thus make penetration easier. The length of each control rod may have two distinct portions, a latter portion which carries a screw thread and a lead-in portion which is shorter than the latter portion and which may carry a thread of greater pitch than that on the latter portion or may have a number of axially extending ribs instead of a thread

  4. Reactor container

    International Nuclear Information System (INIS)

    Furukawa, Hideyasu; Oyamada, Osamu; Uozumi, Hiroto.

    1976-01-01

    Purpose: To provide a container for a reactor provided with a pressure suppressing chamber pool which can prevent bubble vibrating load, particularly negative pressure generated at the time of starting to release exhaust from a main steam escape-safety valve from being transmitted to a lower liner plate of the container. Constitution: This arrangement is characterized in that a safety valve exhaust pool for main steam escape, in which a pressure suppressing chamber pool is separated and intercepted from pool water in the pressure suppressing chamber pool, a safety valve exhaust pipe is open into said safety valve exhaust pool, and an isolator member, which isolates the bottom liner plate in the pressure suppressing chamber pool from the pool water, is disposed on the bottom of the safety valve exhaust pool. (Nakamura, S.)

  5. Nuclear reactors

    International Nuclear Information System (INIS)

    Prescott, R.F.

    1976-01-01

    In the system described the fuel elements are arranged vertically in groups and are supported in such a manner as to tend to tilt them towards the center of the respective group, the fuel elements being urged laterally into abutment with one another. The elements have interlocking bearing pads, whereby lateral movement of adjacent elements is resisted; this improves the stability of the reactor core during refuelling operations. Fuel elements may comprise clusters of parallel fuel pins enclosed in a wrapper of hexagonal cross section, with bearing pads in the form of spline-like ribs located on each side of the wrapper and extending parallel to the longitudinal axis of the fuel element, being interlockable with ribs on pads of adjacent fuel elements. The arrangement is applicable to a reactor core in which fuel elements and control rod guide tubes are arranged in modules each of which comprises a cluster of at least three fuel elements, one of which is rigidly supported whilst the others are resiliently tilted towards the center of the cluster so as to lean on the rigidly supported element. It is also applicable to modules comprising a cluster of six fuel elements, each resiliently tilted towards a central void to form a circular arch. The modules may include additional fuel elements located outside the clusters and also resiliently tilted towards the central voids, the latter being used to accommodate control rod guide tubes. The need for separate structural members to act as leaning posts is thus avoided. Such structural members are liable to irradiation embrittlement, that could lead to core failure. (U.K.)

  6. 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.

  7. GERAÇÃO DE DRENAGEM ÁCIDA E DE CONTAMINAÇÃO POR METAIS PESADOS EM PERFIS DE SOLOS CONSTRUÍDOS EM ÁREA DE MINERAÇÃO DE CARVÃO

    Directory of Open Access Journals (Sweden)

    Dioni Glei Bonini Bitencourt

    2015-12-01

    reas IV e VII, apesar de proporcionar condições químicas favoráveis ao estabelecimento de culturas agrícolas, não evitaram a formação de drenagem ácida em profundidade. O processo de sulfurização e sua relação com a liberação de metais foi melhor caracterizado pela análise de componentes principais realizada nas áreas IV e VII, em razão da correlação entre pH e saturação por bases nos estéreis só se expressar em saturações por bases acima de 40 %, não observada nos materiais dos estéreis das áreas I e II.

  8. Dos generaciones de nativos digitales

    Directory of Open Access Journals (Sweden)

    Joaquín Linne

    Full Text Available A partir de encuestas, entrevistas y observaciones en la Ciudad Autónoma de Buenos Aires, afirmamos que existen dos generaciones de nativos digitales (ND: los jóvenes 1.0 y los adolescentes 2.0. Si bien ambas comparten características comunes, los 2.0 poseen rasgos propios: son una generación post-mail, suelen haberse criado alrededor de entornos digitales y manifiestan de modo online sus aspectos íntimos. Estos contenidos personales, que comparten con su grupo de pares a través de sitios de redes sociales, expresan una nueva concepción de la intimidad que podemos denominar "multimidad". A su vez, dividimos a los ND 2.0 según su nivel de alfabetización digital, condicionado por su entorno tecnológico, su capital cultural y su uso de las TIC, con el objetivo de brindar herramientas analíticas que contribuyan a mejorar las políticas públicas de inclusión digital.

  9. Um estudo comparativo sobre a classe gramatical "nome" nas gramáticas de João de Barros (1540 e de Reis Lobato (1770

    Directory of Open Access Journals (Sweden)

    Marcus Vinícius Pereira das Dores

    2016-09-01

    Full Text Available O presente artigo analisa de forma comparativa como a classe gramatical “nome” é apresentada em duas gramáticas antigas da língua portuguesa – Gramatica da Língua Portuguesa (BARROS, 1540 e A Arte da Grammatica da Língua Portuguesa (LOBATO, 1770. A gramática de Barros destinou-se à instrução dos “mininos e moços”, utilizada, assim, para ensinar a língua portuguesa como “língua mãe” e não como “madastra”, não se tratando, portanto, de uma gramática destinada aos não portugueses (BUESCU, 1983. Já a obra de Lobato foi adotada tanto em Portugal quanto, posteriormente, nas Colônias, para o ensino da língua portuguesa. Este artigo recai no que se refere ao estudo dos nomes e na observação de como é feita a classificação desses vocábulos, se se toma como base o modelo latino ou não. Explica-se a escolha dessa classe de palavra pelo fato de ambos os autores dedicarem um número considerável de páginas da sua obra para essa classe e suas subclassificações.

  10. Comparison of efficiency and reproductive aptitude indexes between a reference and field strains of the cattle tick Rhipicephalus (Boophilus microplus, in Sinaloa, Mexico Comparação dos índices de eficiência e aptidão reprodutiva entre uma cepa de referência e outra de campo do carrapato do gado, Rhipicephalus (Boophilus microplus, em Sinaloa, México

    Directory of Open Access Journals (Sweden)

    Soila Gaxiola-Camacho

    2009-12-01

    Full Text Available The objective of this work was to study the reproductive behavior of two strains of R. (B. microplus, one wild-caught (Native and one reference strain (Media Joya for two years, measuring the reproductive efficiency index (REI and reproductive aptitude index (RAI. Engorged ticks from each strain were collected monthly from February 2002 to February 2004. These were weighed and kept in the laboratory until egg-laying. Oogenic masses were individually weighed and incubated until larvae emergence. REI and RAI were calculated from each sample, grouping ticks by weight in 100 mg range classes. An analysis of variance and Duncan's multiple rank tests were carried out on the data (P O objetivo deste trabalho foi estudar a conduta reprodutiva de duas cepas de R. (B. microplus, uma coletada no campo (Nativa e outra de referência (Média Jóia, por dois anos, calculando o índice de eficiência reprodutiva (REI e o índice de aptidão reprodutiva (RAI. Foram coletados mensalmente carrapatos fêmeas engurgitadas de cada cepa no período de Fevereiro de 2002 a Fevereiro de 2004. Estas foram pesadas e conservadas no laboratório até ovipositar. As massas de ovos foram pesadas individualmente e incubadas até a eclosão das larvas. O REI e o RAI foram calculados para cada coleta, agrupando os carrapatos em classe de peso de 100 mg. Os dados foram submetidos a uma análise de variância e prova de classe múltipla de Duncan (P < 0,05. Foram calculados os coeficientes de correlação de Pearson (P < 0,01 para estimar a associação entre o peso dos carrapatos engurgitados e o peso e número de ovos postos e eclosionados. A cepa Nativa mostrou um peso ao engurgitamento mais alto do que a cepa Média Jóia. Os valores de REI e de RAI em ambas cepas foram similares em todos as classes de peso, mostrando tendência cuadrática na Média Jóia e linear-cuadrática na cepa Nativa (P < 0,05. Ambos os índices por classe de peso no engurgitamento foram sempre mais

  11. 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.)

  12. The prototype fast reactor

    International Nuclear Information System (INIS)

    Broomfield, A.M.

    1985-01-01

    The paper concerns the Prototype Fast Reactor (PFR), which is a liquid metal cooled fast reactor power station, situated at Dounreay, Scotland. The principal design features of a Fast Reactor and the PFR are given, along with key points of operating history, and health and safety features. The role of the PFR in the development programme for commercial reactors is discussed. (U.K.)

  13. 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)

  14. NCSU Reactor Sharing Program

    International Nuclear Information System (INIS)

    Perez, P.B.

    1993-01-01

    The Nuclear Reactor Program at North Carolina State University provides the PULSTAR Research Reactor and associated facilities to eligible institutions with support, in part, from the Department of Energy Reactor Sharing Program. Participation in the NCSU Reactor Sharing Program continues to increase steadily with visitors ranging from advance high school physics and chemistry students to Ph.D. level research from neighboring universities

  15. 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

  16. Self-regulating the effortful "social dos".

    Science.gov (United States)

    Cortes, Kassandra; Kammrath, Lara K; Scholer, Abigail A; Peetz, Johanna

    2014-03-01

    In the current research, we explored differences in the self-regulation of the personal dos (i.e., engaging in active and effortful behaviors that benefit the self) and in the self-regulation of the social dos (engaging in those same effortful behaviors to benefit someone else). In 6 studies, we examined whether the same trait self-control abilities that predict task persistence on personal dos would also predict task persistence on social dos. That is, would the same behavior, such as persisting through a tedious and attentionally demanding task, show different associations with trait self-control when it is framed as benefitting the self versus someone else? In Studies 1-3, we directly compared the personal and social dos and found that trait self-control predicted self-reported and behavioral personal dos but not social dos, even when the behaviors were identical and when the incentives were matched. Instead, trait agreeableness--a trait linked to successful self-regulation within the social domain--predicted the social dos. Trait self-control did not predict the social dos even when task difficulty increased (Study 4), but it did predict the social don'ts, consistent with past research (Studies 5-6). The current studies provide support for the importance of distinguishing different domains of self-regulated behaviors and suggest that social dos can be successfully performed through routes other than traditional self-control abilities. (PsycINFO Database Record (c) 2014 APA, all rights reserved).

  17. 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)

  18. 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.)

  19. 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.)

  20. Thermonuclear reactor

    International Nuclear Information System (INIS)

    Yasutomi, Yoshiyuki; Nakagawa, Moroo; Sawai, Yuichi; Chiba, Akio; Suzuki, Yasutaka.

    1997-01-01

    Silicon composited with reinforcing metals is used for a divertor cooling substrate having an effect as a cooling tube to provide a silicon base composite material having increased electric resistance and toughness. The blending ratio of reinforcing materials in the form of granules, whiskers or long fibers is controlled in order to control heat conductivity, electric resistivity and mechanical performances. The divertor cooling substrate comprising the silicon base composite material is integrated with a plasma facing material. The production method therefor includes ordinary metal matrix composite forming methods such as powder metallurgy, melting penetration method, high pressure solidification casting method, centrifugal casting method and vacuum casting method. Since the cooling plate is constituted with the light metal and highly electric resistant metal base composite material, sharing force due to eddy current can be reduced, and radiation exposure can be minimized. Accordingly, a cooling structure for a thermonuclear reactor effective for the improvement of environmental problems caused by waste disposal can be attained. (N.H.)

  1. Nuclear reactor

    International Nuclear Information System (INIS)

    Irion, L.; Tautz, J.; Ulrych, G.

    1976-01-01

    This additional patent complements the arrangement of non-return valves to prevent loss of cooling water on fracture of external tubes in the main coolant circuit (according to PS 24 24 427.7) by ensuring that the easily movable valves only operate in case of a fault, but do not flutter in operation, because the direction of flow is not the same at each location where they are installed. The remedy for this undesirable effect consists of allocating 1 non-return valve unit with 5 to 10 valves to each (of several) ducts for the cooling water intake. These units are installed in the annular space between the reactor vessel and the pressure vessel below the inlet of the ducts. Due to flow guidance surfaces in the same space, the incoming cooling water is deflected downwards and as the guiding surfaces are closed at the sides, must pass parallel to the valves of the non-return valve unit. On fracture of the external cooling water inlet pipe concerned, all valves of this unit close due to reversal of flow on the outlet side. (TK) [de

  2. Nuclear reactors

    International Nuclear Information System (INIS)

    Pearson, K.G.

    1977-01-01

    Reference is made to auxiliary means of cooling the nuclear fuel clusters used in light or heavy water cooled nuclear reactors. One method is to provide one or more spray cooling tubes. From holes in the side walls of those tubes coolant water may be sprayed laterally into the cluster against the rods. The flow of main coolant may thus be supplemented or even replaced by the auxiliary coolant. A difficulty, however, is that only those fuel rods close to a spray cooling tube can readily be reached by the auxiliary coolant. In the arrangement described, where the fuel rods are spaced apart by transverse grids, at least one of the interspaces between the grids is provided with an axially extending auxiliary coolant conduit having lateral holes through which an auxiliary coolant is sprayed into the cluster. A deflector is provided that extends from a transverse grid into a position in front of the holes and deflects auxiliary coolant on to parts of the fuel rods otherwise inaccessible to the auxiliary coolant. The construction of the deflector is described. (U.K.)

  3. 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.)

  4. 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

  5. Preservação do Patrimônio Arquitetônico e Urbano em São João Del Rei, Brasil: apontamentos sobre a atuação do Conselho Municipal de Preservação do Patrimônio Cultural .

    Directory of Open Access Journals (Sweden)

    Daniela Abritta Cota

    2012-11-01

    Full Text Available Este artigo busca refletir sobre a gestão do patrimônio arquitetônico e urbano em São João Del Rei, MG – Brasil, a partir das práticas empreendidas pelo Conselho Municipal de Preservação do Patrimônio Cultural (CMPPC, considerando a sua efetiva atuação no âmbito municipal. Inicialmente será apresentada uma reflexão teórico-conceitual sobre os condicionantes para intervenções urbanas em contextos com significativo patrimônio cultural, seguida da evolução da política patrimonial no Brasil. Posteriormente será dada ênfase ao estudo de caso de São João Del Rei.

  6. 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

  7. Os organismos geneticamente modificados e a rotulagem dos alimentos - uma análise a partir dos direitos dos consumidores

    Directory of Open Access Journals (Sweden)

    Marcello Vitor Rocha Cota

    2015-11-01

    Full Text Available Ao longo do presente trabalho serão analisados os organismos geneticamente modificados (OGMs frente aos riscos à saúde alimentar e ao meio ambiente, sobretudo o princípio da precaução e a rotulagem dos produtos. A partir de uma dimensão comparativa de três realidades distintas, isto é, a estadunidense, a europeia, com ênfase mercado ao português, e a brasileira – sob um prisma ambiental, a rotulagem dos produtos será confrontada com os direitos dos consumidores, embora em determinadas ocasiões, diante da inexistência de informações adequadas e claras dos produtos, que estão sendo ofertados e consumidos, os consumidores não sabem o que estão consumindo.

  8. Desenvolvimento e operação de reator anaeróbio de manta de lodo (UASB no tratamento dos efluentes da suinocultura em escala laboratorial Development and operation of an upflow anaerobic sludge blanket reactor (UASB treating liquid effluent from swine manure in laboratory scale

    Directory of Open Access Journals (Sweden)

    Cláudio Milton Montenegro Campos

    2006-02-01

    Full Text Available A atividade suinícola vem, desde meados da década de 70, sendo uma das mais poluidoras atividades agroindustriais no Estado de Minas Gerais. Sendo assim, objetivou-se desenvolver um Reator Anaeróbio de Manta de Lodo (UASB-Upflow Anaerobic Sludge Blanket visando tratar os dejetos produzidos com máxima eficiência dentro de um tempo e com custo reduzidos. Para tanto um experimento em escala laboratorial foi projetado e monitorado no Laboratório de Análise de Água do Departamento de Engenharia da Universidade Federal de Lavras (LAADEG, sendo composto por um Tanque de Acidificação e Equalização (TAE, um Reator Anaeróbio de Manta de Lodo e uma Lagoa Aerada Facultativa (LAF, o qual foi alimentado com fluxo contínuo. As análises físico-químicas realizadas foram: DQO, DBO5, Sólidos Totais (Fixos e Voláteis, Temperatura, pH, Nitrogênio, Fósforo, Acidez e Alcalinidade Total. O sistema proporcionou eficiência de remoção média de 93% de DQO, 84% de DBO5 e 85% de Sólidos Totais Voláteis, demonstrando adequada adaptação aos diversos tempos de detenção hidráulica adotados (55, 40, 30, 25, 18 e 15 horas. Os parâmetros adotados na partida do reator UASB foram: COV: 1,11kgDQO.m-3.d-1, COB: 0,019 kgDBO5.kgSVT-1.d-1 e TDH: 55h.The swine production, since 70th , is one of the most pollutant agro-industrial activities in the Minas Gerais State, Brazil. The objective of this research was to develop an Upflow Anaerobic Sludge Blanket Reactor (UASB, aiming at treating the effluent generated within a maximum efficiency and minimum time and cost. Therefore, a lab-scale reactor was built up and monitored in the laboratory of Engineering Department at the Federal University of Lavras (UFLA. The system consisted of an Acidification and Equalization Tank (AET, an Upflow Anaerobic Sludge Blanket reactor (UASB, and an Aerated Facultative Pond (AFP. The system was fed continuously. The physical-chemical analyses carried out were: COD, BOD5, Total

  9. 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)

  10. 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)

  11. 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

  12. 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

  13. 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.)

  14. 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.)

  15. 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

  16. A DOS Primer for Librarians: Part II.

    Science.gov (United States)

    Beecher, Henry

    1990-01-01

    Provides an introduction to DOS commands and strategies for the effective organization and use of hard disks. Functions discussed include the creation of directories and subdirectories, enhanced copying, the assignment of disk drives, and backing up the hard disk. (CLB)

  17. 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

  18. 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.

  19. Dinâmica Glacial e Características Sedimentares Resultantes na Zona Proglacial da Geleira Ecology-Baía do Almirantado, Ilha Rei George Antártica.

    Directory of Open Access Journals (Sweden)

    Kátia Kellem Rosa

    2006-12-01

    Full Text Available A geleira Ecology, localizada na ilha Rei George, ilhas Shetlands do Sul, está sofrendo um processo de rápida retração ao longo das últimas décadas, sendo que no período de 1956 a 1992/95 a geleira retrocedeu 0,37 Km2. Isto gerou um ambiente de deglaciação, com a exposição de várias geoformas na zona proglacial. Este trabalho objetiva estudar o ambiente de deglaciação da zona proglacial da geleira Ecology e seus respectivos depósitos na zona proglacial, além de inferir o regime termo-basal desta geleira. O produto resultante deste trabalho é a criação de um modelo geomorfológico para a zona proglacial da geleira, o qual pode ser usado para comparar com zonas proglaciais de outras geleiras.

  20. 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

  1. 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

  2. Fusion reactor design studies

    International Nuclear Information System (INIS)

    Emmert, G.A.; Kulcinski, G.L.; Santarius, J.F.

    1990-01-01

    This report discusses the following topics on the ARIES tokamak: systems; plasma power balance; impurity control and fusion ash removal; fusion product ripple loss; energy conversion; reactor fueling; first wall design; shield design; reactor safety; and fuel cost and resources

  3. Nuclear reactors; graphical symbols

    International Nuclear Information System (INIS)

    1987-11-01

    This standard contains graphical symbols that reveal the type of nuclear reactor and is used to design graphical and technical presentations. Distinguishing features for nuclear reactors are laid down in graphical symbols. (orig.) [de

  4. Control for nuclear reactor

    International Nuclear Information System (INIS)

    Ash, E.B.; Bernath, L.; Facha, J.V.

    1980-01-01

    A nuclear reactor is provided with several hydraulically-supported spherical bodies having a high neutron absorption cross section, which fall by gravity into the core region of the reactor when the flow of supporting fluid is shut off. (auth)

  5. Hybrid plasmachemical reactor

    Energy Technology Data Exchange (ETDEWEB)

    Lelevkin, V. M., E-mail: lelevkin44@mail.ru; Smirnova, Yu. G.; Tokarev, A. V. [Kyrgyz-Russian Slavic University (Kyrgyzstan)

    2015-04-15

    A hybrid plasmachemical reactor on the basis of a dielectric barrier discharge in a transformer is developed. The characteristics of the reactor as functions of the dielectric barrier discharge parameters are determined.

  6. Ship propulsion reactors technology

    International Nuclear Information System (INIS)

    Fribourg, Ch.

    2002-01-01

    This paper takes the state of the art on ship propulsion reactors technology. The french research programs with the corresponding technological stakes, the reactors specifications and advantages are detailed. (A.L.B.)

  7. Guidebook to nuclear reactors

    International Nuclear Information System (INIS)

    Nero, A.V. Jr.

    1976-05-01

    A general introduction to reactor physics and theory is followed by descriptions of commercial nuclear reactor types. Future directions for nuclear power are also discussed. The technical level of the material is suitable for laymen

  8. continuous stirred tank reactor (CSTR)

    African Journals Online (AJOL)

    AFRICAN JOURNALS ONLINE (AJOL) · Journals · Advanced Search ... stirred tank reactor (CSTR) and the small and large intestines as plug flow reactor (PFR) ... from the two equations are used for the reactor sizing of the modeled reactors.

  9. REDUÇÃO DOS CUSTOS DA QUALIDADE COM MELHORIA DOS PROCESSOS: UM ESTUDO DE CASO

    OpenAIRE

    Oliveira, Gabriel Rech; Universidade de Caxias do Sul; Motta, Marta Elisete Ventura; Universidade de Caxias do Sul; Camargo, Maria Emilia; Universidade de Caxias do Sul; Tondolo, Vilmar Antonio Gonçalves; Universidade Federal de Rio Grande; Zanadrea, Gabriela; Universidade de Caxias do Sul; Russo, Suzana Leitão; Universidade Federal de Sergipe

    2016-01-01

    Com o objetivo de se tornarem competitivas, as empresas impulsionam a redução dos custos dos processos que impactam diretamente no preço do produto, destacando-se os custos de qualidade. Neste cenário, a busca pela qualidade total torna-se o caminho para a sobrevivência, devido ao fato da crescente exigência dos clientes para produtos com qualidade superior e preços baixos. Dentre os principais gastos que contribuem para o aumento dos custos da qualidade destacam-se a sucata e retrabalho de p...

  10. 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)

  11. Molten salt breeder reactor

    International Nuclear Information System (INIS)

    1977-01-01

    MSBR Study Group formed in October 1974 has studied molten salt breeder reactor and its various aspects. Usage of a molten salt fuel, extremely interesting as reactor chemistry, is a great feature to MSBR; there is no need for separate fuel making, reprocessing, waste storage facilities. The group studied the following, and these results are presented: molten salt technology, molten salt fuel chemistry and reprocessing, reactor characteristics, economy, reactor structural materials, etc. (Mori, K.)

  12. Zero energy reactor 'RB'

    Energy Technology Data Exchange (ETDEWEB)

    Popovic, D; Takac, S; Markovic, H; Raisic, N; Zdravkovic, Z; Radanovic, Lj [Boris Kidric Institute of Nuclear Sciences, Vinca, Beograd (Yugoslavia)

    1959-03-15

    In 1958 the zero energy reactor RB was built with the purpose of enabling critical experiments with various reactor systems to be carried out. The first core assembly built in this reactor consists of heavy water as moderator and natural uranium metal as fuel. In order to be able to obtain very accurate results when measuring the main characteristics of the assembly the reactor was built as a completely bare system. (author)

  13. Reactor utilization, Annex A

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1984-01-01

    Reactor was operated until August 1984 due to prohibition issued by the Ministry since the reactor does not have the emergency cooling system nor special filters in the ventilation system yet. This means that the operation plan was fulfilled by 69%. This annex includes detailed tables containing data about utilization of reactor experimental channels, irradiated samples, as well as interruptions of operation. Detailed data about reactor power during this period are shown as well

  14. 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)

  15. Nuclear reactor shutdown system

    International Nuclear Information System (INIS)

    Mangus, J.D.; Cooper, M.H.

    1982-01-01

    An improved nuclear reactor shutdown system is described comprising a temperature sensitive device connected to control the electric power supply to a magnetic latch holding a body of a neutron absorbing material. The temperature sensitive device is exposed to the reactor coolant so that when the reactor coolant temperature rises above a specific level, the temperature sensitive device will cause deenergization of the magnetic latch to allow the body of neutron absorbing material to enter the reactor core. (author)

  16. 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.)

  17. Mirror fusion reactor design

    International Nuclear Information System (INIS)

    Neef, W.S. Jr.; Carlson, G.A.

    1979-01-01

    Recent conceptual reactor designs based on mirror confinement are described. Four components of mirror reactors for which materials considerations and structural mechanics analysis must play an important role in successful design are discussed. The reactor components are: (a) first-wall and thermal conversion blanket, (b) superconducting magnets and their force restraining structure, (c) neutral beam injectors, and (d) plasma direct energy converters

  18. Towards nuclear fusion reactors

    International Nuclear Information System (INIS)

    1993-11-01

    The results of nuclear fusion researches in JAERI are summarized. In this report, following themes are collected: the concept of fusion reactor (including ITER), fusion reactor safety, plasma confinement, fusion reactor equipment, and so on. Includes glossary. (J.P.N.)

  19. Rotating reactors : a review

    NARCIS (Netherlands)

    Visscher, F.; Schaaf, van der J.; Nijhuis, T.A.; Schouten, J.C.

    2013-01-01

    This review-perspective paper describes the current state-of-the-art in the field of rotating reactors. The paper has a focus on rotating reactor technology with applications at lab scale, pilot scale and industrial scale. Rotating reactors are classified and discussed according to their geometry:

  20. 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.)

  1. 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.)

  2. 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)

  3. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1981-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drivemechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displayer rods through the reactor vessel

  4. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Sherwood, D.G.; Wilson, J.F.; Salton, R.B.; Fensterer, H.F.

    1982-01-01

    A mechanical spectral shift reactor comprises apparatus for inserting and withdrawing water displacer elements from the reactor core for selectively changing the water-moderator volume in the core thereby changing the reactivity of the core. The apparatus includes drive mechanisms for moving the displacer elements relative to the core and guide mechanisms for guiding the displacer rods through the reactor vessel. (author)

  5. Produção de biogás no tratamento dos efluentes líquidos do processamento de Coffea arabica L. em reator anaeróbico UASB para o potencial aproveitamento na secagem do café Biogas production in the treatment of Coffea arabica L. processing wastewaters in UASB anaerobic reactor for the potential use in the coffee drying

    Directory of Open Access Journals (Sweden)

    Marco Antônio Calil Prado

    2008-06-01

    Full Text Available Estudou-se a produção de biogás proveniente do tratamento das águas residuárias do processamento por via úmida do café (ARC coco em sistema de tratamento anaeróbio em escala laboratorial. O sistema foi composto de um tanque de acidificação e equalização (TAE, um reator anaeróbio de manta de lodo e fluxo ascendente (UASB, uma lagoa aerada facultativa (LAF, um equalizador de pressão e um gasômetro. O tratamento foi realizado durante 190 dias e o pH foi controlado por certos períodos de tempo, pela adição de NaOH no TAE ou no reator UASB. No reator UASB, os valores máximos e mínimos obtidos na entrada foram de 235 a 7.064 mg.L-1 para DQO; 200 a 3.913 mg.L-1 para DBO5, 500 a 11.153 mg.L-1 para STV e 4,57 a 7,75 para o pH. Na saída do reator UASB, os valores foram de 39 a 2.333 mg.L-1 para DQO; 15 a 1.300 mg.L-1 para DBO5, 272 a 2.749 mg.L-1 para STV e 6,16 a 7,93 para o pH. Os valores mínimos e máximos de vazão afluente foram de 0,18 a 1,56 L.h-1. O biogás apresentou uma produção teórica de 0,545 a de 0,602 m³.kg-1DBO5 e porcentagem de metano de 48,60 a 68,14%.It was studied the biogas production through the treatment of the wet processing coffee wastewaters (ARC in an anaerobic treatment system in laboratorial scale. The system used was composed by one acidification and equalization tank (TAE, one anaerobic upflow sludge blanket reactor (UASB, one facultative aerated pond, one equalization tank and one gas tank. The treatment was carried out for 190 days and the pH was controlled for some periods by adding NaOH inside of the TAE or in the UASB. In the UASB reactor the maximum and minimum values obtained in the inlet were 235 to 7064 mg.L-1 for COD; 200 to 3913 mg.L-1 for BOD5, 500 to 11.153 mg.L-1 for TVS and 4,57 to 7,75 for pH. In the outlet of the UASB, the values were 39 to 2333 mg.L-1 for COD; 15 to 1300 mg.L-1 for BOD5, 272 to 2749 mg.L-1 for TVS and 6,16 to 7,93 for pH. The minimum and maximum values of the inlet

  6. 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)

  7. 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)

  8. 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

  9. Light water reactor safety

    CERN Document Server

    Pershagen, B

    2013-01-01

    This book describes the principles and practices of reactor safety as applied to the design, regulation and operation of light water reactors, combining a historical approach with an up-to-date account of the safety, technology and operating experience of both pressurized water reactors and boiling water reactors. The introductory chapters set out the basic facts upon which the safety of light water reactors depend. The central section is devoted to the methods and results of safety analysis. The accidents at Three Mile Island and Chernobyl are reviewed and their implications for light wate

  10. Fundamentals of reactor chemistry

    International Nuclear Information System (INIS)

    Akatsu, Eiko

    1981-12-01

    In the Nuclear Engineering School of JAERI, many courses are presented for the people working in and around the nuclear reactors. The curricula of the courses contain also the subject material of chemistry. With reference to the foreign curricula, a plan of educational subject material of chemistry in the Nuclear Engineering School of JAERI was considered, and the fundamental part of reactor chemistry was reviewed in this report. Since the students of the Nuclear Engineering School are not chemists, the knowledge necessary in and around the nuclear reactors was emphasized in order to familiarize the students with the reactor chemistry. The teaching experience of the fundamentals of reactor chemistry is also given. (author)

  11. 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

  12. The fast breeder reactor

    International Nuclear Information System (INIS)

    Davis, D.A.; Baker, M.A.W.; Hall, R.S.

    1990-01-01

    Following submission of written evidence, the Energy Committee members asked questions of three witnesses from the Central Electricity Generating Board and Nuclear Electric (which will be the government owned company running nuclear power stations after privatisation). Both questions and answers are reported verbatim. The points raised include where the responsibility for the future fast reactor programme should lie, with government only or with private enterprise or both and the viability of fast breeder reactors in the future. The case for the fast reactor was stated as essentially strategic not economic. This raised the issue of nuclear cost which has both a construction and a decommissioning element. There was considerable discussion as to the cost of building a European Fast reactor and the cost of the electricity it would generate compared with PWR type reactors. The likely demand for fast reactors will not arrive for 20-30 years and the need to build a fast reactor now is questioned. (UK)

  13. 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.)

  14. Reactor power control device

    International Nuclear Information System (INIS)

    Ishii, Yoshihiko; Arita, Setsuo; Miyamoto, Yoshiyuki; Fukazawa, Yukihisa; Ishii, Kazuhiko

    1998-01-01

    The present invention provides a reactor power control device capable of enhancing an operation efficiency while keeping high reliability and safety in a BWR type nuclear power plant. Namely, the device of the present invention comprises (1) a means for inputting a set value of a generator power and a set value of a reactor power, (2) a means for controlling the reactor power to either smaller one of the reactor power corresponding to the set value of the generator power and the set value of the reactor power. With such procedures, even if the nuclear power plant is set so as to operate it to make the reactor power 100%, when the generator power reaches the upper limit, the reactor power is controlled with a preference given to the upper limit value of the generator power. Accordingly, safety and reliability are not deteriorated. The operation efficiency of the plant can be improved. (I.S.)

  15. Reactor power monitoring device

    International Nuclear Information System (INIS)

    Dogen, Ayumi; Ozawa, Michihiro.

    1983-01-01

    Purpose: To significantly improve the working efficiency of a nuclear reactor by reflecting the control rod history effect on thermal variants required for the monitoring of the reactor operation. Constitution: An incore power distribution calculation section reads the incore neutron fluxes detected by neutron detectors disposed in the reactor to calculate the incore power distribution. A burnup degree distribution calculation section calculates the burnup degree distribution in the reactor based on the thus calculated incore power distribution. A control rod history date store device supplied with the burnup degree distribution renews the stored control rod history data based on the present control rod pattern and the burnup degree distribution. Then, thermal variants of the nuclear reactor are calculated based on the thus renewed control rod history data. Since the control rod history effect is reflected on the thermal variants required for the monitoring of the reactor operation, the working efficiency of the nuclear reactor can be improved significantly. (Seki, T.)

  16. The Maple reactor project

    International Nuclear Information System (INIS)

    Malkoske, G.R.; Labrie, J.-P.

    2003-01-01

    MDS Nordion supplies the majority of the world's reactor-produced medical isotopes. These isotopes are currently produced in the NRU reactor at AECL's Chalk River Laboratories (CRL). Medical isotopes and related technology are relied upon around the world to prevent, diagnose and treat disease. The NRU reactor, which has played a key role in supplying medical isotopes to date, has been in operation for over 40 years. Replacing this aging reactor has been a priority for MDS Nordion to assure the global nuclear medicine community that Canada will continue to be a dependable supplier of medical isotopes. MDS Nordion contracted AECL to construct two MAPLE reactors dedicated to the production of medical isotopes. The MDS Nordion Medical Isotope Reactor (MMIR) project started in September 1996. This paper describes the MAPLE reactors that AECL has built at its CRL site, and will operate for MDS Nordion. (author)

  17. 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

  18. O legado dos desenhadores da guerra

    OpenAIRE

    Almeida, Reginaldo Rodrigues de

    2017-01-01

    O comportamento que causa dano ou prejuízo moral é um comportamento violento, logo temido. Porém, não se foge dele, antes se procura.Verifica-se uma avidez global em busca de imagens,sejam fotografias ou vídeos, tendo a fotografia do interior da casa de espectáculos parisiense Le Bataclan, com os cadáveres dos reféns,ainda que pouco perceptível, sido vista até à exaustão, na sequência dos ataque terroristas dodia 13 de Novembro de 2015 em Paris.

  19. 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.

  20. 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

  1. An alternative nuclear program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1981-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is nor capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  2. Alternative Nuclear Program

    International Nuclear Information System (INIS)

    Goldemberg, J.

    1982-01-01

    An analysis of the development of nuclear energy in Brazil is made since its beginning, showing the fundamental policy changes introduced in the end of the 60's with the purchase of the Angra dos Reis I reactor. This decision discouraged the existing efforts of an autonomous development in nuclear energy. The reaction to this policy led to the Nuclear Deal with Germany, which although incorporating some positive aspects is not capable to lead to nuclear independence. The presently existing options are discussed, as well as the transformation of the Nuclear Program in a R and D Program based only in the reactors I, II and III, located in Angra dos Reis. (Author) [pt

  3. 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

  4. 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.)

  5. 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)

  6. 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.

  7. Editorial. Kultūros reiškiniai šiuolaikinių informacijos ir komunikacijos technologijų sąlygomis: nuo meno ir televizijos iki politikos

    Directory of Open Access Journals (Sweden)

    Jovilė Barevičiūtė

    2015-10-01

    Full Text Available Šiame žurnalo numeryje aptariami kai kurie daugiaaspekčiai šiuolaikinės kultūros reiškiniai, apimant tokius jų, kaip menas, televizija, politika ir kt. Medijos ir komunikacija nūdien intensyviai skverbiasi kone į visas darbo ir laisvalaikio veiklos, viešojo ir privataus sektorių sritis, reprezentuodamos dinamišką ir netolygią gyvenamojo pasaulio tikrovę. Medijuotoji komunikacija vis labiau tampa dominuojančia socializacijos forma, ji išstumia gyvąją komunikaciją: kuo toliau, tuo labiau šis reiškinys nusako ne tik jaunimo, bet ir brandaus amžiaus žmonių šiandienį bendravimo būdą. Tad akivaizdu, kad XXI a. žmogus vis labiau pasineria į įvairių medijų tinklus, apraizgančius jo gyvenimą ir tampančius pagrindine socialios ir visavertės eg zistencijos sąlyga. Tokios socialinės institucijos, kaip menas, televizija, politika, religija, šeima ir daugelis kitų, nūdien jau nebėra tokios savarankiškos, kaip, tarkime, prieš dešimt, dvidešimt ar daugiau metų. Jų suverenitetą daugiausia transformuoja būtent medijos, šioms institucijoms diktuojančios savas sąlygas ir primetančios savas taisykles. Kitaip tariant, medijos tampa tokios galingos, kad ima steigti savuosius dėsnius, kuriems vis labiau paklūsta tradicinė gyvosios socializacijos aplinka. Taip kyla daugybė diskutuotinų ir ginčytinų klausimų, paliečiančių socialinių institucijų apibrėžties, autonomijos ir suvereniteto aspektus. Šiuos aspektus iš įvairių perspektyvų gvildena ir šio numerio autoriai. Eugenija Krukauskienė ir Viktorija Žilinskaitė-Vytienė savo straipsnyje aptaria kultūros vartojimo klausimus tirdamos, kaip šiuolaikinio lietuviškojo kino meno pavyzdžius suvokia ir vertina tam tikrų amžiaus kategorijų jaunimas. Algis Mickūnas gilinasi į filosofinius šiuolaikinių diskursų klausimus, pasirinkdamas kūniškumo, lytėjimo ir taktilikos aspektus, glaudžiai susijusius su medijuotosios komunikacijos tema

  8. 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

  9. A Teoria dos Conjuntos de Cantor

    Directory of Open Access Journals (Sweden)

    Antônio Acra Freiria

    1992-07-01

    Full Text Available No final dos anos 50 e começo doe anos 60, houve uma reformulação significativa da Matemática no Brasil. Sob a bandeira do modernismo, seus defensores buscaram inovações no ensino da Matemática. Dessa forma, os reformistas se concentraram essencialmente na linguagem abusiva e no formalismo da Teoria dos Conjuntos, o que trouxe mais danos do que benefícios do ensino da Matemática de 1º e 2ºgraus. A linguagem formal da Teoria dos Conjuntos é porém sua parte menos importante. A teoria criada por Cantor tão logo revelou-se como o fundamento de toda a Matemática, possibilitando o desenvolvimento de novas disciplinas, como a Topologia, a Algebra Abstrata, a Teoria da Medida e Integração, a Teoria da Probabilidade e a Análise Funcional. O objetivo deste trabalho é um relato sucinto de como surgiu essa teoria, apresentando o "Conjunto de Cantor" como um dos mais ricos exemplos de "Conjunto perfeito" encontrados na literatura matemática.

  10. Uso de detectores de neutrinos para el monitoreo de reactores nucleares Uso de detectores de neutrinos para el monitoreo de reactores nucleares

    Directory of Open Access Journals (Sweden)

    Gerardo Moreno

    2012-02-01

    Full Text Available Se estudia la factibilidad del uso de los detectores de antineutrinos para el monitoreo de reactores nucleares. Usando un modelo sencillo de cascada de fisión a dos componentes, se ilustra la dependencia del número de antineutrinos detectados a una distancia L del reactor según la composición nuclear del combustible. Se explica el principio de detección de neutrinos de reactores en base al decaimiento beta inverso y se describe como los detectores de neutrinos pueden emplearse para el monitoreo de la producción de materiales fisibles en el reactor. Se comenta como generalizar este análisis al caso real de un reactor nuclear in situ y uno de los principales experimentos internacionales dedicados a este propósito. We study the feasibility to use antineutrinos detectors for monitoring of nuclear reactors. Using a simple model of fission shower with two components, we illustrate how the numbers of antineutrinos detected at a distance L from the reactor depend on the composition of the nuclear combustible. We explain the principles of reactor neutrino detection using inverse beta decays and we describe how neutrinos detectors can be used for monitoring the production of fissile materials within the reactors. We comment how to generalize this analysis to the realistic case of a nuclear reactor in situ and one of the main international experiments dedicated to study the use of neutrinos detectors as nuclear safeguards.

  11. 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

  12. TRIGA reactor main systems

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the main systems of low power (<2 MW) and higher power (≥2 MW) TRIGA reactors. The most significant difference between the two is that forced reactor cooling and an emergency core cooling system are generally required for the higher power TRIGA reactors. However, those TRIGA reactors that are designed to be operated above 3 MW also use a TRIGA fuel that is specifically designed for those higher power outputs (3 to 14 MW). Typical values are given for the respective systems although each TRIGA facility will have unique characteristics that may only be determined by the experienced facility operators. Due to the inherent wide scope of these research reactor facilities construction and missions, this training module covers those systems found at most operating TRIGA reactor facilities but may also discuss non-standard equipment that was found to be operationally useful although not necessarily required. (author)

  13. 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...

  14. Upgradation of Apsara reactor

    International Nuclear Information System (INIS)

    Mammen, S.; Mukherjee, P.; Bhatnagar, A.; Sasidharan, K.; Raina, V.K.

    2009-01-01

    Apsara is a 1 MW swimming pool type research reactor using high enriched uranium as fuel with light water as coolant and moderator. The reactor is in operation for more than five decades and has been extensively used for basic research, radioisotope production, neutron radiography, detector testing, shielding experiments etc. In view of its long service period, it is planned to carry out refurbishment of the reactor to extend its useful life. During refurbishment, it is also planned to upgrade the reactor to a 2 MW reactor to improve its utilization and to upgrade the structure, system and components in line with the current safety standards. This paper gives a brief account of the design features and safety aspects of the upgraded Apsara reactor. (author)

  15. Solubilidade e disponibilidade dos micronutrientes em fertilizantes

    Directory of Open Access Journals (Sweden)

    F. Vale

    1999-06-01

    Full Text Available A legislação brasileira exige que os micronutrientes nos fertilizantes sejam garantidos pelo teor total presente. Isto abre um precedente para a utilização de produtos não considerados como fontes de micronutrientes na fabricação dos fertilizantes. Todavia, a eficiência agronômica desses produtos é ainda duvidosa. Objetivou-se realizar um trabalho para caracterizar a solubilidade e a disponibilidade dos micronutrientes em trinta fertilizantes comerciais, por meio do uso de cinco extratores químicos: a água e soluções de ácido cítrico a 2%, de citrato neutro de amônio na diluição 1 + 9, de DTPA 0,005 mol L-1 e de EDTA 0,005 mol L-1. Os resultados mostraram a baixa solubilidade dos micronutrientes metálicos (cobre, ferro, manganês e zinco dos fertilizantes tipo "fritas". O ácido cítrico a 2% mostrou-se promissor na caracterização da disponibilidade de cobre, manganês e zinco para as plantas. Para o ferro não houve uma definição entre os extratores estudados. O boro teve boa solubilidade, tanto nos fertilizantes solúveis, como nos insolúveis em água, e a garantia pelo teor total mostrou-se bom indicativo da disponibilidade do elemento. Para o molibdênio a solubilidade foi maior para os fertilizantes com baixo teor do elemento. A garantia dos micronutrientes catiônicos pelo teor total, conforme exige a legislação, não indicou a sua real disponibilidade nos fertilizantes comerciais, mostrando a necessidade de uma definição de extratores para esse fim.

  16. 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)

  17. 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

  18. 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)

  19. 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)

  20. Power reactors operational diagnosis

    International Nuclear Information System (INIS)

    Dach, K.; Pecinka, L.

    1976-01-01

    The definition of reactor operational diagnostics is presented and the fundamental trends of research are determined. The possible sources of power reactor malfunctions, the methods of defect detection, the data evaluation and the analysis of the results are discussed in detail. In view of scarcity of a theoretical basis and of insufficient in-core instrumentation, operational diagnostics cannot be as yet incorporated in a computer-aided reactor control system. (author)

  1. Fast reactors worldwide

    International Nuclear Information System (INIS)

    Hall, R.S.; Vignon, D.

    1985-01-01

    The paper concerns the evolution of fast reactors over the past 30 years, and their present status. Fast reactor development in different countries is described, and the present position, with emphasis on cost reduction and collaboration, is examined. The French development of the fast breeder type reactor is reviewed, and includes: the acquisition of technical skills, the search for competitive costs and the spx2 project, and more advanced designs. Future prospects are also discussed. (U.K.)

  2. Pressurised water reactor operation

    International Nuclear Information System (INIS)

    Birnie, S.; Lamonby, J.K.

    1987-01-01

    The operation of a pressurized water reactor (PWR) is described with respect to the procedure for a unit start-up. The systems details and numerical data are for a four loop PWR station of the design proposed for Sizewell-'B', United Kingdom. A description is given of: the initial conditions, filling the reactor coolant system (RCS), heat-up and pressurisation of the RCS, secondary system preparations, reactor start-up, and reactivity control at power. (UK)

  3. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    1998-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of four main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents, the development of an expert system for the aid to diagnosis; the development and application of a probabilistic reactor dynamics method. Main achievements in 1999 are reported

  4. Seals in nuclear reactors

    International Nuclear Information System (INIS)

    1979-01-01

    The aim of this invention is the provision of improved seals for reactor vessels in which fuel assemblies are located together with inlets and outlets for the circulation of a coolant. The object is to provide a seal arrangement for the rotatable plugs of nuclear reactor closure heads which has good sealing capacities over a wide gap during operation of the reactor but which also permits uninhibited rotation of the plugs for maintenance. (U.K.)

  5. Reactor BR2

    Energy Technology Data Exchange (ETDEWEB)

    Gubel, P

    2000-07-01

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

  6. The Dragon reactor experiment

    International Nuclear Information System (INIS)

    Anon.

    1976-01-01

    The concept on which the Dragon Reactor Experiment was based was evolved at the Atomic Energy Research Establishment at Harwell in 1956, and in February of that year a High Temperature Gas- cooled Reactor Project Group was set up to study the feasibility of a helium-cooled reactor with a graphite or beryllium moderator, and with the emphasis on the thorium fuel cycle [af

  7. The replacement research reactor

    International Nuclear Information System (INIS)

    Cameron, R.

    1999-01-01

    As a consequences of the government decision in September 1997. ANSTO established a replacement research reactor project to manage the procurement of the replacement reactor through the necessary approval, tendering and contract management stages This paper provides an update of the status of the project including the completion of the Environmental Impact Statement. Prequalification and Public Works Committee processes. The aims of the project, management organisation, reactor type and expected capabilities are also described

  8. TRIGA reactor characteristics

    International Nuclear Information System (INIS)

    Boeck, H.; Villa, M.

    2007-01-01

    This module describes the general design, characteristics and parameters of TRIGA reactors and fuels. It is recommended that most of this information should be incorporated into any reactor operator training program and, in many cases, the facility Safety Analysis Report. It is oriented to teach the basics of the physics and mechanical design of the TRIGA fuel as well as its unique operational characteristics and the differences between TRIGA fuels and others more traditional reactor fuels. (nevyjel)

  9. Integral fast reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1989-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. 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. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics

  10. Reactor BR2

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

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

  11. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Chang, Y.I.

    1988-01-01

    The Integral Fast Reactor (IFR) is an innovative liquid metal reactor concept being developed at Argonne National Laboratory. 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. This paper describes the key features and potential advantages of the IFR concept, with emphasis on its safety characteristics. 3 refs., 4 figs., 1 tab

  12. The CONNIE experiment

    Energy Technology Data Exchange (ETDEWEB)

    Aguilar-Arevalo, A.; et al.

    2016-10-19

    The CONNIE experiment uses fully depleted, high resistivity CCDs as particle detectors in an attempt to measure for the first time the Coherent Neutrino-Nucleus Elastic Scattering of antineutrinos from a nuclear reactor with silicon nuclei.This talk, given at the XV Mexican Workshop on Particles and Fields (MWPF), discussed the potential of CONNIE to perform this measurement, the installation progress at the Angra dos Reis nuclear power plant, as well as the plans for future upgrades.

  13. Soil sampling in emergency situations; Amostragem de solos em situacoes de emergencia

    Energy Technology Data Exchange (ETDEWEB)

    Carvalho, Zenildo Lara de [Instituto de Radioprotecao e Dosimetria (IRD), Rio de Janeiro, RJ (Brazil); Ramos Junior, Anthenor Costa [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil). Superintendencia de Licenciamento e Controle

    1997-12-31

    The soil sampling methods used in Goiania`s accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author) 15 refs.

  14. Influence of marine sediments in the distribution of the main radionuclides of the effluent from the nuclear power plant Almirante Alvaro Alberto (Unit 1)

    International Nuclear Information System (INIS)

    Brugnara, Miriam

    1977-01-01

    This study aimed to: 1) Characterize bottom sediments of the Angra dos Reis region, in the dispersion area of the effluent of the central Almirante Nuclear Alvaro Alberto, Unit 1. 2) Determining the adsorption capacity of these sediments to the long half-life and mean radionuclides to be released in the reactor effluent in a higher concentration. 3) Estimate the fraction of the different studied radionuclides that will be immobilized in sediments. 4) Identify critical radionuclides available for food chain

  15. Soil sampling in emergency situations

    International Nuclear Information System (INIS)

    Carvalho, Zenildo Lara de; Ramos Junior, Anthenor Costa

    1997-01-01

    The soil sampling methods used in Goiania's accident (1987) by the environmental team of Brazilian Nuclear Energy Commission (CNEN) are described. The development of this method of soil sampling to a emergency sampling method used in a Nuclear Emergency Exercise in Angra dos Reis Reactor Site (1991) is presented. A new method for soil sampling based on a Chernobyl environmental monitoring experience (1995) is suggested. (author)

  16. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Anon.

    1978-01-01

    Conceptual design studies were made of fusion reactors based on the three current mirror-confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fuel for fission reactors. We have designed a large commercial hybrid and a small pilot-plant hybrid based on standard mirror confinement. Tandem mirror designs include a commercial 1000-MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single-cell pilot plant

  17. HOMOGENEOUS NUCLEAR POWER REACTOR

    Science.gov (United States)

    King, L.D.P.

    1959-09-01

    A homogeneous nuclear power reactor utilizing forced circulation of the liquid fuel is described. The reactor does not require fuel handling outside of the reactor vessel during any normal operation including complete shutdown to room temperature, the reactor being selfregulating under extreme operating conditions and controlled by the thermal expansion of the liquid fuel. The liquid fuel utilized is a uranium, phosphoric acid, and water solution which requires no gus exhaust system or independent gas recombining system, thereby eliminating the handling of radioiytic gas.

  18. Australian research reactor studies

    International Nuclear Information System (INIS)

    McCulloch, D.B.

    1978-01-01

    The Australian AEC has two research reactors at the Lucas Heights Research Establishment, a 10 HW DIDO class materials testing reactor, HIFAR, and a smaller 100kW reactor MOATA, which was recently upgraded from 10kW power level. Because of the HIFAR being some 20 years old, major renewal and repair programmes are necessary to keep it operational. To enable meeting projected increases in demand for radioisotopes, plans for a new reactor to replace the HIFAR have been made and the design criteria are described in the paper. (author)

  19. Mirror fusion reactors

    International Nuclear Information System (INIS)

    Carlson, G.A.; Moir, R.W.

    1978-01-01

    We have carried out conceptual design studies of fusion reactors based on the three current mirror confinement concepts: the standard mirror, the tandem mirror, and the field-reversed mirror. Recent studies of the standard mirror have emphasized its potential as a fusion-fission hybrid reactor, designed to produce fission fuel for fission reactors. We have designed a large commercial hybrid based on standard mirror confinement, and also a small pilot plant hybrid. Tandem mirror designs include a commercial 1000 MWe fusion power plant and a nearer term tandem mirror hybrid. Field-reversed mirror designs include a multicell commercial reactor producing 75 MWe and a single cell pilot plant

  20. 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.)

  1. 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.

  2. Fusion Reactor Materials

    International Nuclear Information System (INIS)

    Decreton, M.

    2002-01-01

    The objective of SCK-CEN's programme on fusion reactor materials is to contribute to the knowledge on the radiation-induced behaviour of fusion reactor materials and components as well as to help the international community in building the scientific and technical basis needed for the construction of the future reactor. Ongoing projects include: the study of the mechanical and chemical (corrosion) behaviour of structural materials under neutron irradiation and water coolant environment; the investigation of the characteristics of irradiated first wall material such as beryllium; investigations on the management of materials resulting from the dismantling of fusion reactors including waste disposal. Progress and achievements in these areas in 2001 are discussed

  3. Trench reactor: an overview

    International Nuclear Information System (INIS)

    Spinrad, B.I.; Rohach, A.F.; Razzaque, M.M.; Sankoorikal, J.T.; Schmidt, R.S.; Lofshult, J.; Ramin, T.; Sokmen, N.; Lin, L.C.

    1988-01-01

    Recent fast, sodium-cooled reactor designs reflect new conditions. In nuclear energy these conditions are (a) emphasis on maintainability and operability, (b) design for more transparent safety, and (c) a surplus of uranium and enrichment availability that eases concerns about light water reactor fueling costs. In utility practice the demand is for less capital exposure, short construction time, smaller new unit sizes, and low capital cost. The PRISM, SAFR, and integral fast reactor (IFR) concepts are responses to these conditions. Fast reactors will not soon be deployed commercially, so more radical designs can be considered. The trench reactor is the product of such thinking. Its concepts are intended as contributions to the literature, which may be picked up by one of the existing programs or used in a new experimental project. The trench reactor is a thin-slab, pool-type reactor operated at very low power density and- for sodium-modest temperature. The thin slab is repeated in the sodium tank and the reactor core. The low power density permits a longer than conventional core height and a large-diameter fuel pin. Control is by borated steel slabs that can be lowered between the core and lateral sodium reflector. Shutdown is by semaphore slabs that can be swung into place just outside the control slabs. The paper presents major characteristics of the trench reactor that have been changed since the last report

  4. 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

  5. Advanced CANDU reactors

    International Nuclear Information System (INIS)

    Dunn, J.T.; Finlay, R.B.; Olmstead, R.A.

    1988-12-01

    AECL has undertaken the design and development of a series of advanced CANDU reactors in the 700-1150 MW(e) size range. These advanced reactor designs are the product of ongoing generic research and development programs on CANDU technology and design studies for advanced CANDU reactors. The prime objective is to create a series of advanced CANDU reactors which are cost competitive with coal-fired plants in the market for large electricity generating stations. Specific plant designs in the advanced CANDU series will be ready for project commitment in the early 1990s and will be capable of further development to remain competitive well into the next century

  6. Mechanical spectral shift reactor

    International Nuclear Information System (INIS)

    Doshi, P.K.; George, R.A.; Dollard, W.J.

    1982-01-01

    A mechanical spectral shift arrangement for controlling a nuclear reactor includes a plurality of reactor coolant displacer members which are inserted into a reactor core at the beginning of the core life to reduce the volume of reactor coolant-moderator in the core at start-up. However, as the reactivity of the core declines with fuel depletion, selected displacer members are withdrawn from the core at selected time intervals to increase core moderation at a time when fuel reactivity is declining. (author)

  7. Nuclear reactor safety systems

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1980-01-01

    A safety system for shutting down a nuclear reactor under overload conditions is described. The system includes a series of parallel-connected computer memory type look-up tables each of which receives data on a particular reactor parameter and in each of which a precalculated functional value for that parameter is stored indicative of the percentage of maximum reactor load that the parameter contributes. The various functional values corresponding to the actual measured parameters are added together to provide a control signal used to shut down the reactor under overload conditions. (U.K.)

  8. RA Reactor; Reaktor RA

    Energy Technology Data Exchange (ETDEWEB)

    NONE

    1978-02-15

    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. [Serbo-Croat] Pored osnovnih karakeristika reaktora RA, organizacije rada i finansijskih pokazatelja, razmatra se stanje opreme reaktora nakon 18 godina rada, pitanja dozvole za rad sa 80% obogacenim gorivom, problem skladistenja isluzenog goriva u bazenu zgrade reaktora i potreba za obnavljanjem komponenti opreme, pre svega elektronske.

  9. Nuclear reactor internals arrangement

    International Nuclear Information System (INIS)

    Frisch, E.; Andrews, H.N.

    1976-01-01

    A nuclear reactor internals arrangement is disclosed which facilitates reactor refueling. A reactor vessel and a nuclear core is utilized in conjunction with an upper core support arrangement having means for storing withdrawn control rods therein. The upper core support is mounted to the underside of the reactor vessel closure head so that upon withdrawal of the control rods into the upper core support, the closure head, the upper core support and the control rods are removed as a single unit thereby directly exposing the core for purposes of refueling

  10. Multi purpose research reactor

    International Nuclear Information System (INIS)

    Raina, V.K.; Sasidharan, K.; Sengupta, Samiran; Singh, Tej

    2006-01-01

    At present Dhruva and Cirus reactors provide the majority of research reactor based facilities to cater to the various needs of a vast pool of researchers in the field of material sciences, physics, chemistry, bio sciences, research and development work for nuclear power plants and production of radio isotopes. With a view to further consolidate and expand the scope of research and development in nuclear and allied sciences, a new 20 MWt multi purpose research reactor is being designed. This paper describes some of the design features and safety aspects of this reactor

  11. 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.)

  12. 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.)

  13. Farewell to a reactor

    International Nuclear Information System (INIS)

    Skanborg, P.

    1976-01-01

    Denmark's second reactor, DR 2, whose first criticality took place the night of 18/19 December 1958 was shut down for the last time on 31 October 1975. It was a light-water moderrated and cooled reactor of swimming-pool type with a thermal power of 5 MW, using 90% enriched uranium. The operation is described. The reactor and auxiliary equipment are now being put 'in store' - all fuel elements sent for reprocessing, the reactor tank and cooling circuits emptied, and a lead shielding placed over the tank opening. The rest of the equipment will remain in place. (B.P.)

  14. Indian advanced nuclear reactors

    International Nuclear Information System (INIS)

    Saha, D.; Sinha, R.K.

    2005-01-01

    For sustainable development of nuclear energy, a number of important issues like safety, waste management, economics etc. are to be addressed. To do this, a number of advanced reactor designs as well as fuel cycle technologies are being pursued worldwide. The advanced reactors being developed in India are the AHWR and the CHTR. Both the reactors use thorium based fuel and have many passive features. This paper describes the Indian advanced reactors and gives a brief account of the international initiatives for the sustainable development of nuclear energy. (author)

  15. 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.)

  16. 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

  17. FFTF reactor assembly system technology

    International Nuclear Information System (INIS)

    Mangelsdorf, T.A.

    1975-01-01

    An overview is presented of the FFTF reactor and plant together with descriptions of core components, core internals, core system, primary and secondary control rod system, reactor instrumentation, reactor vessel and closure head, and supporting test programs

  18. As armas dos cristãos

    Directory of Open Access Journals (Sweden)

    Angelica Hoffler

    2002-01-01

    Full Text Available In this paper, we analyse Juazeiro do Norte particularly considering the belief that the End do the World is about to happen and the need of having their sins forgiven, Man, pilgrim in this world, takes advantage of the weapons offered by the Holy Writ and by the Compassion Books to fight against the eternal enemy. They are: the alms, the fasting, the prayer, the humiliation. / Diante da crença na iminência do Fim dos Tempos e da necessidade de remissão dos pecados, o Homem, peregrino sobre este mundo vale-se das armas que lhe são fornecidads pelas Escrituras e pelos Manuais de Piedade para combater o inimigo eterno. São elas: a esmola, o jejum, a oração, a mortificação.

  19. Reactor building for a nuclear reactor

    International Nuclear Information System (INIS)

    Haidlen, F.

    1976-01-01

    The invention concerns the improvement of the design of a liner, supported by a latticed steel girder structure and destined for guaranteeing a gastight closure for the plant compartments in the reactor building of a pressurized water reactor. It is intended to provide the steel girder structure on their top side with grates, being suited for walking upon, and to hang on their lower side diaphragms in modular construction as a liner. At the edges they may be sealed with bellows in order to avoid thermal stresses. The steel girder structure may at the same time serve as supports for parts of the steam pipe. (RW) [de

  20. Revitalization of reactor usage through reactor sharing

    International Nuclear Information System (INIS)

    Vernetson, W.G.

    1986-01-01

    The purpose of this work was to renew interest in using the University Florida Training Reactor (UFTR) for educational and training purposes outside the Nuclear Engineering Sciences (NES) and Environmental Engineering Sciences (EES) Departments at the University of Florida and for research by others outside the NES Department. The availability of the UFTR made possible through a US Department of Energy (DOE) Reactor Sharing Grant provided the mechanism to pursue generation of renewed interest at all levels both within the University of Florida and from other educational and corporate institutions

  1. Reactor coolant pump for a nuclear reactor

    International Nuclear Information System (INIS)

    Burkhardt, W.; Richter, G.

    1976-01-01

    An improvement is proposed concerning the easier disengagement of the coupling at the reactor coolant pump for a nuclear reactor transporting a pressurized coolant. According to the invention the disengaging coupling consists of two parts separated by screws. At least one of the screws contains a propellent charge ananged within a bore and provided with a speed-dependent ignition device in such a way that by separation of the screws at overspeeds the coupling is disengaged. The sub-claims are concerned with the kind of ignition ot the propellent charge. (UWI) [de

  2. The fusion reactor

    International Nuclear Information System (INIS)

    Brennan, M.H.

    1974-01-01

    Basic principles of the fusion reactor are outlined. Plasma heating and confinement schemes are described. These confinement systems include the linear Z pinch, magnetic mirrors and Tokamaks. A fusion reactor is described and a discussion is given of its environmental impact and its fuel situation. (R.L.)

  3. Molten salt reactor concept

    International Nuclear Information System (INIS)

    Sood, D.D.

    1980-01-01

    Molten salt reactor is an advanced breeder concept which is suited for the utilization of thorium for nuclear power production. This reactor is based on the use of solutions of uranium or plutonium fluorides in LiF-BeF 2 -ThF 4 as fuel. Unlike the conventional reactors, no external coolant is used in the reactor core and the fuel salt itself is circulated through heat exchangers to transfer the fission produced heat to a secondary salt (NaF-NaBF 4 ) for steam generation. A part of the fuel stream is continuously processed to isolate 233 Pa, so that it can decay to fissile 233 U without getting converted to 234 Pa, and for the removal of neutron absorbing fission products. This on-line processing scheme makes this reactor concept to achieve a breeding ratio of 1.07 which is the highest for any thermal breeder reactor. Experimental studies at the Bhabha Atomic Research Centre, Bombay, have established the use of plutonium as fuel for this reactor. This molten salt reactor concept is described and the work conducted at the Bhabha Atomic Research Centre is summarised. (auth.)

  4. The heavy water reactors

    International Nuclear Information System (INIS)

    Brudermueller, G.

    1976-01-01

    This is a survey of the development so far of this reactor line which is in operation all over the world in various types (e.g. BHWR, PHWR). MZFR and the CANDU-type reactors are discussed in more detail. (UA) [de

  5. 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.)

  6. Osiris reactor descriptive report

    International Nuclear Information System (INIS)

    1976-03-01

    OSIRIS is a swimming pool reactor of 70 MW thermal power. Its main purpose is the irradiation of reactor materials in high neutron flux. A description is given of the air conditioning, ventilation, and radioactive gas removal system. (R.L.)

  7. 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.)

  8. Mirror hybrid reactor studies

    International Nuclear Information System (INIS)

    Bender, D.J.

    1978-01-01

    The hybrid reactor studies are reviewed. The optimization of the point design and work on a reference design are described. The status of the nuclear analysis of fast spectrum blankets, systems studies for fissile fuel producing hybrid reactor, and the mechanical design of the machine are reviewed

  9. Reactor Safety Analysis

    International Nuclear Information System (INIS)

    Arien, B.

    2000-01-01

    The objective of SCK-CEN's programme on reactor safety is to develop expertise in probabilistic and deterministic reactor safety analysis. The research programme consists of two main activities, in particular the development of software for reliability analysis of large systems and participation in the international PHEBUS-FP programme for severe accidents. Main achievements in 1999 are reported

  10. The Integral Fast Reactor

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Lineberry, M.J.

    1990-01-01

    Argonne National Laboratory, since 1984, has been developing the Integral Fast Reactor (IFR). This paper will describe the way in which this new reactor concept came about; the technical, public acceptance, and environmental issues that are addressed by the IFR; the technical progress that has been made; and our expectations for this program in the near term. 5 refs., 3 figs

  11. Gas-cooled reactors

    International Nuclear Information System (INIS)

    Vakilian, M.

    1977-05-01

    The present study is the second part of a general survey of Gas Cooled Reactors (GCRs). In this part, the course of development, overall performance and present development status of High Temperature Gas Cooled Reactors (HTCRs) and advances of HTGR systems are reviewed. (author)

  12. A nuclear power reactor

    International Nuclear Information System (INIS)

    Borrman, B.E.; Broden, P.; Lundin, N.

    1979-12-01

    The invention consists of shock absorbing support beams fastened to the underside of the reactor tank lid of a BWR type reactor, whose purpose is to provide support to the steam separator and dryer unit against accelerations due to earthquakes, without causing undue thermal stresses in the unit due to differential expansion. (J.I.W.)

  13. International thermal reactor development

    International Nuclear Information System (INIS)

    Zebroski, E.L.

    1977-01-01

    The worldwide development of nuclear power plants is reviewed. Charts are presented which show the commitment to light-water reactor capacity construction with breakdown by region and country. Additional charts show the major nuclear research centers which have substantial scope in light water reactor development and extensive international activities

  14. Thermal reactor strategy

    International Nuclear Information System (INIS)

    1981-01-01

    This statement sets down briefly the CEGB's views on the requirement for nuclear power and outlines current progress in the implementation of the CEGB's thermal reactor strategy. The programme is traced historically, together with statements of Government policy. The place of Magnox, AGR, SGHWR, PWR and fast breeder reactors is discussed. Advantages and problems associated with the various types are outlined. (U.K.)

  15. 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.)

  16. Reactor Materials Research

    International Nuclear Information System (INIS)

    Van Walle, E.

    2001-01-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  17. Fusion reactors - types - problems

    International Nuclear Information System (INIS)

    Schmitter, K.H.

    1979-07-01

    A short account is given of the principles of fusion reactions and of the expected advantages of fusion reactors. Descriptions are presented of various Tokamak experimental devices being developed in a number of countries and of some mirror machines. The technical obstacles to be overcome before a fusion reactor could be self-supporting are discussed. (U.K.)

  18. Reactor cost driving items

    International Nuclear Information System (INIS)

    Spears, W.R.

    1987-01-01

    Assuming that the design solutions presently perceived for NET can be extrapolated for use in a power reactor, and using costing experience with present day fusion experiments and with fission power plants, the major components of the cost of a tokamak fusion power reactor are described. The analysis shows the emphasis worth placing on various areas of plant design to reduce costs

  19. 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.)

  20. Reactor Materials Research

    Energy Technology Data Exchange (ETDEWEB)

    Van Walle, E

    2001-04-01

    The activities of the Reactor Materials Research Department of the Belgian Nuclear Research Centre SCK-CEN in 2000 are summarised. The programmes within the department are focussed on studies concerning (1) fusion, in particular mechanical testing; (2) Irradiation Assisted Stress Corrosion Cracking (IASCC); (3) nuclear fuel; and (4) Reactor Pressure Vessel Steel (RPVS)

  1. Space Nuclear Reactor Engineering

    Energy Technology Data Exchange (ETDEWEB)

    Poston, David Irvin [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2017-03-06

    We needed to find a space reactor concept that could be attractive to NASA for flight and proven with a rapid turnaround, low-cost nuclear test. Heat-pipe-cooled reactors coupled to Stirling engines long identified as the easiest path to near-term, low-cost concept.

  2. Reactor dynamics calculations

    International Nuclear Information System (INIS)

    Devooght, J.; Lefvert, T.; Stankiewiez, J.

    1981-01-01

    This chapter deals with the work done in reactor dynamics within the Coordinated Research Program on Transport Theory and Advanced Reactor Calculations by three groups in Belgium, Poland, Sweden and Italy. Discretization methods in diffusion theory, collision probability methods in time-dependent neutron transport and singular perturbation method are represented in this paper

  3. Defesa dos direitos humanos: sistemas regionais

    Directory of Open Access Journals (Sweden)

    Hélio Bicudo

    2003-04-01

    Full Text Available O texto discorre sobre a institucionalização dos sistemas de promoção dos Direitos Humanos, ao longo do século XX. Tomando a Declaração Universal dos Direitos do Homem, de 1948, como base e ponto de partida, o articulista aborda as três principais vertentes dos sistemas de promoção desses direitos: a européia, a americana e a africana. A evolução de cada uma delas descrita analógica e epistemologicamente, de forma a salientar singularidades sem perder de vista as influências recíprocas ou mesmo as determinantes próprias do contexto espaço-social. Para finalizar, o articulista destaca a importância do Tribunal Penal Internacional no estabelecimento de uma justiça ecumênica. Concomitantemente, alerta para o perigo contido na ameaça de os EUA não o ratificarem.The text underlines the institutional character acquired by the main systems to promote Human Rights in the twentieth century. Taking the Universal Human Rigths Declaration, of 1948, as the basis for analysis, the author brings up three different approaches to promote these rights: the European, the American and the African. The evolution of each of them is described using its procedure as a basic reference. Besides, an analogical analysis, brings to the fore singularities, without ignoring reciprocal influences dictated by particular contexts, though. The author stresses the importance of the International Penal Court, as a means to establish ecumenical justice. At the same time, he reminds the reader of the risks implicit in the possible non-ratification of the IPC by United States.

  4. A segunda alma do partido dos trabalhadores

    Directory of Open Access Journals (Sweden)

    André Singer

    2010-12-01

    Full Text Available Os dois mandatos de Lula formaram a síntese contraditória das "duas almas" que hoje habitam o PT. Foi o fato de ter implementado, simultaneamente, políticas que beneficiam o capital e promovem a inclusão dos mais pobres, com uma melhora relativa na situação dos trabalhadores, que permitiu a convivência dos princípios estabelecidos em sua fundação, no colégio Sion em 1980, e as diretrizes do programa de governo apresentadas em 2002 na convenção do Anhembi, em São Paulo.Lula's presidency seem to have blended PT's two apparently contradictory "souls". By implementing policies that favor capital while at the same time foster the social inclusion of the poor, and that have also improved working class citizens' life standards, Lula has been able, as a president, to preserve the ideals that animated the party's foundation and the more pragmatic programme for government set out in 2002.

  5. ESCRITORAS BAIANAS DOS OITOCENTOS ENFRENTANDO PRECONCEITOS

    Directory of Open Access Journals (Sweden)

    Helena Parente Cunha

    2017-05-01

    Full Text Available Tem sido a conquista dos últimos anos o reconhecimento das autoras brasileiras dos séculos passados, mias numerosas do que se supunha e que foram esquecidas devido aos preconceitos do canone Literário. A partir da segunda metade do século XIX, com o levantamento dos períodos em todo o país, dirigidos e editados por mulheres e para mulheres, veiculavam as ideias avançadas e, ao mesmo tempo, concepções do sistema patriarcado. O medo do corpo e do erotismo se transmite à produção literária feminina que, ao se inspirar no amor, quase sempre usa linguagem pudica, procuando santificar o sentimento. Mas não raro surgem passagens de uma audácia inesperada, num desafio ostensivo aos convencionalizmos do cânone comportamental. Estudam-se como as escritoreas Ana Ribeiro, Ildefonsa Laura César e Adelio Fonseca, dentro deste contexto

  6. Status of French reactors

    Energy Technology Data Exchange (ETDEWEB)

    Ballagny, A. [Commissariat a l`Energie Atomique, Saclay (France)

    1997-08-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm{sup 3}. The OSIRIS reactor has already been converted to LEU. It will use U{sub 3}Si{sub 2} as soon as its present stock of UO{sub 2} fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU.

  7. 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

  8. Iris reactor conceptual design

    International Nuclear Information System (INIS)

    Carelli, M.D.; Conway, L.E.; Petrovic, B.; Paramonov, D.V.; Galvin, M.; Todreas, N.E.; Lombardi, C.V.; Maldari, F.; Ricotti, M.E.; Cinotti, L.

    2001-01-01

    IRIS (International Reactor Innovative and Secure) is a modular, integral, light water cooled, low-to-medium power (100-350 MWe) reactor which addresses the requirements defined by the US DOE for Generation IV reactors, i.e., proliferation resistance, enhanced safety, improved economics and fuel cycle sustainability. It relies on the proven technology of light water reactors and features innovative engineering, but it does not require new technology development. This paper discusses the current reference IRIS design, which features a 1000 MWt thermal core with proven 5%-enriched uranium oxide fuel and five-year long straight burn fuel cycle, integral reactor vessel housing helical tube steam generators and immersed spool pumps. Other major contributors to the high level of safety and economic attractiveness are the safety by design and optimized maintenance approaches, which allow elimination of some classes of accidents, lower capital cost, long operating cycle, and high capacity factors. (author)

  9. The secure heating reactor

    International Nuclear Information System (INIS)

    Pind, C.

    1987-01-01

    The SECURE heating reactor was designed by ASEA-ATOM as a realistic alternative for district heating in urban areas and for supplying heat to process industries. SECURE has unique safety characteristics, that are based on fundamental laws of physics. The safety does not depend on active components or operator intervention for shutdown and cooling of the reactor. The inherent safety characteristics of the plant cannot be affected by operator errors. Due to its very low environment impact, it can be sited close to heat consumers. The SECURE heating reactor has been shown to be competitive in comparison with other alternatives for heating Helsinki and Seoul. The SECURE heating reactor forms a basis for the power-producing SECURE-P reactor known as PIUS (Process Inherent Ultimate Safety), which is based on the same inherent safety principles. The thermohydraulic function and transient response have been demonstrated in a large electrically heated loop at the ASEA-ATOM laboratories

  10. 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.

  11. Mirror reactor surface study

    Energy Technology Data Exchange (ETDEWEB)

    Hunt, A. L.; Damm, C. C.; Futch, A. H.; Hiskes, J. R.; Meisenheimer, R. G.; Moir, R. W.; Simonen, T. C.; Stallard, B. W.; Taylor, C. E.

    1976-09-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included.

  12. 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.)

  13. Reactor feedwater device

    International Nuclear Information System (INIS)

    Igarashi, Noboru.

    1986-01-01

    Purpose: To suppress soluble radioactive corrosion products in a feedwater device. Method: In a light water cooled nuclear reactor, an iron injection system is connected to feedwater pipeways and the iron concentration in the feedwater or reactor coolant is adjusted between twice and ten times of the nickel concentration. When the nickel/iron ratio in the reactor coolant or feedwater goes nearer to 1/2, iron ions are injected together with iron particles to the reactor coolant to suppress the leaching of stainless steels, decrease the nickel in water and increase the iron concentration. As a result, it is possible to suppress the intrusion of nickel as one of parent nuclide of radioactive nuclides. Further, since the iron particles intruded into the reactor constitute nuclei for capturing the radioactive nuclides to reduce the soluble radioactive corrosion products, the radioactive nuclides deposited uniformly to the inside of the pipeways in each of the coolant circuits can be reduced. (Kawakami, Y.)

  14. 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

  15. Reactor power control device

    International Nuclear Information System (INIS)

    Kobayashi, Akira.

    1980-01-01

    Purpose: To prevent misoperation in a control system for the adjustment of core coolant flow rate, and the increase in the neutron flux density caused from the misoperation in BWR type reactors. Constitution: In a reactor power control system adapted to control the reactor power by the adjustment of core flow rate, average neutron flux signals of a reactor core, entire core flow rate signals and operation state signals for coolant recycling system are inputted to a microcomputer. The outputs from the computer are sent to a recycling MG set speed controller to control the reactor core flow rate. The computer calculates the change ratio with time in the average neutron flux signals, correlation between the average neutron flux signals and the entire core flow rate signals, change ratio with time in the operation state signals for the coolant recycling system and the like and judges the abnormality in the coolant recycling system based on the calculated results. (Ikeda, J.)

  16. Fusion reactor pumped laser

    International Nuclear Information System (INIS)

    Jassby, D.L.

    1988-01-01

    A nuclear pumped laser is described comprising: a toroidal fusion reactor, the reactor generating energetic neutrons; an annular gas cell disposed around the outer periphery of the reactor, the cell including an annular reflecting mirror disposed at the bottom of the cell and an annular output window disposed at the top of the cell; a gas lasing medium disposed within the annular cell for generating output laser radiation; neutron reflector material means disposed around the annular cell for reflecting neutrons incident thereon back into the gas cell; neutron moderator material means disposed between the reactor and the gas cell and between the gas cell and the neutron reflector material for moderating the energy of energetic neutrons from the reactor; converting means for converting energy from the moderated neutrons to energy pumping means for pumping the gas lasing medium; and beam compactor means for receiving output laser radiation from the annular output window and generating a single output laser beam therefrom

  17. Reactor core cooling device

    International Nuclear Information System (INIS)

    Kobayashi, Masahiro.

    1986-01-01

    Purpose: To safely and effectively cool down the reactor core after it has been shut down but is still hot due to after-heat. Constitution: Since the coolant extraction nozzle is situated at a location higher than the coolant injection nozzle, the coolant sprayed from the nozzle, is free from sucking immediately from the extraction nozzle and is therefore used effectively to cool the reactor core. As all the portions from the top to the bottom of the reactor are cooled simultaneously, the efficiency of the reactor cooling process is increased. Since the coolant extraction nozzle can be installed at a point considerably higher than the coolant injection nozzle, the distance from the coolant surface to the point of the coolant extraction nozzle can be made large, preventing cavitation near the coolant extraction nozzle. Therefore, without increasing the capacity of the heat exchanger, the reactor can be cooled down after a shutdown safely and efficiently. (Kawakami, Y.)

  18. Mirror reactor surface study

    International Nuclear Information System (INIS)

    Hunt, A.L.; Damm, C.C.; Futch, A.H.; Hiskes, J.R.; Meisenheimer, R.G.; Moir, R.W.; Simonen, T.C.; Stallard, B.W.; Taylor, C.E.

    1976-01-01

    A general survey is presented of surface-related phenomena associated with the following mirror reactor elements: plasma first wall, ion sources, neutral beams, director converters, vacuum systems, and plasma diagnostics. A discussion of surface phenomena in possible abnormal reactor operation is included. Several studies which appear to merit immediate attention and which are essential to the development of mirror reactors are abstracted from the list of recommended areas for surface work. The appendix contains a discussion of the fundamentals of particle/surface interactions. The interactions surveyed are backscattering, thermal desorption, sputtering, diffusion, particle ranges in solids, and surface spectroscopic methods. A bibliography lists references in a number of categories pertinent to mirror reactors. Several complete published and unpublished reports on surface aspects of current mirror plasma experiments and reactor developments are also included

  19. Status of French reactors

    International Nuclear Information System (INIS)

    Ballagny, A.

    1997-01-01

    The status of French reactors is reviewed. The ORPHEE and RHF reactors can not be operated with a LEU fuel which would be limited to 4.8 g U/cm 3 . The OSIRIS reactor has already been converted to LEU. It will use U 3 Si 2 as soon as its present stock of UO 2 fuel is used up, at the end of 1994. The decision to close down the SILOE reactor in the near future is not propitious for the start of a conversion process. The REX 2000 reactor, which is expected to be commissioned in 2005, will use LEU (except if the fast neutrons core option is selected). Concerning the end of the HEU fuel cycle, the best option is reprocessing followed by conversion of the reprocessed uranium to LEU

  20. 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

  1. 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.)

  2. 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)

  3. 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.)

  4. 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)

  5. 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

  6. 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)

  7. Reactor performance calculations for water reactors

    International Nuclear Information System (INIS)

    Hicks, D.

    1970-04-01

    The principles of nuclear, thermal and hydraulic performance calculations for water cooled reactors are discussed. The principles are illustrated by describing their implementation in the UKAEA PATRIARCH scheme of computer codes. This material was originally delivered as a course of lectures at the Technical University of Helsinki in Summer of 1969.

  8. 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.)

  9. Fourth Generation Reactor Concepts

    International Nuclear Information System (INIS)

    Furtek, A.

    2008-01-01

    Concerns over energy resources availability, climate changes and energy supply security suggest an important role for nuclear energy in future energy supplies. So far nuclear energy evolved through three generations and is still evolving into new generation that is now being extensively studied. Nuclear Power Plants are producing 16% of the world's electricity. Today the world is moving towards hydrogen economy. Nuclear technologies can provide energy to dissociate water into oxygen and hydrogen and to production of synthetic fuel from coal gasification. The introduction of breeder reactors would turn nuclear energy from depletable energy supply into an unlimited supply. From the early beginnings of nuclear energy in the 1940s to the present, three generations of nuclear power reactors have been developed: First generation reactors: introduced during the period 1950-1970. Second generation: includes commercial power reactors built during 1970-1990 (PWR, BWR, Candu, Russian RBMK and VVER). Third generation: started being deployed in the 1990s and is composed of Advanced LWR (ALWR), Advanced BWR (ABWR) and Passive AP600 to be deployed in 2010-2030. Future advances of the nuclear technology designs can broaden opportunities for use of nuclear energy. The fourth generation reactors are expected to be deployed by 2030 in time to replace ageing reactors built in the 1970s and 1980s. The new reactors are to be designed with a view of the following objectives: economic competitiveness, enhanced safety, minimal radioactive waste production, proliferation resistance. The Generation IV International Forum (GIF) was established in January 2000 to investigate innovative nuclear energy system concepts. GIF members include Argentina, Brazil, Canada, Euratom, France Japan, South Africa, South Korea, Switzerland, United Kingdom and United States with the IAEA and OECD's NEA as permanent observers. China and Russia are expected to join the GIF initiative. The following six systems

  10. 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)

  11. 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)

  12. Disk Operating System--DOS. Teacher Packet. Learning Activity Packets.

    Science.gov (United States)

    Oklahoma State Dept. of Vocational and Technical Education, Stillwater. Curriculum and Instructional Materials Center.

    The Learning Activity Packets (LAPs) contained in this manual are designed to assist the beginning user in understanding DOS (Disk Operating System). LAPs will not work with any version below DOS Version 3.0 and do not address the enhanced features of versions 4.0 or higher. These elementary activities cover only the DOS commands necessary to…

  13. Camponeses e esquecimento na Antiguidade Tardia: as revoltas dos bagaudas e dos circunceliões

    Directory of Open Access Journals (Sweden)

    Uiran Gebara da Silva

    2016-12-01

    Full Text Available Esse artigo apresenta alguns dos problemas com os quais eu tive de lidar ao realizar um estudo comparativo entre dois conjuntos de revoltas rurais do Império Romano tardio: as revoltas dos bagaudas na Gália e dos circunceliões na África. O artigo toma como eixo articulador a hipótese lançada por E. A. Thompson sobre o papel do esquecimento na produção dos relatos antigos sobre os bagaudas e a problematiza. Num segundo momento o artigo trata do problema relacionado à compreensão do caráter social de ambos os grupos, levando em consideração os múltiplos relatos presentes nas fontes antigas e as divergentes interpretações modernas sobre eles, enfatizando a necessidade de se reconhecer a tópica da inversão social como um elemento que diferencia os relatos sobre os revoltosos daqueles sobre a bandidagem. Outro elemento importante é o reconhecimento da heterogeneidade dos discursos cristãos com relação às classes subalternas e aos revoltosos, que apontam não para um fortalecimento do patronato rural, mas para o enfraquecimento ou para a crise dessas relações no campo tardo-romano.

  14. Reactor safety protection system

    International Nuclear Information System (INIS)

    Nishi, Hiroshi; Yokoyama, Tsuguo.

    1989-01-01

    A plurality of neutron detectors are disposed around a reactor core and detection signals from optional two neutron detectors are inputted into a ratio calculation device. If the ratio between both of the neutron flux level signals exceeds a predetermined value, a reactor trip signal is generated from an alarm setting device. Further, detection signals from all of the neutron detection devices are inputted into an average calculation device and the reactor trip signal is generated also in a case where the average value exceeds a predetermined set value. That is, when the reactor core power is increased locally, the detection signal from the neutron detector nearer to the point of power increase is greater than the increase rate for the entire reactor core power, while the detection signal from the neutron detector remote from the point of power increase is smaller. Thus, the local power increase ratio in the FBR reactor core can be detected efficiently by calculating the ratio for the neutron flux level signals from two neutron detectors, thereby enabling to exactly recognize the local power increase rate in the reactor core. (N.H.)

  15. Nuclear reactor containing facility

    International Nuclear Information System (INIS)

    Hidaka, Masataka; Murase, Michio.

    1994-01-01

    In a reactor containing facility, a condensation means is disposed above the water level of a cooling water pool to condensate steams of the cooling water pool, and return the condensated water to the cooling water pool. Upon occurrence of a pipeline rupture accident, steams generated by after-heat of a reactor core are caused to flow into a bent tube, blown from the exit of the bent tube into a suppression pool and condensated in a suppression pool water, thereby suppressing the pressure in the reactor container. Cooling water in the cooling water pool is boiled by heat conduction due to the condensation of steams, then the steams are exhausted to the outside of the reactor container to remove the heat of the reactor container to the outside of the reactor. In addition, since cooling water is supplied to the cooling water pool quasi-permanently by gravity as a natural force, the reactor container can be cooled by the cooling water pool for a long period of time. Since the condensation means is constituted with a closed loop and interrupted from the outside, radioactive materials are never released to the outside. (N.H.)

  16. Method of reactor operation

    International Nuclear Information System (INIS)

    Maeda, Katsuji.

    1982-01-01

    Purpose: To prevent stress corrosion cracks in stainless steels caused from hydrogen peroxide in reactor operation in which the density of hydrogen peroxide in the reactor water is controlled upon reactor start-up. Method: A heat exchanger equipped with a heat source for applying external heat is disposed into the recycling system for reactor coolants. Upon reactor start-up, the coolants are heated by the heat exchanger till arriving at a temperature at which the dissolving rate is faster than the forming rate of hydrogen peroxide in the coolants, and nuclear heating is started after reaching the above temperature. The temperature of the reactor water is increased in such a manner and, when it arrives at 140 0 C, extraction of control elements is started and the heat source for the heat exchanger is interrupted simultaneously. In this way spikes in the density of hydrogen peroxide are suppressed upon reactor start-up to thereby decrease the stress corrosion cracks in stainless steels. (Horiuchi, T.)

  17. Nuclear reactor control column

    International Nuclear Information System (INIS)

    Bachovchin, D.M.

    1982-01-01

    The nuclear reactor control column comprises a column disposed within the nuclear reactor core having a variable cross-section hollow channel and containing balls whose vertical location is determined by the flow of the reactor coolant through the column. The control column is divided into three basic sections wherein each of the sections has a different cross-sectional area. The uppermost section of the control column has the greatest crosssectional area, the intermediate section of the control column has the smallest cross-sectional area, and the lowermost section of the control column has the intermediate cross-sectional area. In this manner, the area of the uppermost section can be established such that when the reactor coolant is flowing under normal conditions therethrough, the absorber balls will be lifted and suspended in a fluidized bed manner in the upper section. However, when the reactor coolant flow falls below a predetermined value, the absorber balls will fall through the intermediate section and into the lowermost section, thereby reducing the reactivity of the reactor core and shutting down the reactor

  18. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two dramatic demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the Integral Fast Reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics and also makes possible a simplified closed fuel cycle and waste process improvements

  19. The integral fast reactor

    International Nuclear Information System (INIS)

    Till, C.E.

    1987-01-01

    On April 3rd, 1986, two demonstrations of the inherent capability of sodium-cooled fast reactors to survive unprotected loss of cooling accidents were carried out on the experimental sodium-cooled power reactor, EBR-II, on the Idaho site of Argonne National Laboratory. Transients potentially of the most serious kind, one an unprotected loss of flow, the other an unprotected loss of heat sink, both initiated from full power. In both cases the reactor quietly shut itself down, without damage of any kind. These tests were a part of the on-going development program at Argonne to develop an advanced reactor with significant new inherent safety characteristics. Called the integral fast reactor, or IFR, the basic thrust is to develop everything that is needed for a complete nuclear power system - reactor, closed fuel cycle, and waste processing - as a single optimized entity, and, for simplicity in concept, as an integral part of a single plant. The particular selection of reactor materials emphasizes inherent safety characteristics also makes possible a simplified close fuel cycle and waste process improvements. The paper describes the IFR concept, the inherent safety, tests, and status of IFR development today

  20. Reactor power control device

    International Nuclear Information System (INIS)

    Imaruoka, Hiromitsu.

    1994-01-01

    A high pressure water injection recycling system comprising injection pipelines of a high pressure water injection system and a flow rate control means in communication with a pool of a pressure control chamber is disposed to a feedwater system of a BWR type reactor. In addition, the flow rate control means is controlled by a power control device comprising a scram impossible transient event judging section, a required injection flow rate calculation section for high pressure water injection system and a control signal calculation section. Feed water flow rate to be supplied to the reactor is controlled upon occurrence of a scram impossible transient event of the reactor. The scram impossible transient event is judged based on reactor output signals and scram operation demand signals and injection flow rate is calculated based on a predetermined reactor water level, and condensate storage tank water or pressure control chamber pool water is injected to the reactor. With such procedures, water level can be ensured and power can be suppressed. Further, condensate storage tank water of low enthalpy is introduced to the pressure suppression chamber pool to directly control elevation of water temperature and ensure integrity of the pressure vessel and the reactor container. (N.H.)

  1. Reactor water sampling device

    International Nuclear Information System (INIS)

    Sakamaki, Kazuo.

    1992-01-01

    The present invention concerns a reactor water sampling device for sampling reactor water in an in-core monitor (neutron measuring tube) housing in a BWR type reactor. The upper end portion of a drain pipe of the reactor water sampling device is attached detachably to an in-core monitor flange. A push-up rod is inserted in the drain pipe vertically movably. A sampling vessel and a vacuum pump are connected to the lower end of the drain pipe. A vacuum pump is operated to depressurize the inside of the device and move the push-up rod upwardly. Reactor water in the in-core monitor housing flows between the drain pipe and the push-up rod and flows into the sampling vessel. With such a constitution, reactor water in the in-core monitor housing can be sampled rapidly with neither opening the lid of the reactor pressure vessel nor being in contact with air. Accordingly, operator's exposure dose can be reduced. (I.N.)

  2. Reactor container cooling device

    Energy Technology Data Exchange (ETDEWEB)

    Ando, Koji; Kinoshita, Shoichiro

    1995-11-10

    The device of the present invention efficiently lowers pressure and temperature in a reactor container upon occurrence of a severe accident in a BWR-type reactor and can cool the inside of the container for a long period of time. That is, (1) pipelines on the side of an exhaustion tower of a filter portion in a filter bent device of the reactor container are in communication with pipelines on the side of a steam inlet of a static container cooling device by way of horizontal pipelines, (2) a back flow check valve is disposed to horizontal pipelines, (3) a steam discharge valve for a pressure vessel is disposed closer to the reactor container than the joint portion between the pipelines on the side of the steam inlet and the horizontal pipelines. Upon occurrence of a severe accident, when the pressure vessel should be ruptured and steams containing aerosol in the reactor core should be filled in the reactor container, the inlet valve of the static container cooling device is closed. Steams are flown into the filter bent device of the reactor container, where the aerosols can be removed. (I.S.).

  3. 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.)

  4. Reactor feedwater control device

    International Nuclear Information System (INIS)

    Koshi, Yuji.

    1993-01-01

    In the device of the present invention, an excess response is not caused in a reactor feed water system even when voids are fluctuated by using an actual water level signal as a reactor water level signal. That is, a standard water level signal and a reactor water level signal are inputted to a comparator. An adder adds water level difference signal outputted from the comparator and mismatch flow rate signal prepared by multiplying the difference between a main steam flow rate signal and a feed water flow rate signal by a mismatch gain. A feed water controller integrates the added signal and outputs flow rate demand signal. A feed water system receives the flow rate demand signal as input. A water level calculation means is disposed to such a device for calculating an actual water level based on the change of coolant possessing amount of the reactor, and the output thereof is defined as a reactor water level signal. With such procedures, excessive elevation of water level of the reactor can be prevented even upon occurrence of void fluctuation phenomenon or the like in the reactor such as upon sole scram operation. Accordingly, plant shut down caused thereby can be avoided safely. (I.S.)

  5. 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.)

  6. Heterogeneous gas core reactor

    International Nuclear Information System (INIS)

    Han, K.I.

    1977-01-01

    Preliminary investigations of a heterogeneous gas core reactor (HGCR) concept suggest that this potential power reactor offers distinct advantages over other existing or conceptual reactor power plants. One of the most favorable features of the HGCR is the flexibility of the power producing system which allows it to be efficiently designed to conform to a desired optimum condition without major conceptual changes. The arrangement of bundles of moderator/coolant channels in a fissionable gas or mixture of gases makes a truly heterogeneous nuclear reactor core. It is this full heterogeneity for a gas-fueled reactor core which accounts for the novelty of the heterogeneous gas core reactor concept and leads to noted significant advantages over previous gas core systems with respect to neutron and fuel economy, power density, and heat transfer characteristics. The purpose of this work is to provide an insight into the design, operating characteristics, and safety of a heterogeneous gas core reactor system. The studies consist mainly of neutronic, energetic and kinetic analyses of the power producing and conversion systems as a preliminary assessment of the heterogeneous gas core reactor concept and basic design. The results of the conducted research indicate a high potential for the heterogeneous gas core reactor system as an electrical power generating unit (either large or small), with an overall efficiency as high as 40 to 45%. The HGCR system is found to be stable and safe, under the conditions imposed upon the analyses conducted in this work, due to the inherent safety of ann expanding gaseous fuel and the intrinsic feedback effects of the gas and water coolant

  7. 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

  8. Necessity of research reactors

    International Nuclear Information System (INIS)

    Ito, Tetsuo

    2016-01-01

    Currently, only three educational research reactors at two universities exist in Japan: KUR, KUCA of Kyoto University and UTR-KINKI of Kinki University. UTR-KINKI is a light-water moderated, graphite reflected, heterogeneous enriched uranium thermal reactor, which began operation as a private university No. 1 reactor in 1961. It is a low power nuclear reactor for education and research with a maximum heat output of 1 W. Using this nuclear reactor, researches, practical training, experiments for training nuclear human resources, and nuclear knowledge dissemination activities are carried out. As of October 2016, research and practical training accompanied by operation are not carried out because it is stopped. The following five items can be cited as challenges faced by research reactors: (1) response to new regulatory standards and stagnation of research and education, (2) strengthening of nuclear material protection and nuclear fuel concentration reduction, (3) countermeasures against aging and next research reactor, (4) outflow and shortage of nuclear human resources, and (5) expansion of research reactor maintenance cost. This paper would like to make the following recommendations so that we can make contribution to the world in the field of nuclear power. (1) Communication between regulatory authorities and business operators regarding new regulatory standards compliance. (2) Response to various problems including spent fuel measures for long-term stable utilization of research reactors. (3) Personal exchanges among nuclear experts. (4) Expansion of nuclear related departments at universities to train nuclear human resources. (5) Training of world-class nuclear human resources, and succession and development of research and technologies. (A.O.)

  9. 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)

  10. Nuclear reactor safety system

    International Nuclear Information System (INIS)

    Ball, R.M.; Roberts, R.C.

    1983-01-01

    The invention provides a safety system for a nuclear reactor which uses a parallel combination of computer type look-up tables each of which receives data on a particular parameter (from transducers located in the reactor system) and each of which produces the functional counterpart of that particular parameter. The various functional counterparts are then added together to form a control signal for shutting down the reactor. The functional counterparts are developed by analysis of experimental thermal and hydraulic data, which are used to form expressions that define safe conditions

  11. Fast breeder reactor

    International Nuclear Information System (INIS)

    Ito, Shin-ichi; Maki, Koichi.

    1975-01-01

    Object: To conserve loaded fuel, aquire controllable surplus reaction degree, increase the breeding index, flatten output and improve sealing of neutrons by inserting a decelerating substance in a blanket section. Structure: A decelerating substance such as beryllium or beryllium oxide is inserted in a blanket section between an outer reactor core and reflector. With this arrangement, neutrons are decelerated to increase the low energy components, which are partly subjected to reflection by the outer reactor core to thereby reduce leakage of neutrons from the reactor core. (Kamimura, M.)

  12. Fast Breeder Reactor studies

    International Nuclear Information System (INIS)

    Till, C.E.; Chang, Y.I.; Kittel, J.H.; Fauske, H.K.; Lineberry, M.J.; Stevenson, M.G.; Amundson, P.I.; Dance, K.D.

    1980-07-01

    This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts

  13. Inherently safe reactors

    International Nuclear Information System (INIS)

    Maartensson, Anders

    1992-01-01

    A rethinking of nuclear reactor safety has created proposals for new designs based on inherent and passive safety principles. Diverging interpretations of these concepts can be found. This article reviews the key features of proposed advanced power reactors. An evaluation is made of the degree of inherent safety for four different designs: the AP-600, the PIUS, the MHTGR and the PRISM. The inherent hazards of today's most common reactor principles are used as reference for the evaluation. It is concluded that claims for the new designs being inherently, naturally or passively safe are not substantiated by experience. (author)

  14. Reactor utilization, Part 1

    International Nuclear Information System (INIS)

    Martinc, R.; Stanic, A.

    1981-01-01

    The reactor operating plan for 1981 was subject to the needs of testing operation with the 80% enriched fuel and was fulfilled on the whole. This annex includes data about reactor operation, review of shorter interruptions due to demands of the experiments, data about safety shutdowns caused by power cuts. Period of operation at low power levels was used mostly for activation analyses, and the operation at higher power levels were used for testing and regular isotope production. Detailed data about samples activation are included as well as utilization of the reactor as neutron source and the operating plan for 1982 [sr

  15. Reactor BR2: Introduction

    International Nuclear Information System (INIS)

    Gubel, P.

    2000-01-01

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

  16. Research reactor support

    International Nuclear Information System (INIS)

    2005-01-01

    Research reactors (RRs) have been used in a wide range of applications including nuclear power development, basic physics research, education and training, medical isotope production, geology, industry and other fields. However, many research reactors are fuelled with High Enriched Uranium (HEU), are underutilized and aging, and have significant quantities of spent fuel. HEU inventories (fresh and spent) pose security risks Unavailability of a high-density-reprocessable fuel hinders conversion and limits back-end options and represents a survival dilemma for many RRs. Improvement of interim spent fuel storage is required at some RRs. Many RRs are under-utilized and/or inadequately funded and need to find users for their services, or permanently shut down and eventually decommission. Reluctance to decommission affect both cost and safety (loss of experienced staff ) and many shut down but not decommissioned RR with fresh and/or spent fuel at the sites invoke serious concern. The IAEA's research reactor support helps to ensure that research reactors can be operated efficiently with fuels and targets of lower proliferation and security concern and that operators have appropriate technology and options to manage RR fuel cycle issues, especially on long term interim storage of spent research reactor fuel. Availability of a high-density-reprocessable fuel would expand and improve back end options. The International Atomic Energy Agency provides assistance to Member States to convert research reactors from High Enriched Uranium fuel and targets (for medical isotope production) to qualified Low Enriched Uranium fuel and targets while maintaining reactor performance levels. The assistance includes provision of handbooks and training in the performance of core conversion studies, advice for the procurement of LEU fuel, and expert services for LEU fuel acceptance. The IAEA further provides technical and administrative support for countries considering repatriation of its

  17. Nuclear reactor theory

    International Nuclear Information System (INIS)

    Sekimoto, Hiroshi

    2007-09-01

    This textbook is composed of two parts. Part 1 'Elements of Nuclear Reactor Theory' is composed of only elements but the main resource for the lecture of nuclear reactor theory, and should be studied as common knowledge. Much space is therefore devoted to the history of nuclear energy production and to nuclear physics, and the material focuses on the principles of energy production in nuclear reactors. However, considering the heavy workload of students, these subjects are presented concisely, allowing students to read quickly through this textbook. (J.P.N.)

  18. Power reactor design trends

    International Nuclear Information System (INIS)

    Hogan, W.J.

    1985-01-01

    Cascade and Pulse Star represent new trends in ICF power reactor design that have emerged in the last few years. The most recent embodiments of these two concepts, and that of the HYLIFE design with which they will compare them, are shown. All three reactors depend upon protecting structural elements from neutrons, x rays and debris by injecting massive amounts of shielding material inside the reaction chamber. However, Cascade and Pulse Star introduce new ideas to improve the economics, safety, and environmental impact of ICF reactors. They also pose different development issues and thus represent technological alternatives to HYLIFE

  19. Reactor power control system

    International Nuclear Information System (INIS)

    Tomisawa, Teruaki.

    1981-01-01

    Purpose: To restore reactor-power condition in a minimum time after a termination of turbine bypass by reducing the throttling of the reactor power at the time of load-failure as low as possible. Constitution: The transient change of the internal pressure of condenser is continuously monitored. When a turbine is bypassed, a speed-control-command signal for a coolant recirculating pump is generated according as the internal pressure of the condenser. When the signal relating to the internal pressure of the condenser indicates insufficient power, a reactor-control-rod-drive signal is generated. (J.P.N.)

  20. Reactors of the world

    International Nuclear Information System (INIS)

    1971-01-01

    Basic data relating to 127 power reactors in 15 countries which are expected to be in operation at the end of this year, with a total installed electrical generating capacity of 35 340.15 MW(e), and a listing of 361 research reactors in 46 countries are given in the 1971 edition of the IAEA handbook, Power and Research Reactors in Member States, which has just been published. This edition, the fourth, was prepared especially for the Fourth International Conference on the Peaceful Uses of Atomic Energy. (author)